View source for PY-CEI-NRR-0688, Forwards Summary Rept for 1986 Safety Evaluations Performed Subsequent to Receiving Full Power License on 860318,per 10CFR50.59(b)(2).No Unreviewed Safety Question Identified in 498 Safety Evaluations Performed in 1986

{{Adams
| number = ML20237J195
| issue date = 08/31/1987
| title = Forwards Summary Rept for 1986 Safety Evaluations Performed Subsequent to Receiving Full Power License on 860318,per 10CFR50.59(b)(2).No Unreviewed Safety Question Identified in 498 Safety Evaluations Performed in 1986
| author name = Edelman M
| author affiliation = CLEVELAND ELECTRIC ILLUMINATING CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000440
| license number = 
| contact person = 
| document report number = PY-CEI-NRR-0688, PY-CEI-NRR-688, NUDOCS 8709030519
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 278
}}

=Text=
{{#Wiki_filter:_ _____ ____________ _-
l THE CLEVELAND ELECTRIC ILLUMIN ATING COMP ANY P.O. Box 5000 - CLEVELANo, OHIO 44101 - TELEPHONE (216) 622 9800 - ILLUMINATING BLOG.                       - 55 PUBLICSoVARE Serving The Best Location in the Nation MURRAY R. EDELMAN sa vcontscent Au8ust 31, 1987 NUCLEAR                                                  PY-CEI/NRR-0688 L Document Control Desk U.S. Nuclear Regulatory Commission Washington, D. C.           20555 Perry Nuclear Power Plant Docket No. 50-440 Annual Report of 10 CFR 50.59 Safety Evaluations for 1986 Gentlemen:
Pursuant to 10 CFR 50.59(b)(2), attached is our sommary report for 1986 safety evaluations performed subsequent to our full power operating license
   \                    (March 18, 1986).
* In accordance with approved procedures, each plant modification, instruction change, or test change was first screened by an f                       applicability check for 10 CFR 50.59(a)(1) threshold criteria. All those meeting the threshold criteria were further evaluated pursuant to 10 CFR 50.59(a)(2) criteria and are summarized herein.                       For this time period a total of 498 safety evaluations were performed, none of which resulted in the identification of an unreviewed safety question.
Please feel f ree to contact me if you have any questions or comment.s.
Very truly        ts, JIr Murray R. Edel n Senior Vice President Nuclear Group MRE:njc Attachments cc:    T. Colburn K. Connaughton USNRC, Region III 8709030519 870831 PDR      ADOCK 05000440 P                         PDR    ,

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"                                                                 Attachment 1 PY-CEI/NRR-0688 L 1986 Perry Safety Evaluations by Category The 498 safety evaluations tabulated below are divided into 9 major categories. Some of these categories could have been reduced to a single' overall summary (e.g. Hilti Bolt modifications) which would have significantly compacted this submittal. Also, evaluations of the same change by different disciplines are separately described. Future 50.59 Report's vill be evaluated
       'for such reductions in volume.
Category                                                        Number
: 1.   -Design Changes (except Hilti Bolts & setpoint changes)     209
: 2. Design Document Changes (clarification or as-built)         91
: 3. Hilti Bolts                                                 23 l:      4. Set Point Changes                                           44 l;      5. FSAR Clarification (nontechnical)                           29 1,   s
       -6. Procedure / Instruction Changes                             31 7     Emergency Plan Changes                                       6
: 8. Preoperational/Startup Test changes
* 37
       -9. Temporary Changes                                           28
* Previously submitted in accordance with License Condition 2.C(4).
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                                                                                                                                              .1 1
FORMAT DESCRIPTION L-l     .
Each 50.59. Safety Evaluation summary is presented in the same format as follows:                                                                        ;
l SE N0;               A sequentially assigned number from one (001) to 535, preceded by the year;.e.g. 86-025 Source Document: There are several sources of evaluations which are abbreviated as shown:                                      ,
DCP - Design Change Package DCN - Drawing Change Notice
'f-                                                                 EPI - Engir.eering Plan Instruction SCR - Setpoint Change. Request                                            i SOI - Standard Operating Instruction                                      <
FSAR CR - Final Safety' Analysis Report Change Request ERDR ~ Engineering Design Deviation Request HFI - Hechanical Foreign Item PEI - Plant-Emergency Instruction TCN --Test Change Notice SXI - Special Test Instruction LL & J - Lifted Lead and Jumper NR-PPDS - Nonconformance Repor'. Perry Plant Department Safety-Related NR-MHQS - Nonconformance Report Maintenance & Modification Quality Safety-Related                                         '
HPL - Multiple Plant Listing                                              !
Description of Change:
A short narrative describing the location and type of. plant change. For multiple evaluations the discipline is identified in parenthesis like           l
    ,                                                         (Hechanical Evaluation).
Summary 1       Response to 10 CFR 5.59(a)(2)(1) - is the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report increased?
II      Response to 10 CFR 50.59(a)(2)(ii) - is there a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report created?
l III    Response to 10 CFR 50.59(a)(2)(iii) - is the margin of safety as        j defined in the basis for any technical specification reduced?             ,
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1 Attachment 2 PY-CEI/NRR-0688 L   j l
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l                        PERRY NUCLEAR POVER PLANT                     l l
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l SAFETY EVALUATION 

==SUMMARY==

PURSUANT TO l
10 CFR 50.59(b)(2) 1986

1 SE No.:    86-001 Source Document:      DCP 86-0140, Rev. O Description of Change                                                                             ;
1 The OG50-F120A/B valves in the Liquid Radvaste System corroded due to the                    1 type of fluids being processed. These valves were initially purchased with carbon steel bodies (butt veld) that were unlined and vere replaced vith flanged lined valves under this design change.
Summary s
I. No. This design change improves the system integrity and does not introduce a potential for a greater probability of occurrence or                      i consequence of an accident or malfunction above those defined in the FSAR.                                                                                ,
f II. No. This design change does not alter the general radvaste process path and equipment function or pose an accident or malfunction potential of a different type than evaluated in the FSAR.
III. No. Radvaste release limits and margins are not compromised by this design change. Liquid radvaste process shielding and redundancy are not compromised.
SE No.:    86-002 Source Documer.t :    DCN 570 Description of Change Drawing changes, associated with valves and piping for flov elements.in the non-safety Steam Seal System, were made to clarify actual pipe and valve sizes (Numerous Drawings affected).
Summary                                                                                          i I. No. Draving changes simply clarify actual pipe and valve sizes associated with flov elements. The Steam Seal System is non-safety.                   .
II. No. See I above. Already evaluated in Chapter 15 of the FSAR.
The components simply measure flov and do not involve the Technical III. No.
Specifications.
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l SE No.:      86-003 Source Document:          EPI Al, Rev. 1, TC6 Description of Change 1
l                        Change to an Emergen;y Plan Instruction, Emergency Action Levels, to specify time limits for how long the Safety Parameter Display System (SPDS).can be lost before an Unusual Event must be declared.
Summary I. No. The availability of SPDS vas not used when evaluating occurrence probabilities or accident consequences for the FSAR.
                    .II. No. See I above.
III. No.      The SPDS is not a listed Technical Specification system.
i SE No.:       86-004 Source Document:          PNPP Emergency Plan, Rev. 5, TCl Description of Change l
Change to the Emergency Plan, Emergency Action Levels, to specify time limits for how long the. Safety Parameter Display System (SPDS) can be lost before an Unusual Event v.ust be declared.
Summary l                      I. No. The availability of SPDS vas not used when evaluating occurrence l                                 probabilities or accident consequences for the FSAR.
II. No.      See I above.
III. No. The SPDS is not a listed Technical Specification system.
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SE'No.:         86-005 Source Document:           FSAR CR No. 696
                              ~ Description of Change "Within" vas changed to "for at least" in FSAR Section 8.3.1.1.5.2 to allow for a clarification of the intent of the preoperational test described in FSAR Section 14.2.12.1.9. This test verifies that the
                                     . Reactor Protection System can perform within its design specification
( i . e '. there is at least 2 seconds from the initiation of an RPS HG stop  l l                                     signal until a 5% undervoltage or underfrequency signal is generated).
Summary I. No.        The consequences vould be decreased as the length of time the voltage remains for the RPS is extended after a power failure.
II..No.        See I above.
III. No.        The margin of safety is not reduced.
SE No.:         86-006 Source Document:            S0I F42, Rev. 3 Description of Change The' System Operating Instruction (SOI) for the Inclined Fuel Transfer System (IFTS) allows for the moving of the IFTS carriage to a safe position during a logic controller failure.       In order to perform this
,                                      move, the SOI allows jumpers to be used which alters the automatic i
interlock functions as describe d ~ in FSAR 9.1.4.
Summary
                                 ,I. No. Since the IFTS carriage is being moved to a safe position, the probability of occurrence or the .onsequence of an accident or malfunction is not increased.                                        l II. No.         See I above.
III. No.        The. Technical Specifications for the IFTS are based on overexposure of personnel to radiation, and are not affected by this change.
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SE No.:      86-007
                                . Source Document:           DCP 85-0725, Rev. 0                                                                                                                        l
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Description of Change J
Design change to the Leak Detection System floor drain piping to reroute
                                          .dryvell cooler leak detection piping to " dirty" radvaste drains and the                                                                                   i Fuel Pool Cooling and Cleanup funnel outlet piping to " clean" radvaste drains.     (I6C Evaluation)
Summary I. No. The design change involves the segregation of leakage for the
                                                .radvaste drains and does not increase the probability of occurrence or the. consequences of an accident or equipment malfunction                                                                                         i important to safety.
II. No. Change involves only the segregation of leakage for the minor flow stream within the " clean" and " dirty" radvaste drain' systems.
III. No. The margin of safety is not reduced.
SE No.:     86-008
                                   ' Source Document:         PEI's B13, E12, G42, D23-1, D23-2, D23-3 Description of Change Evaluation of items identified as discrepancies between Rev. 1 of various Plant Emergency Instructions (i.e., B13, E12, G42, D23-1, D23-2, D23-3) and the Perry Specific Techaical guidtlines.
Summary I. No. The Plant Emergency Instructions direct operator actions for events not described in the FSAR.
II. No. See III below.
III. No. Since the changes involved were either administrative                                                                                               l (typographical, roundoffs, etc.), corrections or additional                                                                                        l' conservatism, there is no reduction in the margin of safety as defined in the bases for any Technical Specification.
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SE No.:      86-009 Source Document:        SCR 1-85-508 l
Description of Change f
1 Evaluation of the setpoint for the relief valve 1E51F017 (RCIC System) which was increased to 100 psig to prevent the inadvertent lifting of the relief valve due to insufficient margin between system normal operating conditions and relief valve setpoint. This setpoint change to 100 psig                                                                            )
is well within the 125 psig design pressure specified by the piping design specification.
Summary I. No. The changing of the rellet valve'setpoint to 100 psig does not increase the probability of an accident or malfunction of any components required for safety as evaluated by the FSAR. This setpoint change to 100 psig is well within the 125 psig design pressure specified by the piping design specification.                                                                                     !
II. No. See I above.
1 III. No. .This change enhances the system's operation and vill not reduce the margin of safety utilized by any Technical Specification.
SE No.:      86-010 Source Document:        SOI H25/H26, Rev. 5 Description of Change                                                                                                                                  l The System Operating Instruction (Revision 5) for the Control Room HVAC/Emeegency Recirculation System shovs that upon loss of off-site power, the Control Room HVAC automatically starts in the Emergency Recirculation mode rather than the normal mode (as stated in the FSAR).
This is due to a toxic gas initiation signal caused when the ethylene oxide monitor de-energizes on loss of its non-nuclear safety bus (See also SE 86-017).
Summary I. No. This configuration places the equipment in a higher degree of readiness to mitigate an accident,                                                                                                         t II. No. See I above.
III. No. This is not addressed in the bases for any Technical Specifications.

SE No.:        86-011 Source Document:          FSAR CR No. 871 Description of Change Evaluation of the description of the off-gas retreatment radiation monitor in the FSAR Section 11.5.2.2.1 which does not reflect plant drawings and configuration.
Summary I. No. The trip outputs are used for alarm function only.
II. No. Monitor has no trip functions that can cause an accident or                                                      ,
malfunction.
III. No.       The monitor performs its intended function.
SE No.:        86-012 Source Document:          TTI-0006 Description of Change Evaluation of the performance of Generator Bus Relay Load Check Technical Test Instruction. The purpose of this one time test is to load check the 1-PY-G 87U relay, 1-PY-T 87T relay and 3-PY-Bus 87B relay. The test was completed and the instruction cancelled on 4-12-86.
Summary I. No. One source of electrical power from the off-site power grid remains during performance of this test.
II. No. No new failure mode is introduced by performance of this instruction.
III. No. The margin of safety is not reduced.
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l SE No.:    86-013                                                                                     j Source Document:      FSAR CR No. 854 l
Description of Change Evaluation of additional clarification which was provided to FSAR                                j l              Table 1.8-1, Degree of Conformance for Regulatory Guide 1.105 on
;              Instrument Setpoints, as follows: " Security Devices per Regulatory                              .
I I              Position C.5 may not be provided on the setpoint adjustment mechanism.
!              Safety Related Equipment has been seismically qualified for its function per IEEE-344-1975. This' qualification documentation demonstrates adequate design without the use of a securing device."
Summary I. No. Design, experience and seismically qualified equipment should be                           ;
sufficient for use of the equipment without a locking device on the                        !
setpoint mechanism.
II. No. Setpoint accuracy and drift have been taken into account as part of the calculation for the setpoint value.
III. No. Setpoints in the Technical Specification already take into account instrument accuracy and drift without the use of a securing device.
SE No.:    86-016 Source Document:      ONI-S11 Description of Change Evaluation of FSAR Section 6.4.2.2.1 and the Off-Normal Instruction for Loss of Off-site Power (LOOP), which describes the operation of the                               3 Control Room HVAC System following a LOOP as a return to Normal Operation. System drawings indicate that the Control Room HVAC System vill restart in the Emergency Recirculation mode.
Summary 4
I. No. The system drawing configuration does not increase the equipment use beyond that required.                                                                        I II. No. See I above.
III. No. Technical Specification bases for the Control Room Emergency Recirculation System is concerned with radiation exposure post design basis accidents. Operation of the Recirculation System due to a LOOP condition does not affect the Technical Specification bases.

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SE'No.:        86-017 Source Documents'          FSAR CR No. 869
!          D'escription of Change FSAR Sectinn 6.4.~2.2.1, Control Room HVAC System, stated that, "In a LOOP condition:the_ standby set of supply and return' fans are_ started..." The
                 'as-built drawings show that in a LOOP condition the ethylene oxide.
monitor repeater relay (which'is normally. energized) vill.de-energize.due
                 .to being povered from a non-safety bus,' indicating toxic gas and activatingLthefemergency : recirculation. mode of f the Control = Room HVAC 1
System.. The'FSAR was changed to reflect.the as-built drawings.
1 Summary L             1. No.      The as-built drawing configuration does not ~ increase the equipment l',      .
use beyond that required.
II.' No.      See I above.
III. No.        Technical. Specification bases for the Control. Room Emergency i-Recirculation System is concerned with radiation exposure post design basis accidents.- Operation of the Recirculation System due'       ;
to a. LOOP condition does not affect the Technical Specification basis.
St No.:        86-018 Source Document:=          DCP 86-0094, Rev. O if          Description of Change                                                                 ~
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Design change to be made to the mechanical vacuum pumps in the Condenser Air' Removal System to allow for the removal'and-replacement of sight glass without dameging the sight glass. Threadti unions are.to be installed between the tanks and sight glass isolation valves.
l           Summary I.'No.       Addition of union in separator tank line vill not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in FSAR since the mechanical vacuum pumps are not involved.in an FSAR evaluation.
4      II. No.       The addition of union in separator tank line vill not create an accident other than that already described in the PSAR.
III. No.        Hechanical vacuum pumps are not described in the Technical Specifications.
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SE No.:    86-019                                                                                                                                             :
Source Document:      DCP 85-0694, Rev; 1 Des'cription of Change Design change to allow for the installation of supply diffuser, exhaust registers and ductvork in the Controlled Access Area HVAC System to provide for proper airflow direction and elimination of noise problems.
Summary I. No. This system is non-safety related and'is not required for the safe                                                                                >
shutdown of the plant.
II. No. The change affects only airflow in select areas of the control complex. The overall system function vill remain the same.
III. No. This system is not covered by Technical Specifications.
l SE No.:    86-0020 Source Document:      SOI F11/F15 Description of Change FSAR Section 9.1 states that lifting of the Lover Fuel Pool gates will be performed by the fuel handling platform. The change made to the System                                                                                 l Operating Instruction (50I) states that the mobile crane is used to raise and lover the. Lover Fuel Pool gates.
Summary I. No. This change applies only with no irradiated fuel present.
II. No. See I above.
III. No. See I above.
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r SE No.:                86-021 Source Document:                    PNPP Emergency Plan, Rev. 5, TC #2 Description of Change Change to the PNPP Emergency Plan which specified time limits on.how long the Safety Parame:er Display System (SPDS) can be lost or unavailable before an Unusual Event must be declared to now state;that an Unusual Event must be declared upon loss of the Safety Parameter Display System                 l of ERIS with the concurrent loss of both the Private Branch Exchange (PBX) and Microwave (0PX) Telephone Systems.                                            <
Summary I. No. The availability of the SPDS is not described in the FSAR.
II. No. See I above.
III, No.              The SPDS is not a Technical Specification described system.
SE No.:              86-022 Source Document:                  EPI-A1, Rev. 1, TC #7 Description of Change Change to the PNPP Emerger.cy Plan Instructions (Emergency Action Levels) which specified time limits on hov lung the Safety Parameter Display System (SPDS) can be lost or unavailable before an Unusual Event must be declared to now state that an Unusual Eve.nt must be declared upon loss of the Safety Parameter Display System of ERIS with the concurrent loss of.
both the Private ' Branch Exchange (PBX) and liicrowave (0PX) Telephone System.
     . Summary I. No,   The availability of the SPDS is not described in the FSAR.
II. No. See I above.
III. No.            The SPDS is not a Technical Specification described system.
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l-SE'No.:    86-023 Source Document:      DCN 0610                                                                                                                      ;
j I  Description of Change Drawing change (D302-872) of symbols from gate valves to globe valves.
1 Summary L
I. No. Not important to safety as evaluated in FSAR.
II. No. There is no relationship to an accident or malfunction of a different type, i
l  III. No. The margin of safety is not reduced.
SE No.:    86-024 Source Document:      STI-0V-200, Rev. 1 Description of Change i
Evaluation of allovance made.for refueling equipment to be declared                                                                           !
operable without the refueling bridge travel computer as required by the System Test Instruction.-
Summary I. No. The purpose of the travel computer limits is to prevent damage to                                                                       ;
irradiated fuel. No operations vill be performed with irradiated fuel.
II. No. Since irradiated fuel vill not be moved, no new type of accident or malfunction is possible.
III. No. The margin of safety is unaffected since no operations vill be perfermed with irradiated fuel.
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SE No.:    86-025 Source Document:     DCP 85-0725, Rev. O Description of Change Design change to the Leak Detection System floor drain piping to reroute l      dryvell cooler to " dirty" radvaste drain and the leak detection piping and Fuel Pool Cleaning Cooling and Cleanup funnel outlet piping to
       " clean" radvaste drains. (Mechanical Evaluation)
Summary I. No. Design change involves the segregation of leakage for the radvaste drains and flexhose addition and does not increase the probability of occurrence or the consequences of an accident or equipment malfunction important to safety.
II. No. Change involves only the segregation of leakage for the minor flow streams within the " clean" and " dirty" radvaste drain systems.
III. No. The margin of safety is not reduced.
SE No.:    86-026 Source Document:     STCN 003-1-2 Description of Change Temporary change made to the Start-up Test Instruction (STI) on Fuel Loading to allow for leaving the Reactor Protection System (RPS) shorting links installed during initial fuel load until their removal is required                             '
by Technical Specifications.
Summary I. No. Full compliance with Technical Specifications is maintained.
II. No. SRM monitoring and RPS protection are still available and operable.                                           f III. No. No Technical Specification margin of safety is involved.
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                                                                               .h I                                                                              'SE No.:       86-027 Source Document:                                      SCR 0-86-142 Description of Change S 0h                                      A revision was made to the Control Complex Chilled Vater System, OP47N0261A setpoint parameters (for expansion tank) to represent as-built
(                        plant setpoints.
Summary I. No. This revision represents as-built plant setpoints as identified by safety calculation.
j                                                                  II. No. Setpoint changes apply only to the expansion tank svitches' function to trip the P47 isolation valves closed on decreasing low level.
III. No.' Technical Specifications do not address the P47 system expansion tanks or its instruments' function.
SE No.:      86-028 Source Document:                                      SCR 0-86-143 q                                                                                 Description of Change 1,
A revision was made tc the Control Complex chilled Vater System, OP47N0261B setpoint parameters (for expansion tank) to represent as-built plant setpoints.
Summary I. No. This revision represents as-built plant setpoints as identified by safety calculation.
II. No. Setpoint changes apply only to the expansion tank switches' function to trip the P47 isolation valves closed on decreasing low level.
Li                                                                          III. No. Technical Specifications do not address the P47 system expansion tanks or its instruments' function.
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SE'Noi       86-029 Source Documents-        .DCN 228 Description of Change This drawing change is to make the D-302-772 P&ID for the RVCU Filter        '
Demineralized System correspond to the as-built configuration in the plant. A local low conductivity alarm signal does not exist' coming from~    {
conductivity switches G36-N010A&B and this is to be removed from the P&ID. . However, a low conductivity alarm does exist on Control Room         j Panel P680, which vould make the Control Room Operator aware, that a         ,
problem exists with the RVCU filter /demineralizers or the conductivity      ;
element and/or switch. (I&C Evaluation)
Summary I. No. Lov alarm does not affect any safety system. The control room alarm is still in place.
II. No.      See I above.
III. No.      The Water Chemistry Technical Specifications are based on high conductivity not low conductivity.
i SE No.:       86-031                                              ,
Source Document:          DCN 228-Description of Change This drawing change is to make the D-302-772 P&ID for the RVCU Filter Demineralized System correspond to the as-built configuration in the           i plant.- A local low conductivity alarm signal does not exist coming from      l conductivity switches G36-N010A&B and this is to be removed from the P&ID. However, a low conductivity alarm does exist on Control Room Panel P680, which would make the Control Room Operator aware, that a problem exists with the RVCU filter /demineralizers or the conductivity element and/or switch. (Mcchanical Evaluation)
Summary l
I . No .~ Lov alarm does not affect any safety system. The control room alarm is still in place.
II. No.      See I above.
III. No. The Vater Chemistry Technical Specifications are based on high l
conductivity not low conductivity.
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l SE No.:        86-032
        . Source Document:           DCN 0643                                                   ,
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         ' Description of-Change
                 ' Drawing change to revise, for as-built conditions,-the elevation             l differences between the RPV nozzle center lines and the condensing           ;
chambers on P&ID drawing D-302-608. And to revise the containment
;,                 building temperature Note 2 on subject drawing to 90'F.
Summary I. No. The change caly affected FSAR figure 5.1-35 (Sheet 4), not the text.
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II. No.      See I above, and III below.
III. No.       Centerline differentials and assumed containment building              i Temperature changes are not addressed in the Technical                ;
Specifications and do not change the reactor pressure and level        l instrumentation and control requirements.
l SE No.:         86-033 Source Documtint:           DCP 86-0320, Rev. O                                       jl Description of Change The addition of Richlite floor plate (Approx. 50 square feet) to PGCC        i floor to replace steel plates. Material vill have fire retardant            l coating. Total replacement of steel increases combustible load <0.1% and     !
vill'not affect adequacy of existing fire protection. This change is         l nect:ssary to provide a sound floor for the installation of carpeting in     j the Control Room.
f Summary,                                                                             ,
i I. No. Will still maintain safe shutdown capabilities isolated f rom Control Room. Only have a minimal increase in combustible loading and vill not impact overall fire safety.
II. No. See I above.
III. No.       Only the administrative aspects of fire protection are included in Technical Specifications. This change vill not impact the fire protection program.
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i SE No.:    86-034 Source Document:      SCR 1-86-605                                                           i Description of Change                                                                         i Setpoint changes to be made to the Reactor Protection System (RPS),
1C7150001A to allow for proper operation of equipment connected to the RPS. bus, (a setpoint for the M/G set's voltage regulator is required);
and to allow for the revision of the present setpoints for the nonsafety-related, M/G set mounted, protective devices, to accurately describe.the proper setting for these devices.
Summary                                                                                       i j
I. No. The voltage regulator setpoint is set at.a point which vill provide adequate voltage to all RPS loads. See III below.                             4 II. No. The RPS loads are protected by the two safety-related EPA breakers located downstream of the M/G set output breaker. Two EPA type                     l safety-related breakers have been supplied and connected in series                ;
to provide single failure protection for the RPS loads.                           i l
III. No. The setpoints for the M/G voltage regulator and M/G set mounted protective devices are not discusred in the Technical Specifications or in the FSAR..                                                                   .
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  -SE No.:             86-035 Source Document:                SCR 1-86-606 Description of Change Setpoint changes to be made to the Reactor Protection System (RPS),         f
                 -1C7150001B to allow for proper operation of equipment connected to the RPS bus,-(a setpoint for the M/G set's voltage regulator is required);
and to allow for the revision of the present setpoints for the              l' nonsafety-related, H/G set mounted, protective devices, to accurately describe the proper setting for these devices.
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Summary i
I. No.           The voltage regulator setpoint is set at a point which will provide    j adequate voltage to all RPS loads. See III below.                  l i
II. No.            The RPS Loads are protected by the two safety-related EPA breakers located downstream of the M/G set output breaker. Two EPA type safety-related breakers have been supplied and connected in series    ,
l to provide single failure protection for the RPS loads.               1 1
III. No.             The setpoints for the M/G voltage regulator and M/G set mounted       i protective devices are not discussed in the Technical Specifications  f or in the FSAR.                                                       l
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i SE No.:             86-036 Source Document:                SCR 1-86-611 through 1-86-624 li Description of Change Setpoint change to be made to the Containment Atmosphere Monitoring System to revise high temperature dryvell alarm setpoint to 135"F and to change safety classification to nonsafety. This change is necessary to establish high temperature alarm at Technical Specification Temperature Limit and for consistency with the Plant Emergency Instructions. Alarm circuitry is nonsafety which is what the safety classification is based on.
Summary
                                                                                              )
I. No.            This change is to establish nonsafety circuit alarm setpoints at     l Technical Specification Limit and per PEI's. The FSAR analysis is    l not impacted.                                                        ,
II. No.            See I above.                                                         l l
III. No.             Technical Specifications do not address nonsafety alarm setpoints or 1 alarm setpoint safety classification.
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i SE No.: '86-043 Source Document:      DCP 86-0320,.Rev. 1                                        ;
Description of Change                                                            l The addition of Richlite floor plate (Approx. 75 square feet) to PGCC floor to replace steel plates. Material vill have fire retardant coating. Total replacement of steel' increases combustible load <0.1% and vill not affect adequacy of existing fire protection. This change is        !
necessary to provide a sound floor for the installation of carpeting in      l the Control Room.                                                           [
1 Summary l
I. No. Vill still r.aintain safe shutdown capabilities isolated from Control Room. Only a minimal increase in combustible loading and will not impact overall fire safety.
II. No. See I above.
III. No. Only the administrative aspects of fire protection are included in    j Technical Specifications. This change vill not impact the fire protection program.
i SE No.:    86-044                                                                l Spurce Document:      SCR 1-86-568 and 1-86-569 l
l Description of Change l
Change made to increase the separator storage well level high alarm from 688'7.4" to 688'8" elevation, as well as change safety class from safety to nonsafety because the " alarm" setpoint function is nonsafety.
Summary.
I. No. The increased upper pool makeup volume without an alarm (hi level) vill not flood over the veir vall into the dryvell after an            i inadvertent dump.                                                      l i
II. No. See I above.                                                           I III. No. 'The storage well level high alarm setpoint is not described in the Technical Specifications.
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T l-SE No.:                      86-045 Source Document:                          PEI-B13 Description of Change-                                                                              I Safety Evaluation performed on items identified as discrepancies between Rev. 1 of Reactor Pressure Vessel Control (B13) Plant Emergency Instruction (PEI) and the Perry Specific Technical Guidelines (PSTGs) .
pertaining to 'the use of lif ted leads and jumpers as well as bypass        a switches.
                 ' Summary
                                                                                                                          ?
I. No. The changes are in compliance with the PSTG. Therefore the changes do not increase the probability of occurrence or the consequences of   ;
an accident or malfunction evaluated in the FSAR.                      '
II.-No.          See I above.
III.'No.                   The margin of safety'is not reduced.                                  j t
i SE No.:                    86-046 Source Document:                          DCN 676 Description of Change Drawing change to add and correct MPL numbers to System Diagram No. 912-617.                                                                 j
                 - Summary                                                                                               ;
I. No. Addition of HPL numbers does not affect system function.             '!
l II. No.          See I above.
III. No.                  See I above.
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1 SE No.:- 86-047 Source Document:        DCP 86-055, Rev. 0                                                                                                        l l
Description of Change                                                                                                                            j i
Design change to be made to Liquid Radvaste Disposal System to allov for                                                                f the addition of an evaporator feed strainer and filter to reduce the                                                                       (
amount of resin that is breaking down in the feed and resulting in                                                                      )
                     -increased conductivity.                                                                                                                 J 1
Summary                                                                                                                                        ,
i I. No. This design change does not introduce a potential for a greater                                                                   ;
probability of occurrence or consequence above those defined in the FSAR.                                                                                                                             !
II. No. This design change does not alter the general radvaste process path                                                               l and equipment function.                                                                                                           l III. No. Radvaste release limits / margins, and liquid radvaste process                                                                    j I
shielding and redundancy are not compromised by this design change.
SE No.:     86-048                                                                '
Source Document:        DCP 85-547, Rev. 1 Description of Change Design change to the spacing of fasteners for the bullet resistant firewalls at the 620'6" and 638'6" elevations of the Control Complex.
1 Summary I. No. This modification is generated to meet the intent of fire protection as specified in the FPER and FSAR for a 3-hour Fire Barrier Separation.
II. No. The up-grading of the vall construction vill not cause a threat                                                             to the fuel and the reactor coolant pressure boundary.                                                                                 l III. No. This is not within the scope of the Technical Specifications.
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SE No.:       86-049 Source Document:          DCP 86-238, Rev. O
                               ~
i                                                                                                                    i i                             Description of Change Design change.to allow for the installation of high point vents in the        i Suppression Pool (G43)' level sensing lines to ensure adequate venting of these lines.
Summary                                                                               ,
I. No. The installation of high point vents are done in accordance with the ASHE code for piping and seismic criteria for supports.            l II. No. See I above.                                                            !
III. No.      The addition of vent valves improves system functionability and reliability by assuring that the instrument' impulse lines vill be properly filled.
SE No.:      86-050 Source Document:         DCP 86-208, Rev. O l
Description of Change Design change to allow for the addition of flow regulating valves to the-    ,
seal water lines for the process pumps for the Solid Radvaste Disposal      l 1
System (G51).                                                                \
u
                              .S_ummary                                                                           ..
I. No. The GS1 system does not support any equipment important to safety.
II. No. See I above.
l III. No. See I above.                                                           1 i
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        'SE No.:    86-051' Source Document:       TTI - 009 Description of Change Evaluation of Technical Temporary Instruction for S-1-PY-BUS and S-2-PY-BUS 87B relays load check and 100-PY-B, 200-PY-B 87T relays load check.
Summary I. No. Instruction does not affect safety-related distribution and does not operate any equipment beyond capacity.
II. No. See I above.
III. No. -See I above.
SE'    .:  86-052 Source Document:       DCN 0628' Description of' Change Drawing change to revise cable size to show actual cable size installed on one line diagram D206-051.
Summary I. No. Change results in a inrger cable than what was previously shown and is more conservative in size. The size of cable used for equipment                      j is not discussed in the FSAR.                                                           '
II. No. See I above.
III. No. The margin of safety for Technical Specifications is not reduced by a drawing change to reflect actual cable size used.
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e SE No.:                       86-055 Source Document:                          FSAR-Section 9.1 Description of Change Evaluation of use of jib crane on containment 689' to move fuel from upender into contaiN,ent fuel pool racks.
Summary I. No. .The use of'the jib crane is not prohibited by the FSAR and the                                                        ;
probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR is not increased.
II. No.                      See I above. The jib crane and general purpose grapple are the same safety classification as the fuel handling platform and have                                      l administrative controls.
I III. No.                       These items are not addressed in the Technical Specifications.
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SE No.:                        86-056 Source Document:                         DCP 86-0171, Rev. 1                                                                    ;
l-Description of Change Design change to remove the trip function of Division I and Division II                                !
diesel generator's field ground relays. Field ground relays vill be used to alarm only.
Summary                                                                                                                         ,
j I. No. .The change being made permits the diesel generators to respond to accident conditions, and the continued operation of the Diesels                                   <
under loaded conditions with a concurrent field ground condition present does not result in any malfunction of the equipment.
1 II. No.                      See I above.
III. No.                       The diesel generator field ground relay function is not defined or described in the Technical Specifications.
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                                                                                                                 .l SE No.:    86-057 Source Document:      DCN 650                                                                                  J l
Description of Change                                                                                       i q Dravings changed to accurately indicate instrument air line tubing and                                  )
pressure switch location in the Heater Bay and Turbine Building (Numerous                                 I Drawing Changes).                                                                                       !
Summary                                                                                                      c l
I. No. Drawing changes clarify actual air line tubing and pressure switch                                i locations. Neither of which has any affect on safety as evaluated in the FSAR.
II. No. See I above.
III. Nc. Air line tubing and pressure switch locations do not affect                                        '
Technical Specifications.                                                                         l i
SE No.: .86-060 Source Document:       DCN 0694 Description of Change Draving change to revise the P&ID (D302-102) for the condensate Transfer and Storage System to reflect pipe cap as-built.                                                       i Summary I. No. This drawing change simply clarifies as-built configuration of pipe                               [
beyond valve 1P11-F517. T'- Hdition of this pipe cap is on a                                   ;
nonsafety line and has no bearing on the FSAR.                                                   l i
II. No. See I above.                                                                                     l l
III. No. The pipe cap does not affect Technical Specifications.                                           i I
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SE No. . 86-062
     -Source Document:       'DCF 86-0179, Rev. O                                                                                j Description of Change                                                                                                      1 Design change to change out the liquid process radiation monitor sample                                              ;
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            .line lov flow root valves to improve the sample flow rate.    (Mechanical Evaluation)
Summary I. No. Change results in FSAR system diagram change only. Replacement valves are fully qualified for the intended service and meet the original design requirements.                                                                                .,
II. Nc.. The replacement valves meet the original design intent and are no more likely to fail than'the original valves,                                                                 ,
III. No. Valve replacement vill improve sample flow rate.
SE No t     86-063 Source Document:        DCP-0179, Rev. O Description of Change Design change to replace the 3/4 inch Globe Valves OP43-F524, OP43-F544,                                            !
1P45-F565A/B and 1P45-F566A/B (Nuclear Closed Cooling System and i
Emergency Service Water System respectively) with ball valves and gate valves to improve the sample flow rate. (I&C Evaluation)
Summary I. No. The 1" ball valves are fully qualified to meet the ASME Code requirements and the 1" gate valves meet the initial design requirements.
II. No. The valve replaceme.nts meet the original design criteria.
1 III. No. The replacement of the globe valves vith ball valves and gate valves vill improve the sample flow rate.
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L SE No.:    86-065' j Source Document:       DCP 86-0350, Rev. O Description of Change Design change to replace the 2" Globe Valves IP45-F589, IP45-F591, IP45-F592, IP45-F631 and IP45-F594 of the Emergency Service Vater System in cross-tie lines to the Fire Protection System with 3" gate valves.
This change vill reduce the~ friction loss sufficiently to meet the 75 gpm flow criteria.     (Hechanical Evaluation)
Summary I. No. Change vill decrease the consequences of a fire related accident.                  ;
i II. No. See I above.
  'III. No. The margins of safety are not affected by this DCP.
SE No.:    86-066 Source Document:       DCP 86-0350, Rev 0 Description of Change                                                                        !
Evaluation of the Emergency Service Vater System (P45) to Fire Protection              l System crosstie valve replacement which vill improve performance of SSE supply to fire hoses as described in FSAR Appendix 9A to meet                          l commitments. (Fire Protection Evaluation)
Summary                                                                                      j I. No. This change does not affect the safe shutdown function of the P45 system.
II. No. There are no potential initiating causes of threats to the fuel and               a the reactor coolant pressure boundary.
III. No. Only the administrative aspects of fire protection are within the scope of Technical Specification.
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   .SE No.:           86-067 Source Document:             DCP 85-0420, Rev. O Description of Change Design change'to eliminate the unnecessary energization of the HPCS Diesel Generator "RUN" Solenoid when the S-1 switch is placed in the maintenance mode.
Summary I. No.      This change results in increased reliability of the solenoid.
II. No.      This change vill improve the HPCS diesel generator reliability and not increase or influence the possibility of an accident or malfunction different than previously evaluated in the FSAR.
111. No.          This change is not addressed by the Technical Specifications.
SE No.:          86-068 Source Document:             DCP 86-0223, Rev. O Description of Change                                                 ,
Design change to allow for a closure structure which is to be provided for existing masonry opening in the vest exterior vall of Off-Gas Building.- (Structural / Civil Evaluation)
Summary I. No.       The proposed structure is a fixed structure designed to meet Seismic I requirements.
II. No.       See I above.
III. No.       The installation of the closure does not have any influence on margins of safety defined in the bases for any Technical Specification.
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i SE No.:    86-069 Scurce Document:      DCP 86-0223, Rev. 0 l
Description of Change Design change to allow for the sealing off of the ventilation relief louver for the Off-Gas Building.     (Mechanical Evaluation)
Summary                                                                                                                '
I No. Sealing off this relief louver vill not adversely affect the capabilities of the system to exhaust air from the off-gas building and from potentially contaminated areas.
II. No. This change does not threaten the integrity of this system or other systems.
1 The margin of safety defined in the Technical Specifications is not
                                                                                                                           ~
III. No.
changed by this modification.
I SE No.:    86-070                                                                                                      ;
Source Document:      FCR 02520                                                                                        1 Description of Change                                                                                                  j Evaluation of a test in which the M38-C002A fan speed Auxiliary Building Ventilation System (H38) exhaust fans shall be increased to 1300 RPM, and the flow monitored (under dirty filter conditions) to see if design flow is met. During this test, it is expected that the motor vill exceed nameplate amps.
Summary i
I. No. This test vill be performed prior to initial criticality. The M38 system is nonsafety-related.
II. No. The possibility that the exhaust fan vould malfunction was already evaluated in the FSAR. Redundant exhaust fans are provided in case                                          !
of a single failure.
III. No. The Technical Specifications vill not be affected by this test.
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l             SE No.:     86-071 Source Document:        RVI-14, Rev. 1, TC1 Description of Change Change made to an instruction for the Solid Radvaste Solidification System (G51) to allow non-radioactive vaste to be processed and disposed of without using mobil solidification equipment (NUS) until vaste becomes radioactive.
Summary I. No. Transfer of non-radioactive filter sludge and resin to drums vill occur within the Radvaste Building.
II. No. Vaste vill be verified non-radioactive prior to transfer into drums.
III. No. Only non-radioactive vaste vill be processed this way,                      f I
SE No.:      86-072 Source Document:         DCP 85-0249, Rev. O Description of Change                                                                    !
Design change to tie in exhaust from off-gas panels 1N64-P001, 1N64-P002 to Exhaust System (M36), to allow air from these panels to be filtered.
Summary I. No. The design change vill allow air frot the panels to flow directly into the M36 exhaust doct, rather than recirculating the air back into the room and eventually flowing into the M36 duct. This change vill not change the overall system function.
II. No. The routing of ductvork between the panels and the M36 duct vill not threaten the integrity of the fuel or the reactor coolant pressure boundary.
III. No. The M36 system is not included in the Technical Specifications.
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SE No.:    86-073                                                                l Source Document:         DCP 86-0223A, Rev. 0 l                                                                                                                                                     l
?                                                                                                                                                     l Description of Change                                                                 j f
Design change to remove three supply registers from the Off-Gas Building exhaust. Pertains to the design. change to allow for the sealing off of   4 the ventilation relief louver for the Off-gas Building.                        l Summary I. No. The removal of supply registers vill not adversely affect the         'l i
capability of the system to exhaust air from potentially               .
contaminated areas in the Off-Gas Building,                          i l
II. No. This change does not threaten the integrity of this system or other systems.                                                             l III. No. The margin of safety defined in the Technical Specifications is not changed by this modification.
* SE No.:    86-074                                                               l Source Document:      ._DCP 86-0372,.Rev. O                                     i Description of Change                                                           !
To reduce system leakage for the Safety-Related Instrument Air System, a   !
design change is to be made to delete the receiver isolation valves (1P57-F510A, B; 1P57-F511A, B) and replace with straight pipe. And also replace instrument root. valves (1P57-F514A and 1P57-F515A) with a tubing sty.Le valve.                                                              ;
Gummary                                                                         ;
t I. No. A loss of safety-related instrument air vill be reduced, because the number of potential leakage paths is reduced.
II. No. Removing / replacing non-active valves vill not increase the possibility of a malfunction.
III. No. The margin of safety vill not be reduced since there vill be less air leakage and hence more air available to actuate SRV's, l
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l SE No.s. 86-075                                                                     !
Source Documentt      DCP 86-0373, Rev. 0                                              l l
Description of Change                                                                  l Design change to install the Unit 2 Safety-Related Instrument Air               l receivers as additional high pressure air storage tanks at the drain of     1 the presently installed tanks (Unit 1) to double the available air              j volume.                                                                         j 1
            ' Summary                                                                            9 I. No.'  This is a design change for adding safety-related air receiver tanks and vill not increase the probability of occurrence or the consequences of an. accident / malfunction previously evaluated in the  l FSAR.
i II. No. See I above.
III. No. This design change increases safety-related air storage capacity and i                        vill improve existing margins of safety as defined in the plant Technical Specifications.
SE Ilo. :  86-076 l             Source Document:     DCP 85-0694, Rev. 2 l
Description of Change Design change to the Supply and Exhaust Duct Branches (of the controlled Access Area HVAC H21) to eliminate noise problem and aid in airflow balancing for the Radiation Protection office.
i Summary I. No. The H21 system is nonsafety-related and overall function is not affected.
II. No. The change affects only the airflow in a select area of the control complex. The overall H21 system function vill remain the same.          ;
j             III. No. See II above.                                                            3 i

l-SE No.:    86-077 Source Document:       DCP 86-0055A, Rev. O Description of Change                                                              !
Design change to provide insulation for 2" flush lines for Liquid Radvaste Disposal System.
Summary I. No. This is an insulation change only. Mainly added for personnel           1 protection from hot (temperature) pipe and does not increase accident potential.
II. No. See I above.
III. No. This insulation change does not affect the margin of safety as defined in the Technical Specifications.
i SE No.: '86-078                                                                    )
Source Documents       .DCP 86-0023, Rev. 0                                        l Description of Change Design change made to modify isolation valve 1P52-F200 (Instrument Air       l System) control logic to enable the control room operator to bypass the LOCA isolation signal to open the valve to restore instrument air to the containment-.    (Mechanical Evaluation)                                     :
i Summary I. No. This new control facilitates mitigation of emergencies covered by      1 the Plant Emergency Instructions. All containment isolation           l functions as described in the FSAR are maintained.
II. No. This new control affects a single containment isolation valve.         I Single failures of isolation valves are addressed by the FSAR.
l III. No. This new control does not affect containment integrity or isolation   )
as described in the Technical Specification bases.                    l 1
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SE No.:     86-079 Source Document:        DCP 86-0023, Rev. O                                                                                     j I
Description of Change 1
Design change made to modify Isolation Valve 1P52-F200 (Instrument Air                                                    l System) control logic to enable the control room operator to bypass the                                                   l LOCA isolation signal to open the valve to restore instrument air to the                                                  l containment. (Electrical Evaluation)                                                                                      f l
Summary I. No. Credit is taken (in the FSAR) for Check Valve P52-F550 providing adequate containment isolation if PS2-F200 vere to fail open.                                                       l II. No. This change does not create a new disturbance that would threaten                                                   !
the fuel or reactor pressure coolant boundary.                                                                      I III. No. This design change does not reduce the margin of safety as defined                                                  }
in the bases for the Technical Specifications.
SE No.:      86-080 DCP 86-0393, Rev. 0                                                                                     l Source Document:
Description of Change i
Design change pertaining to the installation of startup neutron sources                                                   j (Californium).
Summary I. No. The adding of Californium sources with the existing antimony source                                                 j does not increase the probability of occurrence, consequences of an                                               1 accident or malfunction of equipment that is important to safety.                                                  j II. No. The possibility for an accident or malfunction of a different type                                                  ,
than any evaluated previously in the FSAR is not created.                                                          [
j III. No. Neutron sources are not addressed in the Technical Specifications.                                                 j l
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i SE No.:    86-081                                                                                                                            l Source Document:      FTI-E32                                                                                                           ~1 l
Description of Change Evaluation of the receipt and installation of Californium neutron sources.
                                                        ' Summary I. No. There are no FSAR Chapter 15 events dealing with neutron sources nor                                                           !
are they addressed elsewhere in the FSAR.
II. No. The addition of four source holder tubes vill not appreciably affect the core flow distribution. Any release of radioactivity would.be bounded by that from an irradiated bundle.
III. No. Startup sources are not addressed in the Technical Specifications.                                                             !
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SE No.:    86-082                                                                                                                       ,l Source Document:      STI-Jll-003                                                                                                         i Description of Change                                                                                                                     !
Change to Startup Test Instruction'on fuel loading to allow for the unloading of 16 fuel bundles from the reactor vessel,'the loading of 4 Cf-252 sources into the vessel, and the reloading of the 16 fuel bundles.
Summary i
I. No. The same controls vill be in place that were used for the initial loading and the core verification vill be done after the source                                                                [
loading and reloading of the affected bundles is completed.
                                                           .II. No. See I above, f
III. No. None of the bases for Technical Specifications are affected.                                                                   I i
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SE No.:     86-083
-Source Document:       FSAR CR No. 871 Description of Change                                                                              ,
Clarification made to FSAR Section 11.5.2.2.1 on the Off-Gas Retreatment Radiation Monitor. trip circuits. The FSAR was changed to show two trip alarms of the off-gas retreatment radiation monitor ratemeter, and one trip' alarm from the radiation monitor recorder.
Summary I. No. Subject change pertains to describing the number of alars.s associated with the off-gas retreatment radiation monitor readout                    l devices.
II. No. Correction was made to cite the specific number of trip alarms to Control Room readout devices.                                                         >
III. No. Off-gas pre neatment radiation monitor alarm trip association with l
Control Room readout devices are not described in Technical Specifications.                                                                       t SE No.:     86-084 Source Document:       DCP 86-0299, Rev. 0                                                        :
i Description of Change Design change to add capability to drain off the condensate for the dryvell hyilrogen analyzer sample lines.
l Summary I. No. Drainage provision is to allow system to function as designed.
II. No. The containment isolation /dryvell leakage design provisions are                     l maintained.                                                                          l III. No. Passive drainage for the combustible gas control system is not Technical Specification related.                                                     l I
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SE No.:    86-085 Source Document:       DCP 86-0425, Rev. O Description of Change Design chang ( to remove whip restraint (1B21-R105A) U-Bolts on main steam line.' This va l eliminate'an interference between it and condensate
              -chamber 1B21-D008A during system heatup. This restraint does not get                                   i loaded due to any B21 postulated breaks.                                                             -!
Summary                                                                                                     f l
I. No. The removal of whip restraint 1B21-R105A (Nuclear Boiler System)                                j does not affect safety previously evaluated in the FSAR. . Break                                 i SA4LL does not Joad this restraint.                                                             j II. No. The removal of this whip restraint does not present a different type                             !
of accident or malfunction than evaluated in the FSAR.                                        '{
III. No. The removal of a main steam whip restraint does not affect safety as                             [
defined per the Technical Specifications.                                                       I SE No.:     86-086 Source Document:       DCN 0762                                                                             l Description of Change Change to Residual Heat Removal System P&ID's to show temporary startup                                !
strainers removed.                                                                                     [
Summary I. No. This is an editorial change only to show piping during plant operation.
II. No. See I above.
l III. No. See I above.
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SE No.:      86-088                                                                                                           j i                         Source Document:        DCP 86-0320, Rev. 2 b                                                                                                                                                      ;
l                         Description of Change                                                                                                         !
Temporary design change to allow replacement of damaged floor plate's in                                            .;
Control Room with Richlite material. This is a temporary repair and                                                  i non-combustible floor plates will be installed before commercial operation.
l Summary I . No . . Th'e limited amount of material used per this design change vill not create a significant increase in the fire hazard as a temporary replacement.
II. No. The potential for a design basis fire in the Control Room is not increased.
III. No.
Only the administrative aspects of fire protection are included in Technical Specifications.                                                                                       !
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SE No.:      86-089 Source Document:        DCP 85-0677, Rev. O Description of Change Design change of failure mode of 1N23F020 (Condensate Filtration System) from fail-as-is to fail-open.   (I6C Evaluation) (see SE 86-090 below)
Summary l
I. No. Change to fall-open vill decrease the probability of loss of feedvater flow transient.
II. No. See I above, III. No. The margin of safety is not changed or affected.
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f SE No.:                                            86-090                                                              f
]                                                                            Source Document:                                             DCP 85-0677, Rev. 0                                      l Description of Change 1
Design change which relocates a check valve in the instrument air supply to the condensate filtration system bypass valve, 1N23F020, and changes              )
the valve's failure mode from fail-as-is to fail-open.               (Chemical Engineering Evaluation)
Summary I. No.                          This change decreases the consequences of a loss of instrument air to the condensate system.
II. No.                                 This change vill not introduce the possibility for an accident or malfunction of a different type then those already evaluated in the PSAR.
III. No.                                       This system is not part of the basis for Technical Specifications.
SE No.:                                        86-091 Source Document                                          DCP 85-0677, Rev. O Description of Change Design change of failure mode of 1N23F020 (Condensate Filtration System)            I from fail-as-is to fail-open.                                                       l l
l Summary I. No.                       Change to fail-open vill decrease the probability of loss of feedvater flov transient.
II. No.                             See I above. Loss of feedvater flow is already analyzed in Chapter 15 of the FSAR.
III. No.                                    The margin of safety is unaffected.

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p SE No.:                 86-092
     ' Source Document:                        DCN 0783 l          Description of Change Drawing change for the panel location for 1N27N599 A&B (Feedvater System)  !
from P654 and P655 to P868 and P869 (302-971).
Summary i
I. No.      Only'a correction of panel number on P&ID is involved.
l II. No.           See I above.
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III. No.               See I above.
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           -SE No.:                 86-093 Source Document:                 SOI-E22A i
Description of Change Evaluation of a change made'to the High Pressure Core Spray System Operating Instruction to provide a section on venting of the HPCS System high point vents, when a Discharge Pressure Lo Alarm is received, or     ;
whenever the HPCS vater leg pump is secured.                             l, Summary I. No. The FSAR accident consideration is that the piping is filled and vented. This instruction provides an alternative fill and vent      !
method.
II. No.        See I above, the same accident or malfunctions as evaluated in the FSAR vould still be current.
III. No.           The system always remains filled to height of suppression pool level.
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SE No.:         86-094
)   Source Document:                  DCP 85-0320A, Rev. O Description of Change Design change to provide for the installation of an air-conditioning unit to provide cooling to the area in which the computer controls for the snubber test machine are located.
Summary 1~. No. The Auxiliary Building Ventilation System (M38) function is not          l affected by this_ change.
II. No.       The addition of the air-conditioning unit vill not affect the present ventilation system.
III. No.        The change does not affect the function of the M38 exhaust system and there vould be no change to Technical Specifications.
SE No.:         86-095 Source Document:                  FSAR CR 86-050                                         {
Description of Change A change was made to the FSAR Section 9.1.4.3 to reflect that there are no limit switches on the refuel platform to prevent running the grapple into all valls.
Summary I. No.       A travel safety control computer is in place to eliminate the chance of the fuel mast running into a vall. The computer is designed to interrupt power to the bridge, trolley and fuel hoist drives when the platform enters a predetermined restricted area. Power to the platform drive motor is also interrupted when the computer is not functioning. The platform does have limit switches which prevent trolley movement to the extreme east and vest valls.
II. No.       See I above.
III. No.        The safety interlocks are not discussed in the Technical Specifications.
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e SE No.:                                                               86-096 Source Document:                                                                            FSAR CR 86-054 Description of Change Change to. routine calibration frequency of non-technical specification related area radiation monitors, identified in FSAR, from yearly to an 18 month basis.
Summary I. No.                                                Equipment is non-safety and a failure of an area radiation monitor does not affect equipment important to safety as previously evaluated.
II. No.                                                        See I above.
III. No.                                                              This change does not affect the calibration frequency (18 month) as defined in the Technical Specifications for area radiation monitors.
SE No.:                                                               86-098 Source Document:                                                                           DCP 85-0287, Rev. O Description of Change Design change to add a pressure regulating valve to the inlet of the Condensate Demineraliger System's hot water tank.
l Summary I. No.                                                This change affects the regeneration facilities of the Condensate Demineralized System and as such is not important to plant safety.
l II. No.                                                       This change vill not introduce the possibility for an accident or         '
malfunction of a different type than those already evaluated in the FSAR.
1 III. No.                                                              This system is not part of the bases for Technical Specifications.
                    .                                                                                                                                        l l
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SE No.'s   S6-099 Source Document;         DCP 86-0382, Rev. O Description'of Change                                                                                                         l Design checge to redefine the Auxiliary Building Ventilation System                                                     i design irflovs and adjustment of fans accordingly, so that system vill
    ,          be operabid under all dirty filter conditions'.             (Hechanical Evaluation)
Summary                                                                                                                     .;
i I. No. The Auxiliary Building Ventilation System is nonsafety-related and                                                f is not required for safe shutdown of the plant.                                                                   t i
II. No. The change in design air flows will allow the system to function as                                             '!
designed, to keep constant exhaust flow rate at all times.
Il
        'III. No. The margin of safety'is not reduced.
ll                                                                                                                                 A sl     SE No.:     86-100 7,    _S.ource Document:       DCP 86-0382, Rev. 0                                                                                  r Description of Change Design change to redefine the Auxiliary Building Ventilation System design air flows and adjustment of fans accordingly, so that system vill be operable under all dirty filter conditions.              Determination of effect of redefined airflows on in plant environmental zone temperatures and equipment qualification.             (Equipment Qualification Evaluation)
Summary I. No. All equipment within affected zone remains qualified under revised temperature conditions for both normal, abnormal and accident conditions.                                                                                                       j 1
II. No. Revised temperatures do not create the possibility for an accident or malfunction not evaluated previously in the FSAR, since all                                                    l affected equipment remains qualified.
III. No. All equipment within affect (d zones remains qualified for normal, 7              abnormal and accident conditions. Therefore, any potential for the                                                j reduction of margin of safety per the Technica), Specifications is
                                                                              ,                                                         i i                    eliminated.                                                                                                        l yJ                                                                                    ,
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I SE No.:     86-101 Source Document:       DCP 86-0128, Rev. O Description of Change A pressure decay test on the dryvell airlock door seal pneumatic system must be performed every 18 months. Currently, test connections exist on the air tanks inside the dryvell. The dryvell door must remain closed for the 24 hour test duration. The dryvell equipment hatch, therefore, must be open to allow access for personnel performing the test. This change routes the test connection tubing to outside the dryvell airlock bulkhead'in containment. Personnel can then run the decay test regardless of whether or not the equipment hatch is open. Radiation exposure vill also be reduced because dryvell entry vill be unnecessary.
Summary I. No. Neither dryvell integrity nor airlock integrity are affected by this design change. As a result, probability or consequences are not increased.
l                                                                                                                                                                                            l l                        II. No. Since the change does not affect dryvell integrity no other possible accidents can occur.                                                                                                                                  ]
III. No. The change does not affect Technical Specification margins of                                                                                         i '
safety; it provides a simpler and safer way to test for Technical Specification compliance.                                                                                                                             ;
                                                                                                                                                                                            )
SE No.:     86-102 Source Document:       DCN 0731 Description of Change Drawing change to update Quality Augmented Designation on the Fire Protection System P&ID's (Numerous Draving Changes).
l                       Summary
                          -I. No. This change expands the area to which the Quality Augmented Program applies.                                                                                                                                              J II. No. There are no potentia 1' initiating causes of threats to the fuel and the reactor coolant pressure boundary.                                                                                                                j l                       III. No. This portion of fire prote: tion is not addressed in Technical                                                                                        i Specifications.
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l SE No.:      86-103                                                                                            f Source Document _:       SOI-M28                                                                            'l Description of Change Evaluation of the Emergency. Closed Cooling Pump Area Cooling System which cannot be remote-manually started or stopped from-the Control Room as described in the FSAR Section 9.4.5.1.2.
Summary I. No. No change to equipment or system operation has occurred to modify-FSAR accident' analysis. The, system vill etill start automatically c
during a LOCA.
II. No. .The possibility for an accident or malfunction of a di fferent type than any evaluated previously in the FSAR is not created.
III. No. No operating parameters are affecteu.
SE No.:       86-104 Source Document:         DCP 85-099A, Rev. O Description of Change Design change to add a new sample chiller to the Condensate Demineralized System.
Summtry I. No. The sample chiller and associated instruments are not required to operate during or after an accident.
II. No. The sample chiller and associated instruments do not need to be                                ,
operational to shutdown the reactor.
III. No. The sample chiller vill operate as before, thus the margin of safety has not been reduced.                                                                         l I
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SE No.:     86-105 Source Document:        DCP 85-099A. Rev. O Description of Change Design change to add a new sample chiller to the Condensate Demineralized System.
Summary I. No. The sample chiller and associated components are not required to operate during or after an accident.
II. No. The sample chiller and associated components do not need to be operational to shutdown the reactor or maintain it in a safe shutdown condition.
III. No. The sample cooler system does not affect Technical Specifications and is not a basis for margin of safety.
SE No.:      86-106 Source Document:        DCP 86-114, Rev. O Description of Change Design change to allow for modification of Reactor Vater. Cleanup Filter / Demineralized System (1G36-A003) Backwash Receiving Tank (BWRT) for an ultrasonic level detector.      (Mechanical Evaluation)
Summary I. No. All modifications are performed to codes and standards specified in Table 3.2.1 of the FSAR.
II. No. Function of level instrumentation is not changed.
III. No.      BVRT level instrumentation is not covered by Technical Specifications.
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SE No.:                                                                                             86-107 Source Document:                                                                                              DCP 86-114, Rev. O Description of Change Design change to allow for modification of Reactor Vater Cleanup Filter / Demineralized System (1G36-A003) Backvash Receiving Tank (BVRT) for an ultrasonic level detector. (Piping and Equipment Evaluation)
Summary I. No.                                                                      Modification is in compliance with ASME Code. Design margin is not compromised.
II. No.                                                                              The addition of an instrument nozzle to a tank does not create a new possibility for an accident or malfunction.
III. No.                                                                                       Technical Specifications do not address ASME Code design margins or the design of low pressure storage tanks.
SE No.:                                                                                        86-108 Source Document:                                                                                         DCP 86-114, Rev. O Description of Change Design to allow for modification of Reactor Vater Cleanup Filter / Demineralized System (1G36-A003) Backvash Receiving Tank (BVRT) for a ultrasonic level detector.                                         (I&C Evaluation)
Summary I. No.                                                                 The BVRT level instrumentation ic not included in any accident or malfunction evaluations in the FSAR.
II. No.                                                                          The function of the level instrumentation does not change.
l                                                                   III. No.                                                                                   The BVRT level instrumentation is not described in the Technical l
Specifications.
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SE No.:      86-109 Source Document:        HFI 16-295 Description of Change Evaluation of a temporary change to allow for temporary discharge piping from vaste mixing tank to 55 gallon drum in Radvaste Building truck bay.
Summary I. No. Resin and. sludge are verified non-radioactive prior to transfer to 55 gallon drums.
II..No.
* Transfer of non-radioactive vaste occurs within'the Radvaste Building truck bay which has floor drains and ventilation.
i Radioactive vaste vill not be transferred via the temporary piping.
III.~ No.
The mobile solidification system vill be reconnected at that time.
SE No.:      86-110 Source Document:        DCP 86-0481, Rev. O Description of Change Design change to allov for the replacement of existing Cutler-Hammer relays (E31K200A, B, C and D) in the Control Room with Agastat relays for the Leak Detection System (Temperature Measurement / Alarm).
Summary I. No. The Cutler-Hammer relay is being replaced by a qualified Agastat EGP relay. Relay change vill improve the operability of circuit by eliminating relay chatter.
II. No. See I above.
III. No. Technical Specifications do not address these relays in the leak detection alarm circuitry.
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SE No.:   86-111 Source Document:     DCN 0807 Description of Change Drawing change to correct Drawing 302-109 by adding sample shutoff valves and conductivity cells.    (Chemical Engineering Evaluation)
Summary                                                                                                 ]
I. No. The adding of sample shutoff valves and conductivity cells does not affect system or any safety-function.
II. No. See I above.                                                                                  !
III. No. This system does not affect Technical Specifications.
SE No.:   86-112 Source Document:     DCN 0807 Description of Change Drawing change to correct Drawing 302-109 by adding sample shutoff valves and conductivity cells.    (I6C Evaluation)
Summary I. No. The adding of sample shutoff valves and conductivity cells does not affect system or any safety function.                                                         t II. No.. See I above.
III. No. The operation of the system has not changed, l
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l' SE No.:                    86-113 Source Document:                     DCN 0712 i
Description of Change Drawing change of symbol for valve IN24F365 (condensate Demineralized System) from a ball valve to a butterfly valve to reflect the as-built configuration. Editorial Change.
Summary I. No. This valve has no, safety function.
II. No.         The possibility for an accident or malfunction.of a different type is not created.
III. No.                  This-item does not reduce the margin of safety.
SE No.:                  86-114 Source Document                      PAP - 0103, Rev. 3 FSAR CR No. 86-74 Description of Change Technical Specification Section 6.5 does not include all requirements of FSAR Section 13.4.1.4. PAP-0103 and FSAR changed to reflect the Technical Specifications.
Summary I. No. The review requirements being removed from PORC responsibility are performed by other knowledgeable, responsible members of the plant staff.
II. No.       See I above.
III. No.                There is no affect on the bases described in the Technical
                                             . Specifications.
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SE No.:     86-115 Source Document:       DCP 86-055B, Rev. O Description of Change Design change'to add control' air tubing to the backwash valve (Liquid Radvaste Disposal System, G50) as well as reroute air tubing to the evaporator level control valve (0G50-F328A/B). (Pertains to SE No. 86-55)
Summary I. No. This part of the G50 system is nonsafety and is not described in the FSAR Chapter 15 analysis, s
II. No. See I above.
III. No. The margin of safety is not reduced.
SE No.:     86-117 Source Document:       DCP 86-200, Rev. 1 Description of Change Design change to allow for the relocation of the spectrum recorder        l D51-R170 (Seismic Monitoring System) from elevation 630'-1" at the recire. pump piping to elevation 636'-6", adjacent to RHR pipe support.
This change should improve seismic data interpretation. (See also CEI     j letter to the NRC dated April 25, 1986, No. PY-CEI/NRR 0452L)             {
Summary I. No. This is a relocation of the spectrum recorder only.
II. No. Relocation of the instrument does not increase a possibility of occurrence or the consequences of any accident or malfunction.
III. No. The margin of safety is not reduced.
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            -SE No.:              86-118 Source Document:                   DCP 86-115, Rev. O Description of Change                               '
Design change to allow for the addition of four bypass switches, one in each panel (1813-P691-694) to override the HSIV Level 1 isolation signal as instructed by the Plant Emergency Instructions.
Summary I. No.            The bypass switches are safety-related hardware.
II. No.             The bypass switches are a keylocked type, with the key removable in    l normal position. The switches shall only be used in a specific condition per the Plant Emergency Instructions (The current EPGs allow the operator to bypass the Level 1 MSIV; isolation signal).
1 III. No.               There is no change to Technical Specifications.
              'SE No.:                86-119 Sour'ce Document:                  DCP 86-377, Rev. O Description of Change Design change to allow for the installation of test switches to isolate Reactor Vater Cleanup (RVCU) circuitry to facilitate the performance of system SVI's.
Summary I. No.             The use of 1E switches to accomplish the isolation does not degrade safety. The isolation of the RVCU circuitry for the performance of an SVI is described in the PSAR.
II. No.             See I above.
III. No.              The isolation of the RVCU circuitry has no effect on manual initiation of RVCU isolation.                                        .,
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SE No.:      86-120-Source Document:          FSAR CR No. 86-045 Description of Change Change to the FSAR to reflect plant organizational and personnel changes.
Summary I. No. The changes are organization / personnel changes only and should strengthen the plant organization.
II. No. See I above.
III. No. See I above. These organizational changes are already incorporated into the Technical Specifications.
SE No.:      86-121 Source Document:
FSAR CR No. 866 Description of Change Editorial changes to FSAR Chapter 14 test abstracts.
Summary I. No. These changes are editorial and no technical change is involved.
II. No. See I above.
III. No      The margin of safety is not reduced as defined in the Technical
                                         'ipecli sations.
                                                 ~
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SE No.:      86-122 h   Source Documeny:       FSAR CR No. 867 Description of Change
          ' Changes to FSAR Table-1.8-2 and FSAR Section 17.2.10.2 to document l           compliance with Regulatory Guide 1.88.
1 Summary I. No. This change does_not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety.
II. No. This change does not create the possibility for an accident or malfunction that is different from what was previously described in the FSAR.
III. No. Technical Specifications are not affected by this change.
l SE Ne :      86-123 Source Document:       DCP 86-499, Rev. O Description of Change Design change to provide diesel backed power for H0V's OP41-F400 and 1P41-F390 of the Service Water System.
Summary I. No. This design change enhances the equipment protectien (nonsafety equipment). The addition of these MOV loads has been considered for a LOOP occurrence and are-insignificant during a LOCA event since these loads are shed.
II. No. See I above.
III. No. See I above.
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p-SE No.t      86-124
!                          Source Document:            DCP 86-0371, Rev. O                                       i Description of Change Design change to allos for the addition of RVCU differential flow meter         '
1E31-R614C to panal lH13-P680-1B.
Summary I. No. The additional meter is optically isolated from the safety-related circuitry of the Leak Detection System.
II. No. The additional meter provides indication only and does not change        ;
any system functions.
i III. No. The RUCU-differential flow indication is not included in the bases for any Technical Specification.
SE No.:      86-125 Source Document:           -DCP 86-0516, Rev. O Description of Change Design change to add two vacuum breaking valves on the discharge piping of the oil separator to prevent the separator from completely draining (Liquid Radvaste Sumps System).
Summary I. No. The addition of vacuum breakers on the oil separators has no safety function. The breakers allow water to drain to the floor drain collector tanks.                                                     .
II. No.      The breakers serve no safaty tunerion and vill not compromise safety in the plant, i
III. No.        The vacuum breakers and the oil separator are not discussed in the Technical Specifications.                                            y l
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                                                                                     -i SE No. . 86-126 Source Document:          DCN 0814 Description of Change-Draving revision to clarify cable size (D206-051).
Summary I. No.       This is only a draving change to clarify cable size. No functional change on the drawing was made.
II. No.       This is not a design change.
III. No.       For clarification purposes only.
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1 SE No.:      86-127 Source Document:        EDDR 226 Description of Change Evaluation of FSAR Section 9.2.7.3, which identifies that Valves OP41-F400 and 1P41-F390 (Service Vater System) are povered from the stub bus. These two valvos are currently povered from normal F buses and vill not be povered from the stub bus until the Design Change Package 86-0499 is implemented (DCP 86-0499 completed implementation on 9-15-86).
(Hechanical Evaluation)
Summary l
;                        I. No. Valve 1P41-F390 is the turbine building closed. cooling heat exchanger discharge valve bypass. The intent of having F390 on the stub bus is to maintain valve operability in the post LOOP scenario, so F390 can be closed. This valve should be closed after a LOOP in order to reduce the number of flow paths through the service water system. This valve may be positioned manually closed.
Valve OP41-F400 is the system bypass valve. It is used to increase i or decrease system flov to provide total service water flow compatible with the number of P41 pumps running, so the pumps-operate at their design point. In the post LOOP scenario, this valve also would have to be throttled back in order to provide the nuclear closed cooling heat exchanger with enough water. This valve may also be positioned manually closed.
II. No. See I above.
III. No. The operation of nuclear closed cooling in post LOOP scenario is not affected. The margin of safety is not reduced. The Nuclear Closed Cooling System is not in Technical Specifications, i
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SE No.:         86-128-Source Document              EDDR 226 Description of Change                                                                         ,
Evaluation of-FSAR Section 9.2.7.3, which identifies that Valves OP41-F400.and 1P41-F390 (Service Vater System) are povered from the stub              i bus. These tvo. valves are currently povered from normal F buses and vill not.be povered from the stub bus...itil the Design Change Package 86-0499 is implemented (DCP 86-0499 completed implementation on 9-15-86).
(Electrical Evaluation)
Summary
: 1. No.       The diesel backed stub bus and the F bus are nonsafety and vill not i
have any effect on safety.
II. No.       The change of power supply to these valves from one nonsafety source to another nonsafety source vill not cause an accident or increase malfunctions of the electrical system.
III. No.         Power supply for these valves is not covered in the Technical Specifications.
SE No.:         86-129 Source Docur.entt            DCP 85-295B, Rev. O Description of Change Design change to allow for the installation of a ventilation subsystem for the tool storage / tool decontamination areas in the Intermediate Building.                                                                            l Summary I. No.       The ventilation subsystem to be installed vill become a part of the Intermediate Building Ventilation System and vill be nonsafety-related. This system is not required to shutdown the plant.
II. No.        See I above.
III. No.         The addition of this ventilation subsystem will provide for filtration of potentially contaminated air exhausted from these areas.
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SE No.:    86-130 Source Document:       HFI for H43 Description of Change Evaluation of the removal of hydromotors to recirculation dampers on the Diesel Generator Building Ventilation System to allov recirc. dampers to be manually closed. The hydromotors are to be repaired or replaced prior to August 31, 1986.     (HVAC Evaluation)
Summary I. No. The probability of occurrence or the consequences of an accident are not increased based on current or historic outside ambient temperatures for this time of year. Dampers position themselves to take 100% outside air by positioning the recirculation dampers in
;                                                      the full closed position. Once the engine is started, outside temperature has no effect on environmental qualification on electronics or engine.
In the event of a fire, the CO2 system vill initiate dumping CO2 into the coom. The fan vill still trip, but the outside air supply damper vill not close. This is not viewed as a problem, since the CO2 vill be dumped into the room and the fire vill be extinguished.
The stay time of the CO2 vill be reduced slightly. The CO2 system vill be supplemented by a fire watch.
II. No. A more severe environmental condition is not created, because with the range of current or historic outside air temperatures, the recire, dampers vill be closed and the outside air supply damper vill be open supplying 100% of outside air.
III. No. The M43 system vill provide adequate cooling to the diesel generator.

T SE No.:    86-131 Source Document:      HFI for H43 Description of Change Evaluation of use of Mechanical Foreign Item which reverses the linkage on the Diesel Generator Building Ventilation System (1H43-F020A) such that the damper is open with the operator failed close.        (Engineering Evaluation)
Summary I. No. The probability of occurrence or the consequences of an accident are not increased with current or historic outside ambient temperatures for this time of year. Vith the current or historic outside ambient temperature, normal system operation would position the recirculation dampers and the outside air damper to supply mostly outside air.
The outside air damper is being blocked open to ensure a suction path during the fan start. When the system is shutdown normally, the outside air damper is closed and the recirculation dampers are open. The recirculation dampers are currently blocked, thus isolating any suction path.
In the event of a fire, the CO2 system vill initiate dumping CO2 into the room. The fan vill still trip, but the outside air supply damper vill not close. This is not viewed as a problem, since the CO2 vill be dumped into the room and the fire vill be extinguished.
The stay time of the CO2 vill be reduced slightly. The CO2 system vill be supplemented by a fire watch.
Vith the system shutdown and the outside air damper open, the diesel oil heater and jacket water heater vill be able to maintain the diesel engine temperature, due to the range of the current and historical air temperatures.
Once the engine is started, outside temperature has no effect on
              . environmental qualifications on electric or engine design intent.
II. No. A more severe environmental condition is not created, since with the range of current or historic outside air temperatures, the recirculation dampers vill be closed and the outside air supply damper vill be open supplying 100% of outside air.
III. No. The M43 system vill provide adequate cooling to the diesel generator.
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1 SE No.:       86-132 Source Document:              HFI 16-443 Description of Change Evaluation of the temporary disabling by lifted lead H25K200A (Control Room HVAC System), high chlorine monitor which initiates Control Room HVAC emergency re frculation. Logic will become 1 out of 3 instead of 1 out of 4. Two ir Train "B" and one available in Train "A" vill be functioning to ionitor chlorine.
Summary I. No.      Chlorine detection will still be available for the Control Room HVAC System.
t II. No.         See I above.
III. No.         Chlorine detection is not described in Technical Specifications.
:                     SE No.:           86-133                                                                                                                           -I Source Document:              FSAR CR No. 86-068 l                       Description of Change                                                                                                                                .
!                                FSAR Section 9.4.12.2.8 describes a remote switch in the Control Room that vill start the smoke venting system exhaust fans (for.the plant electrical areas), which is not reflected on the system drawings. The                                                                      !
FSAR is to be changed to describe that operation of the smoke venting fans is initiated manually from the Intermediate Building.
Summary I. No.         The actual location of the start switch is accessible for the fire brigade.
II. No.          The smoke venting system mitigates the consequences of a fire by clearing smoke to aid in firefighting.
III. No.           There is no change to any Technical Specifications requirement.
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SE No.:    86-134                                                                                                          I Source Document:       DCN 0713                                                                                            f Description of Change f
Drawing change to update Draving D302-713 to show valve OP22F657, a throttle valve, on the outlet of the service rinse line, j
Summary l
: i. No. Changing this drawing does not affect the accident analysis.                                                    :
II. No. See I above.
III. No. This system is not covered by Technical Specifications.
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  'SE No.:     86-136 Source Document:       DCP 86-224, Rev. O I
Description of Change Design change to add a 3" bypass line around the discharge valve in order to be able to reduce Emergency Service Vater System flow to the Emergency.
Closed Cooling System heat exchanger.
Summary
, 1 I. No. Currently the heat exchanger outlet valve is a manual valve which is throttled. This mode of operation vill not change with the addition of a 3" manual valve around this outlet valve.
II. No. No different type of accident vill be created.
III. No. The margin of safety is not reduced, because redundancy is maintained and single failure criteria is still met.
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l SE No.:         86-137 Source Document:           DCN 0893 FSAR CR No. 86-75 Description of Change Drawing change of HPL number of Valve 1R47F506A&B to 1R47F549A&B on        I Draving D302-353 Rev. E and FSAR Fig. 9.5-11.                              l l
Summary I. No. The drawing change of an MPL number has no effect on equipment or plant configuration as described in the FSAR.
II. No. See I above.
III. No. The plant Technical Specifications are not affected by the subject change.
i SE No.:     86-138 5ource Document:        DCN 0735 Description of Change Drawing change to make p manent in the Service Air System a 2 inch isolation valve and a 2 lu h pipe tee and cap installed upstream of Service Air Connection IP51-F0719. This connection is used during Off-Gas System testing (D302-242).
Summary I. No. The Service Air System is nonsafety and has no safety-related function. Failure of this system vill not compromise any safety-related system or component.
II. No. See I above.
III. No. Service Air is not a Technical Specification system.
l L - - - _ - _ _ _ _ _ _ ___ _ _ ___ _ _                                                                              j

SE No.:                                  86-139 Source Document:                                                                DCN 0904 FSAR CR No. 86-78 Description of Change Drawing change of MPL number and designation of the jacket vater high temperature trip sensor from " Temperature Element 1R46N0027A6B" to
           " Temperature Svitch 1R46N0702A&B" on Drawing D302-354 Rev. G and FSAR Figure 9.5-9.
Summary I. No.                                 The subject change affects only the labeling of the temperature svitch. All other factors of the design remain unchanged. There is no physical change to plant hardware.
I     II. No.                                 The subject change only involves labeling of equipment and does not affect plant design beyond that scope.
III. No.                                   The Technical Specifications are not affected by the subject change.
SE No.:                                    86-140 Source Document:                                                              DCP 86-433, Rev. O Description of Change Design change to allow for the installation of socket veld unions to safety relief valve drain lines on the Auxiliary Steam and Drains System to facilitate removal and install tion of safety relief valves.
Suma.nry I. No.                                    The addition of unions to the drain lines does not alter the FSAR description of the plant.
II. No.                                      See I above.
III. No.                                      The addition of the unions has no affect on the Technical Specifications.
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SE No.:    86-141 Source Document:       HFI for H43 Description of Change Evaluation of the removal of the hydromotor to the Diesel Generator Building Ventilation (H43) System outside air damper to allov damper to be manually opened. The hydromotor is to be replaced or repaired prior to August 31, 1986. (HVAC Evaluation)
Summary I. No. The probability of occurrence or the consequences of an accident are not increased with current or historic outside ambient temperatures for this time of year. Vith the current or historic outside ambient temperature, normal system operation vould position the recirculation dampers and the outside air damper to supply mostly outside air.
The outside air damper is being blocked open to ensure a suction path during the fan start. When the system is shutdown normally, the outside air damper is closed and the recirculation dampers are open. The recirculation dampers are currently blocked, thus isolating any suction path.
                       .In the event of a fire, the CO2 system vill initiate dumping CO2 into the room. The fan vill still trip but the outside air supply damper vjll not close. This is not viewed as a problem, since the CO2 vill be dumped into the room and the fire vill be extinguished.
The stay time of the CO2 vill be reduced slightly. The CO2 system vill be supplemented by a fire watch.
With the system shutdown and the outside air damper open, the diesel oil heater and jacket water heater vill be able to maintain the diesel engine temperature, due to the range of the current and historical air temperatures.
Once the engine is started outside temperature has no effect on environmental qualifications on electric or engine design intent.
II. No. A more severe environmental condition is not created cince with the range of current or historic outside air temperatures the recirculation dampers vill be closed and the outside air supply damper vill be open supplying 100% of outside air.
III. No. The M43 system vill provide adequate cooling to the diesel generator.
l         SE No.:   86-142 Source Document:     DCP 86-114A, Rev. 1 Description of Change Design change to replace the Reactor Vater Cleanup Filter / Demineralized i
              . Backwash Receiving Tank level transmitters with an ultrasonic level l
monitor.   (Hechanical Evaluation)
Summary I. No. This level instrumentation is nonsafety.
L          II. No. Replacement of existing level indication does not present a L                   different type of accident or malfunction.
         'III. No. The margin of safety is not reduced as defined in the bases of the Technical Specifications.
SE Ho.:   86-143 Source Documents'    DCP 86-114A, Rev. 1 l
Description of Change Design change to replace.the Reactor Vater Cleanup Filter / Demineralized Backvash Receiving Tank level transmitters with an ultrasonic level monitor.   (I&C Evaluation)
Summary I. No. The Backwash Receiving Tank level instrumentation is not included in I
any accident or malfunction evaluation in the FSAR.
II. No. The function of the level instrumentation does not change as a result of this design change. Only location and hardware selection l
has changed.
III. Nu. The Backwash Receiving Tank level instrumentation is not described l                   in the Technical Specifications.
l-I-
SE No.:                     86-144 Source Document:                        SCR l-86-1172 6 SCR l-86-1173 Description of_ Change Setpoint change to increase the pressure regulating valve (IP57F0005A, Safety-Related Instrument Air System) from 150 to 155 peig and provide a leave-as-is-zone of +20/-5 psig.
Summary L
I. No.                   The increase in the pressure band is still within the 200 psig design pressure of the system and below the 180 psig pressure relief valve setting.
II. No.                   The increase in the pressure band does not create the possibility of a new accident or malfunction than previously evaluated in the FSAR since the setpoint is within 200 psig max and 150 psig minimum design pressures.
III. No.                    This setpoint is not described in the Technical Specifications.
l l
SE No.:                     86-145 Source Document:                       DCP 86-531, Rev. O Description of Change Under the existing system control logic, the alarming or failure of any one of four chlorine monitors vill automatically switch both Control Room HVAC trains to the emergency recirculation mode. The logic is to be changed so that the trip of any one monitor gives alarm only, and the I                           trip of tvo monitors in Train "A" (or "B") switches the HVAC System to l
the emergency recirculation mode of operation. (Electrical Evaluation)
Summary l
I. No.                   Redundancy is preserved and no single failure vill prevent system operation.
II. No.                   See I above.
III. No.                    Technical Specifications are unaffected because they do not address the chlorine monitors, and this logic change does not affect any other function of Control Room HVAC.

SE No.:     86-146 Source Document:        DCP 86-531, Rev. O Description of Change Under the existing system control logic, the alarming or failure of any one of four chlorine monitors vill automatically switch both Control Room HVAC trains to the emergency recirculation mode. The logic is to be changed so that the trip of any one monitor gives alarm only and the trip of two monitors in Train "A" (or "B") switches the HVAC System to the emergency recirculation mode of operation.    (HVAC Evaluation)
Summary I. No. . Redundancy is preserved and no single failure vill prevent system operation.
II. No. See I above.
III. No. Technical Specifications are unaffected because they do not address the chlorine monitors, and this logic change does not affect any other function of Control Room HVAC.
SE No.:      86-147 Source Document:        DCP 85-067C, Rev. O Description of Change Design change to allow for utilities in the new oil lab located in the 599' elevation of the Control Complex.
Summary I. No. The additional piping and flow requirements for the nev lab is                                         l minimal and does not affect the probability of occurrence of an accident.
II. No. The affected areas of these systems are located in an area of the                                      3 I
Control Complex where they vill not increase the possibility of an accident.
III. No. The affected areas of these systems are not covered by Technical Specifications.
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1

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'  SE No.:      86-148                                                                                                                     ,
Source Document:        DCN 0801 Description of Change Change to P6ID's to show piping *":ing plant operation with the temporary start-up strainers removed (SLCS, " U System, RVCU Filter / Demineralized System, Energency Closed Cooling Sy. tem, and Control Complex Chilled Vater System).
l Summary I. No. This is an editorial change only and as such the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety is not increased.                                                                           ;
II. No. See I above.
III. No.      The margin of safety as described in the bases for any Technical                                                          l Specifications is not reduced.
L 1
SE No.:       86-149
* Source Document:        DCN 0800 t
Description of Change Change to P&ID's to show piping during plant operation with the temporary start-up strainers removed (Lov Pressure Core Spray System, High Precsure Core Spray System and Reactor Core Isolation Cooling System).
Summary I. No. This is an editorial change only and as such the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety is not increased.
II.-No. See I above.
III. No.      The margin of safety as described in the bases for any Technical Specifications is not reduced.
                                                                                                                   .- - _____ _ _____ -__-_ - ____                                 __ a

SE No.:    86-150 Source Document:                      DCN 0918 Description of Change Drawing change made to update diagram drawings (D302-081 & 082) to agree with elementary and viring drawings. Changes consisted of the addition of Panel 1H13P601 open/ closed lights for the feedwater inlet shutoff valves 1B21F065A6B and correction of panel location reference for alarm on Pressure Switches 1N27N020A,B,C&D. (I6C Evaluation)
Summary I. No. Correcting the diagram drawings to agree with the elementary and viring drawings does not change the basic design functions of equipment in the Feedvater System.
II. No.      See I above.
III. No.       Correcting the diagram drawings to show valve indicating lights and correcting panel location reference for pressure switch alarm does not change any margin of safety as defined in the Technical Specification.
SE No.:        86-151 Source Document:                      DCN 0703 Description of Change Drawing change of the panel location for 1N27N599A & B from "P654 and P655" to "P868 and P869" to correct editorial error (D302-971).
Summary I. No.      Only a correction to a panel number.
II. No.      See I above.
III. No.      See I above.

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f, 86-152 t [. SE No.:
DCN 0375',                                                #
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Description of Change                                                  i.,
3 .s Drawing change to the system diarypm for the Auxiliary Building Ventilation System to shov snat thre is ducted air into and out of the
                                        ,                 calibration lab (D912-615).                                        < l'
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                                       -lkummar
                                                ' I. No. This change do w not affebt the overall' ventilation system runction..
                                          >t. 7f.No.) See I abote.                                                ,
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III. N9,.'          See I abowe.           .
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SE No.:             86-153                                                                                             !
Source Document:                     STI-N33-129 i
Description of Change Safety Evaluation was performed to evaluate a difference between Startup Test Ins p uction on the Steam Seal System, Rev. 2 (STI-N33-129) and FSAR Table M .2.2 Startup Tests. FSAR Table 14.2-2 states that the Steam Seal St.irtup Test Instruction is performed at Test Conditions 1, 3 and 6. The S'iI currently has testing scheduled at Test Conditions HU, 3, and 6. The change was made to allov verification of a steem flow path to the steam l                                                       seals with non-nuclear steam (TC HU) as opposen to nuclear steam (TC 1).
This is in accordance with the Perry Nuclear Station policy of ALARA.                                        j Summary                                                                                                                 !
I . V.      The system vill be operated normally per its System Operating Instruction. The new test section does not involve any plant manipulations, only taking data on a normally operating system.                                    ;
i II. No.          This system has no safety function. The system vill be in normal                                    ;
operation.                                                                                         l III. No.            This system is not included in the bases for Technical l                                                                 Specifications.
                                                                                                                                                                     ~
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1 I
SE No.:     86-154 Source Document:        DCN 0918 Description of Change Draving change made to update diagram drawings (D302-081 6 082) to agree with elementary and viring drawings. Changes consisted of the addition of Panel 1H13P601 open/ closed lights for the feedvater inlet shutoff valves 1B21F065A & B and correction of panel location reference for alarm on Pressure Switches 1N27N020A, B, C & D.     (Mechanical Evaluation)
Summary I. No. Correcting the diagram drawings to agree with the elementary and viring drawings does not change the basic design functions of equipment in the Feedvater System.
II. No. See I above.
III. No. The Technical Specification safety margin is not reduced by drawing revision to reflect as-built information. The valve indicating        ,
                                        . lights and pressure switch alarms are not addressed in the Technical Specifications.
SE No.:     86-155 Source Document:         FSAR CR No. 86-51 Description of Change FSAR change (PSAR Section 9.1.4.4) to remove the need for periodic inspection of the fuel racks.
Summary I. No. There vould be no increase in the chance of an accident due to the racks being inspected prior to use, and there are no components which if left unchecked, could cause the racks to become inoperative.
II. No. Since there are no moving parts which can fail or cause degradation of the equipment, deletion of the periodic visual inspection vill not affect the fuel storage racks or other equipment in a different manner than previously evaluated in the FSAR.
III. No. The inspection of fuel racks is not discussed in the bases for any Technical Specifications.

l SE No.:     86-157                                                                                   :
Source Document:-       FSAR CR No. 86-071 Description of Change PSAR change (FSAR Section 10.2.5.3) to clarify protective measures to be taken during operation and maintenance of the turbine generator to prevent fires and explosions.                                                                  l Summary I. No. Incorporation of the change as-described does not increase the probability or consequences of an accident or equipment malfunction.
II. No. The' possibility for an accident or malfunction of a different type                      .
is not created.
III. No. This change is not defined in the bases for any Technical Specification.
SE No.:      86-158-Source Document:        DCP 86-0494, Rev. O i
Description of Change Design change to allow for cable terminations and the addition of Hygrometry Sampling System for Sensor 1D23N260 (Containment Atmosphere Monitoring System).                                                                        -l l
Summary I. No. Humidity instrumentation is designated non-safety by the FSAR, and                     j the proposed design change to correct operability problems is also                     l J
nonsafety-related.
II. No. See I above.
III. No. Technical Specifications do not address this specific humidity instrumentation.
I l
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     -SE No.:      86-159                                                                                  .
Source Document:       FSAR CR No. 86-073                                                         )
1 Description of Change                                                                              1 i
PSAR change (FSAR Section 9.3.5.3) to clarify the requirement for the operable SLC pump to be demonstrated operable when the other SLC pump is l            ~out of service for repairs.
Summary.
l I . . No . The Technical Specifications define definite plant operating conditions for one and both SLC pumps inoperable for plant operation conditions 1, 2 and 5. The probability and consequences of an accident remain the same.
II. No. The possibility for the loss of one or both SLC pumps has previously been evaluated in the PSAR.
III. No. There is no Technical Specifications requirement to test the
(                  operable pump when one SLC pump is out of service for repairs.
I I.
SE No.:     86-160 Source Documents.     'DCP 85-0295, Rev. O                                                       i i                                                                                                       !
Description of Change Design change to allow for fire suppression for the tool decontamination room in the Intermediate Building elevation 574'-10". (Fire Protection Evaluation) l Summary I. No. The additional fire suppression for this facility vill have no impact on the safe shutdown analysis or separation of redundant trains of systems.
II. No. There are no potential initiating causes of threats to the fuel and the reactor coolant pressure boundary.
III. No. Only administrative aspects of fire protection are in the Technical Specifications.
f I
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                                                                                                       ?
SE No.:         86-161 Source Documents           DCP 85-0295, Rev. 0 Description of: Change Design change to allow for the installation of architectural valls and ceilings as well as structural steel beam assemblies for the tool decontamination room in the Intermediate Building at Elevation 574'10".
(Civil / Structural Evaluation)
Summary I. No.       The installation of this room does not adversely affect any safety-related equipment, components or buildings.
II. No.       See I above.                                                                        l III. No.        The addition of this room does not affect any of the Technical Specification bases.
1 SE No.:          86-162 Source Document:           DCP 85-0295, Rev. O Description of Change Design change to allov for the installation of architectural valls and ceilings as well as structural steel beam assemblies for the tool decontamination room in the Intermediate Building at Elevation 574'10".
(Fire Protection Evaluation)
Summary I. No.       There are no safe shutdown components or circuits in this level of the Intermediate Building and the Safe Shutdown analysis is not affected.
II. No.       There are no potential initiating causes of threats to the fuel and the Reactor Coolant Pressure Boundary.
III. No.        Only the administrative aspects of fire protection are in the Technical Specifications.

    -                                                                                    1 l:
t SE No. ' 86-163                                                                    '
Source Document:      FSAR CR No. 86-057 Description of Change                                                              ,
i FSAR Change (FSAR-Chapter 13) concerning training requirements of Reactor and Computer Engineering Unit Lead.                                          l
      , Summary-I. No. This change concerns-administrative titles and training requirements  ;
and therefore does not involve postulated accidents or equipment      !
malfunctions.                                                         ,
II. No. See I above.                                                          i l
III. No. This change does not involve any Technical Specification bases.
i i
SE No.:     86-164                                                               j Source Document:      FSAR CR No. 86-079                                          '
Description of Change FSAR Change (FSAR Appendix 15E) to add the results of the Maximum Extended Operating Domain (MEOD) loss of feedvater heating analysis to Appendix 15E.                                                               ;
i Summary   '
I. No. The Perry specific analysis shows that loss of feedvater heating in   !
the MEOD regime is less severe (i.e., bounded by) than the existing   j Chapter 15 loss of feedvater heating.                                 l l
II. No. The possibility for an accident or malfunction of a different type    1 than any evaluated previously is not created.
III. No. The margin of safety as defined in the bases for any Technical         l Specification is not reduced.                                          ,
1 4
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SE No.:     86-165                                                                                                         ;
i Source' Document: '      FSAR CR No. 86-083 Descrip' tion of Change                                                                                                    l FSAR Change (to FSAR Chapters 13, 14 and 17) to reflect reorganization.                                              :
u
             ' Summa ry I
I. No. The' changes only involve reassignment and realignment of                                                     ;
responsibilities. No administrative functions important to safety                                        {
have been deleted.
i II. No. 'See I above.
III. No. See I above.
SE'No.:     86-167                                                                                                       l Source Document:        HFI for lH32 Description of Change j
Evaluation of the removal of the hydromotors to 1M32-F040A & B (Emergency Service Vater Pump House Ventilation) to allow the outside air dampers to                                          ,
be manually open. The hydromotors are to be replaced or repaired prior to August 31, 1986.
Summary I. No. No probability of occurrence or consequences of an accident vill                                             l increase based on current or historic outside ambient temperatures.
Dampers position themselves to take 100% outside air by positioning                                         i the outside air dampers in the full open position.                                                          l II. No. The M32 outside air dampers open, does not result in a more severe environmental condition since these outside air dampers vill be open with current or historic outside air temperature and 100% outside air vill be used.                                                                                           I III. No. The IM32 system vill provide adequate cooling to the Emergency                                              :
j Service Water Building and its associated equipmer..                                                        1

i SE No.:            86-168 Source Document:                HFI for lH32 Description of Change Evaluationlof.the removal of the hydromotors to 1H32-F050A & B to allow recirculation damper to be manually closed. The hydromotors are to.be                                               i
                           . replaced prior to August 31, 1986.
Summary I. No.. No probability of occurrence or consequences of an. accident will increase based on current or historic outside ambient temperature.
Dampers position themselves to take 100% outside air by positioning
                                  .the recirc.-dampers in the full closed position.                                                               ;
II. No.           With the M32 recire, dampers manually closed, it does not result in a more severe environmental condition since these recirculation dampers.. vill be closed with current or historic outside air temperatures and 100% outside air will be used.
III. No.            The 1H32 system vill provide adequate cooling to the Emergency Service Water Building and its associated equipment.
1 SE No.:            86-169 Source Document:               HFI for H32 Description of Change Evaluation of the removal of the hydromotor to 1H32-F070A & B to allow exhaust dampers to be manually open. The hydromotor is to be replaced ur repaired prior to August 31, 1986.
Summary I. No.           No probability or occurrence or consequences of an accident vill increase based on current or historic outside ambient temperatures.
With the exhaust dampers manually open, an air flow path is ensured for discharging.
II. No.           Vith the M32 exhaust dampers manually open, it does not result in a more severe environmental condition with current or historic outside air temperatures. No impact on the Fire Protection System vill exist.
III. No.            The 1H32 system vill provide adequate cooling to the Emergency Service Vater Building and its associated equipment. Vith the exhaust dampers manually open, an air flow path is ensured.
_______-________a

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SE No.:      86-170 Source Document:        DCN 0937 Description of Change s
Drawing change to allow for clarification of safety class break by changing the safety class markers to be consistent with each other (D302-353).
Summary 1
I. No. The subject drawing change clarifles the original designed safety classification break and does not affect the original design as evaluated in the FSAR.
II. No. No change to the design or new design is created or added by the                               ;
subject drawing change.
III. No. The Technical Specifications are unaffected by this change.
i SE No.:     86-171 fource Document:        DCN 0941 Description of Change Drawing change to correct diagram drawing (D302-655) to agree with elementary and viring drawings by removing indication of spent fuel storage pool low level alarming from level switch OG41N025. Lov level alarming is provided from level switch OG41N026.
Summary I. No. The design functions of the Fuel Pool Cooling and Cleanup System do not change.
II. No. The possibility for an accident or malfunction of a different type than any evaluated previously is not created.
III. No. The Technical Specification safety margin is not reduced by a drawing revision to show as-built information as given on elementary and viring drawings.
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SE No.:     86-172 Source Document:       DCN 0928 Description of Change
                                                                                                                       )
Drawing change to revise door schedule to indicate a Type 86N latch set                               j for door CC 504,-and remove door CC 503 from the door schedule and from                              '
the architectural layout.   (D103-032 & D105-015) i Summary                                                                                                     l l'
I. No. Neither of these doors are a security door or a rated fire door and therefore has no effect on any accident evaluated in the FSAR.                             .;
II. No. See I above.
III. No. See I above.
SE No.:     86-174                                                                                       l
         . Source Document:       DCP 86-0602, Rev. O f
D_escription e            of Change-                                                                              -!
Design change to allov for the addition of piping and valves to a lov                           ll pressure air storage tank that is to be installed on both divisions of                            ;
the Safety-Related Instrument Air System for increased system reliability.    (See SE's that follow throughout this package.)
Summary                                                                                                  j I. No. This de:ign change substitutes low pressure air storage for high                            l pressure air storage and vill not increase the probability / con-                            ,
sequences of an FSAR accident.                                                               '
f II. No. See I above.
i III . N'     There are no Technical Specifications affected by this design change, since it is limited to the addition of piping and valves.
i 5
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_ _ _ _ _ = _ _ _ - _

Y SE No.:    86-175 Source Document:       PEI-D23-2 TCN No. 1                                                        :
<: Description of Change
        . Change to the Plant Emergency Instruction for the Containment Atmosphere JHonitoring System (D23) to delete the use of the upper personnel airlock as a containment vent path.
Summary i
I. No. This change does-not deviate from the Perry Specific Technical                         !
Guidelines. Therefore, the change does not increase the probability                    i of an accident or equipment malfunction.                                               l II. No. See I above.                                                                          !
III. No.' The Technical Specification margin of safety is not affected by this change.
SE No.:    86-177                                                                                 i Source Document:       DCP 86-0612, Rev. O Description of Change                                                                             !
Design change pertaining to modification of Safety-Related Instrument Air Check Valves to. eliminate leakage.
Sammary                                                                                           ;
I. No. The addition of redundant sealing surfaces on the check valve redu~ces the probability of the loss of pressure in the safety-related instrument air system. The combination of the fit of                   ,
the metal vasher with captured o-rings, and the small travel the                      !
disc moves at the operating flow rate prevents the redundant seal from jamming in the valve body.
II. No. Vith the reaundant seals installed, the possibility of a loss of                      ,
Safety-Related Instrument Air vill be reduced.
III. No. .The availability of Safety-Related Instrument Air vill increase; therefore, it vill be better able to support the ADS function of 8'SRV's. This vill not reduce the margin of safety in Technical Specifications.
1
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SE No.:     86-178 Source Document:       DCP 85-337, Rev. O Description of Change Design change to allow for a power feed to clearvell pump P20C001A to be changed from the 480V Panel. FID12 to the 480 V HCC F1B08.                                           MCC F1B08 is backed up by-the Division 2 Diesel Generator, so pump P20C001A vill now ha"e a backup power supply.
Summar:L I. No. The clearvell pump supplies cooling water to the service water pump.
Neither are part of safety-related systems and are not required for safe shutdown of the reactor.
II. No. See I above.
III. No. See I above.
SE No.:      86-179 Source Document:       STI-F41-034 Description of Change This safety evaluation was performed to evaluate a difference between STI-F41-034, Reactor Internals Vibration, Rev. 2, and FSAR Table 14.2-2, Startup Tests.
FSAR Table 14.2-2 states that the Reactor Internals Vibration Startup Test Instruction is performed at Test Conditions HU, 3, 4, and 6. The STI was changed to schedule testing at Test Conditions HU, 3, 4, 6, 7 and 8. The testing at Test Conditions 7 and 8 was added to verify plant operating parameters in the extended operating domain.
SSER 8 Section 15.1 approved operation in this extended operating domain for plant startup testing.
Summary I. No. HE0D operation has been analyzed in Chapter 15 of the FSAR.
II. No. See I above.
III. No. HEOD has been incorporated into the Technical Specifications.
                                                                                                                                          )

1
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i 86-180 SE No.:
Source Document:               DCP 86-0510A, Rev. O Description of Change s.
Design change to allov for the replacement and relocation of flow transmitter 1N24-FT-N479 (Condensate Demineralized System) to an area in the system that vill avoid corrosion. (ISC Evaluation) i Summary I. No. .The design change only replaces the instrument type (differential                ;
pressure vs. rotameter) and relocates it to a point further upstream on the pipe.
II. No.           The design change does not change the function of the instrumentation and vill not create a new condition for an accident.
III. No.            The design change.does not affect the Technical Specifications.
I SE No.:              86-181                                                                 l Source Document:               DCP 86-0510A, Rev. O Description of Change                                                                       l Design' change to allow for the replacement and relocation of flow transmitter 1N24-FT-N479 (Condensate Demineralized System) to an area in           .)
the system that vill avoid corrosion. (Mechanical Evaluation)                       !
Summary
                            'I. No.          The design change has no effect on safety-related equipment or systems.
II. No.            The design change vill not create any conditions for an accident not 1 previously described in the PSAR.
III. No.             The design change does not affect the Technical Specifications.       ;
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SE No.:                       86-183-DCP 86-0378, Rav. 0                                        l L                        Source Document:
                        - Description of Change I
Design change to allor for the removal of interferences for mobil           l solidification equipment (Solid Radvaste Dicposal System).
Summary I. No. The valve, piping, and camera (all of which are nonsafety-related) being removed does not increase the probability of an accident.
II.,No.            The equipment being removed does not have a function for mobile solidification.
III. No.                     The equipment being removed has no. reference in Technical Specifications.
SE No.:                     86-184 STI-J11-021 5ource Document:
Description of Change This safety evaluation was performed to evaluate a difference between STI-J11-021, Core Power Void Mode Response and FSAR, Table 14.2-2, Startup Tests.
FSAR Table 14.2-2 states that the Core Power Void Mode Response Startup Test Instruction,1s performed at Test Conditions 4 and 5. The STI has been changed to schedule testing at Test Conditions 4, 5, and 7. The testing at Test Condition 7 was added to verify plant operating paraceters in the extended operating domain.
SSER 8 Section 15.1 approved operation in this extended operating domain for plant startup testing.                                                 .
Summary I. No. HE0D operation has been analyzed in Chapter 15 of the FSAR.
II. No. See I above.
III. No.             The margin of safety as defined in the bases for any Technical Specification has not been reduced.
l l
l

l SE No.:       86-185 Source Document:        STI-B33-030A Description of Change                                                                                                                    {
This safety evaluation was performed to evaluate a difference between STI-B33-030A, One Recirculation Pump Trip and Restart and FSAR                                                                      !
Figure 14.2-4.
FSAR Figure 14.2-4 is the Startup Test Condition Pover/Flov Hap which defines Test Condition 6 as limited at 100% core flov. The STI is written to trip the recirculation pump from greater than 100% core flov in the extended flow region for the extended operating domain.                                                                      !
SSER 8 Section 15.1 approved operation in this extended operating domain for plant startup testing.                                                                                                          ,
I Summary                                                                                                                                  ,
I. No.      Per Appendix 15E of the FSAR, all of the above have been evaluated and shown to have not increased.
II. No.      Since only core flov is being changed, no different accident or malfunction is being created.                                                                                              i III. No.      Per Appendix 15E of the FSAR, the margin of safety is not being reduced.                                                                                                                   ,
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f SE No. :   86-186 STI-N27-023A, Rev. 2 l  Source Document:
Description of Change                                                                                I This safety evalcation was performed to evaluate the differences between                         I the Startup Test Instruction for the Feedvater Master Reactor Level                             I Controller, Rev. 2 (STI-N27-023A) and FSAR Table 14.2-2.                                        )
l FSAR Table 14.2-2 states that the Startup Test Instruction is performed at Test. Conditions HU, 1, 2, 3, 4, 5, and 6. The STI has been changed to                        i schedule testing at Test Conditions HU, 1, 2, 3, 4, 5, 6, 7, and 8. The testing in Test Condition 7 and 8 has been added to verify plant operating parameters in the extended operating domain.                                          (
SSER 8 Section 15.1 approved operation in this extended operating domain for plant startup testing.
Summary I. No. The input of step increases / decreases into the Feedvat(r Haster Reactor Level Control System is not as severe as the Feedvater Flow Controller Failure described in FSAR Chapter 15, Appendix E.
II. No. See description above.
III. No. The margin of safety as defined in the bases of Technical Specifications is not reduced.
SE No.:                       86-187 Source _ Document:                       STI-P35-001 Description of Change This safety evaluation was performed to evaluate a difference between STI-P35-001, Chemical and Radiochemical, Rev. 2 and the FSAR Section 14.2.12.2.1 and Table 14.2-2, Startup Tests.
STI-P35-001, Chemical and Radiochemical Test was changed to include                    i Level 2 acceptance criteria on moisture carryover for testing performed                l in the Maximum Extended Operating Domain (HE0D).
Table 14.2-2 states that the Startup Test Instruction is performed at Test Conditions OV, HU, 1, 2, 3, 5, and 6. The STI has been changed to add additional testing in the increased flow region at Test condition 3 and in the extended load region at Test Condition 8.
FSAR 14.2.12.2.1 does not list any specific Level 2 acceptance criteria.
The STI has been changed to include Level 2 acceptance criteria on moisture carryover in the increased flow region of Test Condition 3 and the extended load region of Test Condition 8.
SSER 8 Section 15.1 approved operation in this extended operation domain for plant startup testing.
Summary I. No.                MEOD operation has been analyzed in Chapter 15 of the FSAR.
II. No.                      Sec I above.
III. No.                      The effect of MEOD operation is covered in Technical Specifications.

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SE No.:        86-188 Source Document:          STI-E12-071 Description of Change
               'this safety evaluation was performed to evaluate a difference between
                       ~
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STI-E12-071, Residual Heat Removal System and FSAR Table 14.2-2, Startup
[
i
               . Tests.
FSAR Table 14.2-2 states that the Startup Test Instruction is performed in Test Conditiona 1, 2, and 6. The STI has been changed to perform testing in' Test Conditions 1, 2, 6, and 8.
SSER 8 Section 15.1 approved operation in this extended operating domain l                 for plant startup testing.
Summary l           I. No.       Testing in TC 8 versus TC 6 does not result in additional steam l
loads on the RHR system and is no more severe than as previously l                        described in the FSAR.
l II. No.        See I above.
1' III. No.       The margin of safety as defined in the bases of Technical Specifications is not reduced.
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SE No.:    86-189 Source Document:      STI-R63-133, Rev. 2 Description of Change This safety evaluation was performed to evaluate the differences between i                      STI-R63-133. Loose Parts Monitoring System,.Rev.'2 and FSAR Table 14.2-2, Startup Tests.
PSAR Table 14.2-2 states that the Startup Test Instruction is performed at Test Conditions HU, 1, 2, 3, 4, 5, and 6. The STI has been changed to schedule testing at Test Conditions HU, 1, 2, 3, 4, 5, 6, 7, and 8. The testing in Test Condition 7 and 8 was added to verify plant operating parameters in HE00.
SSER 8 Section 15.1 approved operation in this extended operating domain for plant startup testing.
Summary I. No. This test only collects baseline data at different power levels.
II.ENo. See I above.
I III. No. Data collection does not reduce the margin of safety as defined in the-Technical Specification bases.
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SE No.:     86-190 Source Document:       STI-B33-030E l
Description of Change This safety evaluation vas performed to evaluate the differences between STI-B33-030E, Re:irculation System Cavitation, Rev. 2 and l'                 FSAR 14.2 12.2.27.5.
FSAR 14.2.12.2.27.5 states that the cavitation interlocks vill be tested with two loop operation during reactor power reductions using the control rods until cavitation occurs or the interlock is reached. The STI has l
been revised to incorporate a " procedural" cavitation limit during single
!                  loop operation since the cavitation interlocks are not applicabic under l                  those conditions.
Summary I. No. FSAR Appendix 15E of the FSAR evaluates HEOD, as does Appendix 15F for single loop operation.
Additionally, Technical Specification 3/4 10.4 allows testing with                           ;
only one recirculation pump in operation. Cavitation protection for the Recirculation System is provided by the system's cavitation interlocks and'not with the pover/ flow map. Since these interlocks                          i vill be operable, no changes to the cavitation protection vill be in                         i effect. During the single loop testing, cavitation protection is                           l provided by the procedural limit.
II. No. Both increased core flov and single loop operation are evaluated in Appendices 15E and 15F of the FSAR.
III. No. Per Appendices 15E and 15F of the FSAR, the margin of safety is not being reduced. Cavitation protection is operable as designed.
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l SE No.:                    86-191                                                                                         !
Source Document:                       PEI-D23-1, PEI-D23-2 and PEI-D23-3                                                 )
Description of Change Change to the plant emergency instructions pertaining to containment temperature pressure control, dryvell and containment pressure control, and dryvell temperature control, which incorporate human factor                                             ;
enhancements made to various control room backpanels in an effort to optimize operator response.
Summary I. No.           The changes do not deviate from the Perry Specific Technical Guidelines (PSTG's). Hence, the consequences of an accident or equipment malfunction are not increased.
II. No.                 These changes do not create the possibility of an unanalyzed accident or malfunction because they comply with the PSTG's.
III          No.           These changes are not related to any Technical Specification margin of safety.
i SE No.:                    86-192 Source Document:                      STI-B33-030B Description of Change This safety evaluation was performed to evaluate a difference between STI-B33-030B, Recirculation Pump Trip of Two Pumps, Rev. 2 and FSAR Figure 14.2-4.
The Startup Test Instruction has been developed to allow testing above 95% core flow within Test Condition 6. FSAR Figure 14.2-4 defines a maximum core flow limit of 100% for Test Condition 6.
SSER 8 Section 15.1 approved operation in this extended operating domain for plant startup testing.
Summary I. No.            Per Appendix 15E of the FSAR, all of the above have been examined and shown to have not increased.                                                             j II. No.                Since only core flow is being changed, no different accident or                               l i                                                     malfunction is being created,                                                                j i
                                                                                                                                                   )
III. No.                   Per Appendix 15E, the margin of safety is not being reduced.
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SE No.:                                                                                        86-193 Source Document                                                                                               STI-C95-099 Description of Change This safety evaluation vas performed to evaluate a difference between STI-C95-099, ERIS and FSAR Table 14.2-2, Startup Tests.
FSAR Table 14.2-2 states that the Startup Test Instruction is performed in Test Conditions OV, HU, 1, 3, and 6. The STI has been changed to perform testing in Test Conditions OV, HU, 1, 3, 6, and 8.
SSER 8 Section 15.1 approved operatlon in this extended operating domain for plant startup testing.
Summary I. No.                                                                        This test involves only data gathering. This test does not perform plant manipulations.
II. No.                                                                                   See I above.
III. No.                                                                                           There are no Technical Specification bases relating to this test.
SE No.:                                                                                           86-194 Source Document:                                                                                                DCP 86-0602D, Rev. O Description of Change Design change to allov for the installation of anchor bolts and temporary cored holes for Safety-Rolated Instrument Air System lov pressure storage tanks.
Summary I. No.                                                                      The capacity of the slabs is still adequate to support the design loads. The loss of concrete in the cored holes is not detrimental to the integrity of the Auxiliary Building roof slab.
II. No.                                                                              See I above.
III. No.                                                                                      See I above.

SE No.:     86-195 Source Document:       STI-C85-022 Description of Change                                                                                            j
             -This safety evaluation was performed to evaluate a difference between STI-C85-022, Pressure Regulator, Rev. 2 and FSAR Section 14.2.12.2.19 and Table 14.2-2, Startup Tests.                                                                               ,
FSAR 14.2.12.2.19 states that a plot of power versus the peak variable values along the 100% rod line vill be maintained. The Startup Test                                        j Instruction has been changed to obtain this plot along the bounding.
licensed rod line. This change was made to support testing in the Maximum Extended Operating Domain (HE00).
PSAR Table 14.2-2 states that the Startup Test Instruction vill be performed at Test Conditions 1 through 6, inclusively. The STI has been changed to schedule testing for Test conditions 1, 2, 3, 4, 6, 7, and 8.
SSER 8 Section 15.1 approved operation in this extended operating domain j              for plant startup testing.                                                                                ;
Summary I. No. HEOD operation has been analyzed in Chapter 15 of the FSAR.
II.-No. HEOD operation has been analyzed in Chapter 15 of the FSAR.
III. No. The effect of HEOD operation is covered in the Technical                                            4 Specifications.                                                                                     ;
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SE No.:      86-196                                                                                              !
Source Document:        DCN 0957                                                                                 [
f Description of Change Drawing change to add pump names and various component master parts list numbers to further clarify / identify components on the HPCS Diesel Lube 011 System Diagram (4549-20-023-1).
Summary I. No. The subject change is only a clarification of design details and the                                j system / equipment design as previously evaluated in the FSAR is                                      l unchanged.
I II. No. The subject change has no ef fect on the system / equipment design.                                   !
1 III. No. The Technical Specifications are not af fected by the subject change.                                 ]
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SE No.t     86-197 Source' Document:      DCN 0929 Description of Change Drawing change to delete two orifices from each standby diesel generator jacket water system, downstream of the turbocharger aftercoolers (D302-354).
Summary I. No. The subject drawing change removes orifices which vere nevet used during the preoperational or surveillance testing or ever installed on the Standby. Diesel Generators. These orifices vere included in the original design, however they were found to be unnecessary by the engine designer / manufacturer, as the design met all of the system operating performance requirements without ever implementing them.                                                                                                          i II. No. In llEht of the written basis for Item I above, no new design factor has been introduced by the subject drawing change, and all original design parameters have been maintained.
III. No. . The Technical Specifications are unaf fected by the subject change.
SE No.:     86-198 Source Document:       DCP 86-602D, Rev. 1 Description of Change Design change to allow for the cutting of three rebars in order to enable the installation of drilled bolts in the Auxiliary Building for the                                                    1 Safety-Related Instrument Air System low pressure storage tanks.
Summary                                                                                                                      .
I. No. The two north-south bars being cut are secondary bars (non-load bearing). The one east-vest bar being cut is additional reinforcement provided and is not required for design loads.
II. No. Since the slab capacity remains unchanged, the possibility of an accident or malfunction is not increased.
III. No. See I above. The margin of safety is not reduced.
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l SE No.:                        86-199 Source Document:                             STI-C91-019 Description of Change This safety evaluation was performed to evaluate a difference between STI-C91-019, Core Thermal Power and FSAR Table 14.2-2, Startup Tests.
PSAR Table 14.2-2 states that the Core Thermal Power Startup Test Instruction is performed at Test Conditions 1, 2, 3, 4, 5, and 6. The STI has been changed to schedule testing at Test Conditions 1, 2, 3, 4, 6, 7, and 8. The testing at Test Conditions 7 and 8 was added to verify plant operating parameters in the extended operating domain.
FSAR Section 14.2.12.2.16 states that reactor power shall be limited to values on or beloe the 105% steam flow design flow control line.
SSER 8 Section 15.1 approved operation in this extended operating domain
* for plant startup testing.
Summary I. No.                 This startup test does not manipulate plant parameters but only collects data.
II. No.                          Operations in the HEOD region has been analyzed in Chapter 15, Appendix E of the FSAR.
III. No.                          See I and II above.
SE No.:                           86-0200 Source Document:                                DCP 86-602D, Rev. 2 Description of Change Design change to allow for the installation of anchor bolts, temporary core drill, grout and the cutting of five rebar in the Auxiliary Building for Safety-Related Instrument Air System low pressure storage tanks.            !
l Summary I. No.             The capacity of the slabs is still adequate to support the design loads. The cutting of four north-couth rebars that are non-load bearing secondary bars and one east-west bearing bar vill not compromise the ability of the Auxiliary Building slab to support the design loads.
II. No.                     Since the slab capacity remains unchanged, the possibility of an accident or malfunction is not increased.
III. No.                          See I above.

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                            .SE No.:      86-201 I                            Source Document:        DCP 86-602E, Rev. 0 l
Description of Chan$e Design change to allov for the routing and support of conduits 1P57R4B .75 and IP57RSA .75, as well as the rework of conduit IP57R3A .75, for the installation of low pressure storage tanks in the safety-related Instrument Air System.
Summary I. No. The conduits.are adequately supported for the load cases defined in the FSAR. The attachment of Type 5 conduit supports to the vall for the 3/4 inch diameter conduit does not impair the structural integrity of the vall, i
II. No. See I above.
III   No. See I above.
SE No.:      86-203 Source Document:        DCP 86-0602D, Rev. 4 Description of Change Design change to allov for the installation of anchor bolts, temporary core drill, grout and the cutting of five rebar in the Auxiliary Building and five rebar in the Intermediate Building for the Safety-Related Instrument Air System low pressure storage tanks.
Summary                                                                                                        ,
t I. No. The capacity of the slabs is still adequate to support the design                                 ,
loads. The cutting of four north-south rebars that are nonload bearing secondary bars and one east-vest bearing bar vill not compromise the ability of the Auxiliary Building slab to support the design loads. The cutting of three east-west bars and two north-south bars vill not compromise the ability of the Fuel Handling Duilding foundation mat to support the design loads.
II. No. Since the slab capacity remains unchanged, the possibility of an accident or malfunction is not increased.
III. No. See I above.

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SE No.:     86-204 Source Document:        SVI-B33-T1168 STI-F41-034 Description of Change This safety evaluation was performed to evaluate the incorporation of monitoring for thermal stratification in STI-F41-034, Reactor Internals Vibration vice SVI-B33-T1168, Idle Recirculation Loop Temperature and Flow.
Technical Specification 3.4.1.4 is surveillance tested using SVI-B33-T1168, Idle. Recirculation Loop Temperature and Flov in normal               i j'
plant operating conditions to verify no thermal stratification prior to an idle recirculation loop start-up.      During non-nuclear heatup, a 100 psi nitrogen overpressure is applied to the reactor, which invalidates the use of steam dome pressure to determine steam dome temperature. The SVI is not written to mc71 tor thermal stratification in           ,
this operating condition. The STI has bean developed to perform this                ,
surveillance during non-nuclear heatup by using~ recirculation suction temperatures.
l Summary I. No. No probability or consequence of an accident or malfunction vill increase. During non-nuclear heatup there vill be no feedvater flow    i into the RPV and no core heat generated. Thus, an operating L                                recirculation loop auction temperature vill be equivalent to that in l                                the stear. dome. Because a nitrogen precharge of at least 100 psi
* above saturation pressure vill be maintained in the steam dome during non-nuclear heatup, the indicated steam dome temperature, which is based on steam dome pressure, vill be in error. This is why recirculation loop suction temperature vill be used tor steam     a i
dome temperature during the non-nuclear heatup.                                 '
II. No. The possibility for an accident or malfunction of a different type than any evaluated previously is not created.
1 III. No. Since this use of the recirculation loop suction temperature for                 j steam dome temperature is only applicable during the non-nuclear                 I heatup portion of STI-F41-034, the additional precautions on thermal            l stratification incorporated in STI-F41-034 vill assure that no reduction in the safety margin as described in the 3.4.1 Basis of                l Technical Specifications will occur, t

f SE No.:      86-205 ISource Document:                 DCP 86-653, Rev. O Description of Change                                                                                                                    .
Design change to add 3/4 inch flanged drain connections to allow water removal from the Off-Gas System after charcoal absorber flooding and charcoal removal.
Summary I. No. This design change vill not impact or increase accidents or malfunctions as defined in the FSAR. This design change vill not cause equipment failure.
II. No. See I above.
III. No. The Off-Gas System operation margin of safety and gaseous release rate margin of safety are not impacted by this design change.
SE No.:       86-206 Source Document:                 DCP 86-602B, Rev. O Description of Change Design change to allow for the addition of a low pressure air storage tank on both divisions of the Safety-Related Instrument Air System (P57).
Summary I. No. This design change is limited to the addition of low pressure air storage tanks in the P57 system and does not increase the                                                                    '
probability of previously evaluated FSAR consequences, accidents or others.
II. No.       See I above.
III. No.       This thange does not reduce the Technical Specifications margin of safety, since larger tanks vill provide greater storage capacity of                                                          l air at the reduced pressure.
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i SE No.:    86-207 Source Document:      DCP 86-602F, Rev. O Description of Change                                                                                               j i
Design change to_allev for the installation of safety-related air                                              i pressure instrumentation for the low pressure air storage tanks and the                                        i deletion of the old alarm setpoints and the addition of new alarm                                              !
setpoints.                                                                                                     l f
Summary I. No. Normal tank pressure vill be between 160 and 170 psig with system                                        l design limits of 150 and 180 psig. The alarm setpoints vill give                                         ;
annunciation prior to going below the 150 psig and going above the                                       !
180 psig design limits.
II. No. See I above.
III.-No. The margin of safety in the alarm setpoint change has not been reduced. It is above the 150 psig low pressure design limit.                                             j SE No.:    86-208 Source Document:       DCP 86-602G, Rev. O Description ~of Change Design change to allov for the fabrication and erection of lifting beam                                        l assembly for the Safety-Related Insttument Air System (P57) low prassure                                       j storage tanks.                                                                                                 1 Summary I. No. The lifting beam assembly is designed to adequately support the tank loads during the rigging phase of installation of the P57 low pressure air storage tanks in accordance with the requirements of MAP-1301, Rev. O, NUREG-0512, and ANSI N14.6-1978.                                                       )
i II. No. See I above.
III. No. See I above.
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SE No.:             86-209 Source Document:               DCP 86-480, Rev. O Description of Cha'nge Evaluation of Hilti bolt installation in Reactor Building; pertaining to a design change to allow for the location of the dryvell equipment L                                          ' drain sump level transmitter outside of the sump.
1        <
Summary t:
                                    .I. No. The Hilti bolts are designed such that they do not impair the structural integrity of the Building.
}                               .II. No.          The Hilti . bolts do not create the possibility for an accident or                                      ;
malfunction of a different type than previously evaluated.
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                           - III. No.             See I above, i
SE No.:            86-210 Source Document:             .DCP 86-602C, Rev. O
                                                        ~
Description'of Change Design change: to allow for instrumentation for the Safety-Related Instrument Air (P57) low pressure air storage tanks.      (I&C Evaluation)                                    :
Summary I. No. The design change defined by this DCP now requires that the system                                      j pressure for both the "A" and "B" loops be monitored from lov                                           i pressure air storage tanks. The instrumentation vill nov be                                            l monitoring a system pre mure of approximately 150 psig instead of 2,500 psig.                                                                                             !
II. No.       See I above.                                                                                           1 l
III. No.           The change vill not affect the margin of safety as defined in the bases for any Technical Specification.
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SE No.:                      86-211 Source Document:                         DCP 86-602C, Rev. O Description of Change Design change to allow for instrumentation for the Safety-Related Instrument Air (P57) low pressure air storage tanks. (Hechanical Evaluation)
Summary I. No.                    This design change adds low pressure air tank instrumentation which vill provide greater storage capacity of air at the reduced pressure and does not increase the probability / consequences of FSAR accidents.
II. No.                    See I above.
III. No. . This does not reduce the Technical Specification margin of safety, since the larger tanks vill provide greater storage capacity of air at the reduced pressure.
SE No.:                       86-212 Source Document:                        DCP 86-602C, Rev. O Description of Change Evaluation of Hilti bolt installation in safety-related building, pertaining to a design change to allow for the Safety-Related Air (P57) low pressure air storage tanks. (Civil / Structural Evaluation)
Summary I. No.                    Hilti bolts are designed such that they do not impair the structural integrity of the. building.
II. No.                    Hilti bolts do not create the possibility for an accident or malfunction of a different type than previously evaluated.
III; No.                     See I above.
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SE No.:         86-213 Ssurce Document:            DCP 86-675, Rev. 0-                                        l 1
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    ' Description of Change               i Design change to allow for the replacement of the HSIV Leakage Control 15 minute time delay relay with a 30 minute time delay relay. (See also      l SE No. 86-0222'.).(I6C Evaluation)
Summary
            'I. No. This change does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the PSAR.
II. No. This change does not create a new accident or malfunction than previously evaluated in the FSAR.
III. No. Technical Specifications do not address these time delay relays.        :
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SE No.:      86-214-                                                               3 Source Document:         DCP 85-295M, Rev. O Description of Change Design change to allow for the Tool Decontamination Room fire protection    j L
core drills.
Summary i
l                                                                                            j I. No. The removal of concrete for these core drills has no affect on the    '
ability of the slabs to' support the required design loads and therefore the probability of an accident or malfunction is not increased.
II. No. Since the slab capacity is unchanged, the probability of an accident or malfunction is not increased.                                     ,
i III. No. See I above.
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SE No.:    86-215 Source Document:       STCN 034-2-3 for STI-F41-034 Description of Change This safety evaluation was developed to evaluate the temporary connection of a nitrogen manifold, temporarily installed per DCP 85-657 to support non-nuclear heatup testing required for the prototype reactor internals vibration measurement program.
The nitrogen charging is made through the RCIC head spray line.
Containment integrity vill be maintained and all applicable Technical Specification requirements met,.if the test connection valves are opened to recharge nitrogen. The two test connection vent.valv's (lE31-F035 and lE31-F034) vill remain locked closed when nitrogen recharging is not required.
Summary I. No. During non-nuclear heatup a nitrogen charging manifold vill be 6        connected to the test connection line just upstream of 1E51-F013.
II.       This is covered in DCP 85-657 The two 3/4" test connection valves (1E51-F035 and 1E51-F034) vill remain locked-closed throughout the test, except if recharging of the nitrogen blanket is required. In this case, the valves vill be opened long enough to complete the necessary recharging.
Plant conditions during the test require the reactor to remain shutdown. Although the plant has achieved initial criticality, the fuel is considered non-irradiated and vill remain so throughout testing.
Technical Specification requirements for containment integrity vill be adhered ;o and the applicable Technical Specification requirements met if the test connection valves are opened.
The test connections are located in the Auxiliary Building and are continuously acces;ible and therefore may be closed, if required, at any time.
From the above, it is concluded that the probability of occurrence or the consequences of an accident or malfunction of equipment l
important to safety previously evaluated in the FSAR is not l'              increased and that no possibility for an accident or malfunction of a different type than any evaluated in the FSAR is created.
III. No. Technical Specification requirements are not violated.
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SE No.:                86-216                                                                    l Source Document:                  DCN-0847                                                       ,
t Description'of Change h                                            Draving change to add Valve OG61F0594 (Liquid Radvaste Sumps System) in                   l order to reflect as-built on Draving D302-741.
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-                                          I. No.              The addition of this valve does not affect any text of the FSAR.          I I'                                        II. No.              This valve serves no safety-related function and is not directly         i related to safety-related equipment.
III. No.               This valve is not mentioned in the Technical Specifications.             !
i SE No.:                86-217                                                                  ]
Source Document:                  DCN 0998 3
Description of Change l
Draving change'to change Master Parts List numbers of the Standby Diesel Generator starting air solenoid valves on Drawings D302-351 and 4549-57-031 to agree with Elementary Viring Diagrams B208-216 Sheets 5                    -
and 7.
Summary I. No.              The subject drawing change resolves an equipment tagging discrepancy, restoring tagging consistency for the valves on the referenced design documents. The plant design as evaluated and approved by the NRC remains unchanged.
II. No.              The subject change does not create or add any naw unevaluated design parameters.
The Technical Specifications are not af fected by the subject drawing   ;!
III. No.                                                                                        i change.
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SB'No.:       86-218 Source Document:          DCN 0951 Description of Change
                                      'Draving change on diagram drawing to'show the alarming of the opening of the Steam Bypass Valves 1C85F0001 and F0002 and the correcting of the source location of Computer Point 1C85NC001 to agree with the Elementary                                       ,
and Viring Drawings (D302-021).                                                                                 '
Summary I. No. Correcting the diagram drawing to agree with the elementary and viring drawings does not change the basic design functions of the equipment in the Steam Bypass and Pressure Regulation System.
II. No. See I above.                                                                                              1 III. No.      Correcting the diagram drawing to show valve opening / alarming, and correcting the socree location for the computer point does nc '
change any margin of safety as defined in the Technical Specifications.
SE No.:       86-219 Source Document:          DCN 0545 Description of Change Drawing change to relocate piping specification and class break to outb(ard veld of 1E22F011 (HFCS System) (D302-701).
Summary                                                                                                                 >
I. No. This is a minor editorial change to the Figure (6.3-7 Sheet 2 of 2) in the FSAR that has no impact on the previously' evaluated occurrences or consequences of an accident or malfunction of safety-related equipment.                                                                                 ;
II. No. This is a minor editorial change that does not create the possibility for an accident / malfunction of a different type than that previously evaluated.
III. No.      This is a minor editorial change to better define piping specification / class break, which has no impact on margins of safety for the plant Technical Specifications.
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SE No.:    86-220 Source Document:      STI-N31-024 Description of Change This safety evaluation was performed to evaluate the differences between STI-N31-024, Turbine Valve Surveillance, Rev. 2 and the FSAR Section 14.2.12.2.21 and Table 14.2-2, Start-up Tests.
FSAR 14.2.12.2.21 states that valve testing vill be performed at increasing power levels along the 100% load line. The Start-up Test Instruction has been changed to include valve testing along the bounding licensed load line.
FSAR Table 14.2-2 states that the Start-up Test Instruction is performed at Test Conditions 2, 5, and 6. The STI has been changed to schedule testing at Test Conditions 2, 5, 6, 7, and 8.
SSER 8 Section 15.1 approved operation in this extended operating domain for plant start-up testing.
Summary I. No. HEOD operation has been analyzed in Chapter 15 of the FSAR.
II. No. See I above.
    -III. No. The effect of MEOD is covered in the Flant Technical Specifications.
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SE No. 221 i        Source Document:                   STI-G42-119
                                                                                                                         'l Description of Change This safety evaluation was performed to evaluate a difference between STI-G42-119, Suppression Fool Cleanup System and FSAR Table 14.2-2, Start-up Test.
FSAR Table 14.2-2 states that the Start-up Test Instruction is performed i
in Test Conditions OV, 2, and 6. The STI has been changed to perform testing in Test Conditions OV, 2, and 8.                                                      1 SSER 8 Section 15.1 approved' operation in this extended operating domain for plant start-up testing.
Summary                                                                                                         :
The test is performed following the full reactor isolation, i
I. No.
(STI-B21-025B).
!                   II. No.       Operations in the HE0D-region has been analyzed in Chapter 15, Appendix E of the FSAR.
III. No.             The margin of safety for any Technical Specification is not reduced.
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1 SE No.:                  86-222 Source Document:                        FSAR CR No. 86-102 Description of Change FSAR change (Section 6.'7.3.5), to change the E32-N602 timer.(HSIV Leakage control System) setpoint to 30 minutes as justified by plant specific dose. calculation.           (Mechanical Evaluation) (Reference SER Section 6.5.2) 1 Summary I. No.             The E32 HSIV Leakage Control System controls and minimizes the
                  &                 release of fission products which could leak through the closed main II.                  steam isolation valves after a LOCA. The system provides this control by processing MSIV leakage prior to release to the atmosphere through the Annulus Exhaust Gas Treatment System.
The design basis-LOCA which results in the greatest release of radioactive material to the containment results from a complete                          1' circumferential break of one of the two recirculation loop pipes.
Section.15.6.5.5.1.2 (Fission Product Transport to the Environment)                     ,
of the FSAR describes the transport paths for the design basis radiological dose calculation. Subitem d (page 15.6-19a) defines the assumed leakage through the HSIVs to the Annulus Exhaust Gas Treatment System (M15). Subitem d states: " Assuming the HSIVs. leak 25.0 cfh per valve, leakage past the inboard HSIVs is conservatively assumed to begin immediately after the accident." This assumption is-conservative because the HSIV-LCS is manually initiated and until that' time, flov to the AEGTS is zero. The dose calculation does not take credit for the delay involved in starting the system.
The proposal to change the N602 timer to 30 minutes vill not affect the dose calculation presently defined in Chapter 15 since a time delay is not considered in the analysis. Therefore, an unanalyzed condition does not exist.
From a E32 system level standpoint, increasing the N602 setpoint vill result in additional bleeddown time of the main steam pipe volume between the inboard and outboard MSIVs.      Since this volume                    '
has been isolated from the reactor as the result of a LOCA signal, bleeddown time is not relevant to the operation of the E32 system.
In the unlikely event of an inboard HSIV failure to close, the potential exists to blowdown the reactor vessel through the open MSIV, LC subsystem and into the AEGTS.      However, pressure interlocks                !
and "HSIV closed" permissives are part of the design to prevent initiation of any subsystem with abnormally high steam line pressure                      ;
or failure of the HSIV to close.                                                         l III. No.                The margin of safety as discussed in the Technical Specifications vill not be affected as a result of a change in setpoint.
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j SE No.:    86-223 Source Document:      SCR 1-86-1212 & 1-86-1213 Description of Change Setpoint revision of allovable limits of 1B21N693A&B (Nuclear Boiler System) to 220.1" vater column (RCIC Trip Shutoff - R.V. Level 8). Also the addition of 220.7" vater column safety limit.
Summary I. No. This revision of the allovable limits does not affect the performance of RCIC's safety function after an accident. This change ensures that the main steam lines vill be protected from a vater slug since the allovable limit is decreased in the conservative direction. The reliability of the affected channels is enhanced and the consequences of an accident are not increased.
II. No. In addition to the above explanation, FSAR Section Table 15.4-4 describes only R.V. Level 2 trip unit actuation to alleviate a rod drop accident. These changes do not create an additional possibility for an accident / malfunction.
l III. No. The margin of safety is not reduced.
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SE No.:     86-224                                                                                                     '
Source Document:        SCR-1-86-1224 thru 1227 (DCP 86-665, Rev. 0)
Description of Change Design change to allow for the replacement of Control Relays for lE32-N653A, E, J & N trip units with time delay relays (HSIV Leakage Control System). This is required to allow continued operation of the system in the event of intermittent flow signal spikes. (I&C Evaluation)
Summary I. No. .The replacement of Control Relays E32-KlA,E,J&N in the HSIV Leakage Flov Trip Unit Circuit, with a time delay relay vill not create an accident since this system is only used after a LOCA has occurred.
The time delay is required to dampen spikes in the flow transmitter output thereby eliminating spuriouc trips. This delay vill only last about 20 seconds, and since the FSAR Section 6.7.3.5 states that the trip units vill be bypassed for approximately 13 minutes, the extra 20 seconds will not have an adverse effect on the system operation.
II. No. The relays are replacing m es that vere already evaluated in the HSIV-LCS Control Circuit. The new relays are safety-related i.e.,
seismically qualified devices, their only differen-e being a delay on energizing which vill not create a malfunction. No new equipment is being added, relays are just being replaced.
III. No. These relays are not a part of the Technical Specifications.
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                                                 - 109 -
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SE No.:    86-225
    -Source Document:        SCR's 1-86-1228 through 1-86-1231 Description of Change Setpoint change, to change the E32-N0602 timer delay setting (MSIV Leakage Control System) to 30 minutes i 30 seconds. (Reference SER Section 6.5.2)
Summary I. No. The E32.HSIV Leakage Control System controls and minimizes the
        &-      release of fission products which could leak through the closed main II.       steam isolation valves after a LOCA. The system provides this control by processing MSIV leakage prior to release to the atmosphere through the Annulus Exhaust Gas Treatment System.
i The design basis LOCA which results in the greatest release of radioactive material to the containment results from a complete circumferential break of one of the two recirculation loop pipes.
Section 15.6.5.5.1.2 /?ission Product Transport to the Environment) of the FSAR describes the transport paths for the design basis radiological dose calculation. Subitem d (page 15.6 19a) defines the assumed ' leakage through the HSIVs to the Annulus Exhaust Gas Treatment System.(H15). Subitem d states: " Assuming the HSIVs leak 25.0 cfh per valve, leakage past the inboard MSIVs is conservatively assumed to begin immediately after the accident." This assumption is conservative because the HSIV-LCS is manually initiated and until that time, flow to the AEGTS is zero. The dose calculation does not take credit for the delay involved in starting the system.
The proposal to change the N602 timer to 30 minutes vill not affect                                             :
the dose calculation presently defined in Chapter 15 since a time                                               ;
delay is not considered in the analysis. Therefore, an unanalyzed                                               'j condition does not exist.
From a E32 system level standpoint, increasing the N602 setpoint vill result in additional bleeddown time of the main steam pipe volume between the inboard and outboard HSIVs.      Since this volume has been isolated from the reactor as the result of a LOCA signal, bleeddown time is not relevant to the operation of the E32 system.
In the unlikely event of an inboard MSIV failure to close, the potential exists to blovdown the reactor vessel through the open MSIV, LC subsystem and into the AEGTS. However, pressure interlocks and "HSIV closed" permissives are part of the design to prevent                                                ;
initiation of any subsystem with abnormally high steam line pressure or. failure of the HSIV to close.
III._No. The margin of safety as discussed in the Technical Specifications vill not-be affected as a result of a change in setpoint.
                                               - 110 -
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     -SE'No.:      86-226 Source Documentt         DCP 86-665, Rev. 0                                                       ,
Description of Change Design change to allov for the replacement of control relays for 1E32-N653A,E,J6N trip. units with time delay relays (MSIV Leakage Control System). This is required to allow continued operation of the system in                    k the event of intermittent flov signal spikes.       (I6C Evaluation)
Summary                                                                                          j I. No. The replacement of control relays E32-K1A,E,J6N in the HSIV leakage flov trip unit circuit, with a time delay relay vill not create an accident since this system is only used after a LOCA has occurred.
The time delay is required to dampen spikes in the flov transmitter output, thereby eliminating spurious trips. This delay vill'only-last about 20 seconds,.and since the FSAR Section 6.7.3.5 states that the trip units vill be bypassed for approximately 13 minutes, the extra 20 seconds vill not have an adverse effect on the system                 ;
operation.
II. No. The relays are replacing ones that were already evaluated in the MSIV-LCS Control Circuit. The new relays are safety-related i.e.,
seismically qualified devices, their only difference being a delay on energizing, which will not create a malfunction. No new equipment is being added, relays are just being replaced.
III. No. These relays are not a part of the Technical Specifications.
                                                    - 111 -
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SE No.:                          86-227 Source Documents                            .DCP 86-602D, Rev. 6 Description of Change Design change to allov for the installation of anchor bolts, temporary access hole, grout, and the cutting of rebar for the Safety-Related i                                                    Instrument Air System low pressure storage tanks.
Summary I. No.                        The capacity of the slabs is still adequate to support the design loads. The cutting of four north-south rebars that are non-load bearing secondary bars and one east-west bearing bar vill not co.mpromise the ability of the Auxiliary Building. slab to support the design loads. The cutting or three east-vest bars and two north-south bars vill not compromise the ability of the Fuel
                                                             . Handling Building foundation mat to support the design loads.         ,
Removal of concrete for Access Hole (Approx. 18" by 18") through the Auxiliary Building roof does not affect the design capacity of the roof. The cutting of one bar in each direction on the top and-bottom and two shear bars also does not compromise the ability of the roof slab to support the required design loads.
                             .II. No.                          Since.the slab capacity remains unchanged, the possibility of an accident or malfunction is not increased.
III. No.                          See I above.
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SE No.:                  86-228 Source Documentt                     DCP 86-602G, Rev. 1 Description of Change Design change to allov for the fabrication and erection of lifting beam assembly and associated lifting / rigging criteria for installation of the Safety-Related Instrument Air System (P57) low pressure storage tanks.
Suinma ry I. No.         The minor changes to the lifting beam assembly do not affect the load capacity as evaluated in DCP-86-602G, Rev. O. Rev. 1 changed c                               the lifting criteria for the fuel handling P57 tank only, since Section 6 of ANSI N14.6 is not appll-cable to the Fuel Handling Building, since the slab is on grade and no safe shutdovn equipment is affected by this lift.
II. No.            The lifting beam assembly is designed to adequately support the tank loads during installation of the P57 low pressure storage tanks in accordance with the requirements of MAP-1301, NUREG-0612, ANSI N14.6-1978.
III. No.               The lifting beam design and lifting criteria fulfill the safety margins as required.
SE No.:                 86-229 Source Document:                   DCN 0951, Rev. O Description of Change Drawing change for revision of system diagram (Steam Bypass System, 302-021) to agree with the elementary and viring diagram for alarm function on IC05-F001 and F002 opening and also for correction of switch source for Computer Point 1C85NC001.
Summary I. No.       There are no changes in the present design function or operation of the steam bypass system as a result of this drawing change.
II. No.           Evaluation of accidents / malfunctions vill not differ from those in the FSAR vith the incorporation of this drawing change.
III. No.               No safety margins as desccibed in the Technical Specifications are affected by this drawing change.
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SE No.:      86-230 Source Document:          DCP 85-0573D, Rev. O Description of Change                                                                                                    l Design change to allov for the relocation of the dry active vaste handling facility building's heat piping and supports.
               ,(Nonsafety-Related)
Summary
          .I. No. The relocation of piping and supports does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety.
II. No. The relocation of piping and supports does not create the possibility for an accident or malfunction of a different type.                                          .
III. No.      This is not addressed in the Technical Specifications.
SE No.:       86-231 Source Document: ~        HFI 15-571 Description of Change A pipe blank vas installed in the Fuel Pool Cooling and Cleanup System (C41) to provide Unit 1/ Unit 2 separation. This item is not reflected on Figure 9.1-9 in the FSAR.     (Temporary Modification)
Summary I. No. Unit 2 equipment is not relied upon for Unit 1 accident analysis in ihe Fuel Pool Cooling and Cleanup System.
II. No. No different accidents or malfunctions are created by the installation of this Hechanical Foreign Item betveen Unit 2 and common equipment.
III. No.      Unit 2 is not used for any bases of any G41 Technical Specification.
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t SE No.: ' 86-232 Source Document:          DCP 85-067C, Rev. 1                                                    !
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Description of Change Design change to allow for utilities (piping / valves) in the new oil lab in the 599' elevation of the control Complex.
{
Summary                                                                                        J I
: 1. No.       The additional piping and flow requirements for the new lab are minimal and do not affect the probability of occurrence of an                  )
accident.
1 II. No.       The affected areas of these systems are located in an area of the control complex.vhere they vill not increase the' possibility of an            !
accident.
III. No.        The affected areas of these systems are not covered by Technical Specifications.
SE No.:         86-233 Source Document:          FSAR CR No. 86-106 Description of Change FSAR change (Section 13.5) pertaining to the addition of two new volumes to the Operations Manual for Special Test Instructions and Licensing and Compliance Instructions.
Summary I. No.      Administrative. change only, the plant is not affected relative to occurrence and consequences of an accident.
II. No.       See I above.
III. No.        Administrative change only, Technical Specifications are not affected in any manner.
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l         SE No.:     86-234 L
Source Document         SCR 1-86-1001
         . Description of Change
;              Setpoint change to provide a setting for time delay relay 62-C2 L              (1N4305003, Generator Stator Vinding Cooling' System). This relay l              controls the on-off cycling of the load reference motor.
l Summary I. No. The reactor recirculation system is capable (in auto) of following a loss of. stator cooling runback.
[-         II. No. FSAR Chapter 15.2 transients have analyzed for turbine trip.
III. No. Loss of stator cooling runback is not discussed in Technical Specifications.
o-l SE No.:     86-235-Source Document         DCP 86-647, Rev. O Description of Change l
Design change to place a notch in Reactor Building Column '7' to allov for thermal movement of 1" diameter 1C11 pipe (Control Rod Drive System).
Summary I. No. The design capacity of the column including the effects of the indicated notch is adequate to support the design loads and therefore maintains the structural integrity of the co''imn.
II. No. See ' above.
III. No. The stresses were checked against the same allovables as per the original design calculations, subsequently the design margia of safety remains the same.
                                                   - 116 -

SE No.:      86-236 Source Document:        STI-B21-025A                                                                           <
{f' Description of Change This safety evaluation was performed to evaluate a difference between STI-B21-025A, MSIV' Functional Test and FSAR Table 14.2-2, Start-up Tests.
FSAR Table 14.2-2 states that the Start-up Test Instruction is performed in Test Conditions HU, 2, 5, and 6. The STI has been changed to perform                              ,
testing in Test Condition HU,   2,.3, and 8.                                                          j l
SSER 8 Section 15.1 approved operation ~in this extended operating domain for plant start-up testing.
Summary                                                                                                       l I. No. Thia transient has been analyzed in Chapter 15 of the FSAR for the above conditions which include operations in the Maximum Extended Operating Domain (HE0D) region.
II. No. See I above.                                                                                     !
III. No. Operations in the MEUD region are allowed by Technical Specifications.
SE No.:      86-237' Source Document:        STI-833-029A Description of Change This safety evaluation was performed to evaluate the differences between STI-B33-029A, Recirculation Flow Control - Valve Position Loop, Rev. 2                                i and FSAR Figure 14.2-4.
FSAR Figure 14.2-4 defines Test Conditions 3 and 6 to be limited by 100%
core flow. There is no defined region for Test Condition 8. The STI has been changed to perform testing in the increased flow regions of Test Conditions 3 and 6 and the extended load region of Test Condition 8.
SSER 8 Section 15.1 approved operation in this extended operating domain for plant start-up testing,                                                                           ,
Summary I. No. HEOD operation has been analyzed in Chapter 15 of the FSAR.
II. No. See I above.                                                                                     l III. No. The effect of MEOD operation is covered in the Technical Specifications.
                                               - 117 -

SE No.:     86-239 Source Document:                          SXI-002 Description of Change Evaluation of the use of a sp*cial test for the Safety-Related Instrument Air System, which is the system retest following the design change to l
allow for the addition of two, lov pressure air storage tanks.
Sumtary I. No. This retest vill ensure the new system meets the design criteria r    cified and therefore does not increase the probability or t asequences of an accident. The retest is consistent with the requirements specified for testing in FSAR Chapter 14.
II. No. See I above.
III    No. The performance of this test does not alter the margin of safety.
It vill demonstrate the system performs as designed.
I SE No.:      86-240 Source Do'ument:                               DCP 86-494, Rev. 1 Description of Change Review os the attachment of nonsafety/nonseismic related conduit supports to safety related beams in the Reactor Building; pertaining to a design change to add a Hygrometry Sampling System to ensure adequate sample flov to the humidity sensor in the Containment Atmosphere Monitoring System.
i Summary I. No. The loads being added to the safety-related beams are minimal when compared to design service loads. The structural integrity of the beams is not impaired by the additional loads.
II. No. Attachment to the safety-related beams does not create the possibility for an accident or malfunction of a different type than previously evaluated.
III. No. See I above.
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SE No.:      86-241 Source Documents.        DCP 86-008, Rev. O I
Description'of Change-Design change to allow for concrete " Knockout" removal in the Radvaste Building.
Summary I. No. . concrete " Knockout" removal affects only the building structure in a localized area. The original building design took'into account the   ,
possible " future" removal'of this " Knockout". There is no safety l.
equipment in the area.
l II. No. No equipment or systems related to safety are involved in the removal of the concrete " Knockout".
III. No. Margins of safety are not reduced as the " Knockout" was a built-in design feature.
l                           .SE No.:      86-242 i                            Source Document:        DCN 01086 Description of Change Draving change to incorporate HPL number to Strainer (Dvg. No. 302-713).
Editorial change.
Summary I. No. There is no change to equipment.
II. No. See I above.
III. No. See I above.
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                  'SE No.:      86-243 Source Document:                                                     DCP 86-0679, Rev. O.
Description of Change i
Design change to add control viring, etc., to trip the neutralization basin pumps (P21-C010A&B, Two-bed demineralized) based on pH readings from a portable pH meter.
l Summary' l
I. No. The controls for the vaste neutralization basin pumps serve no
;                               safety function.-
l L                    II. No. See I above.
III. No. Not addressed by Technical Specifications.                                                                                                                                           i SE No.:      86-244' Source Document:                                                      DCP 86-0541, Rev. O Description of Change Design change to allow for the installation of an 8" Fire Protection System Line to the fire training area to provide two new fire hydrants.
(Nonsafety-Related)
Summary.
I. No. Items are within scope of fire protection procedures and vill not affect, hinder, malfunction or.cause an accident important to safety.                                                 Does not affect safe shutdown.
II. No. There are no potential' initiating causes of threats to the plant.
III. No. Only administrative aspects of fire protection are addressed in Technical Specifications.
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l SE No.:                  86-245 L  Source Document:                      DCP 86-0550, Rev. 4 Description of Change Reviev of installation of Hilti Kvik bolts into safety-related concrete l
in the Radvaste Building; pertaining to design change to Liquid Radvaste Disposal System to allow for the addition of an Evaporator Feed Strainer and filter to reduce the amount of resin that is breaking down in the l
!                     feed and resulting in increased conductivity.
Summary I . . No . Ililti bolts are designed such that they do not impair the structural integrity of the building.
l              II. No.      The Ililti bolts do not create the possibility for an accident or malfunction of a different type than-previously evaluated.
III. No.               See I above.
SE No.:               86-246 Source Document:                  DCP 85-067F, Rev. O Description of Change l                      Review of interface for additional loads on steel beams at the 599' elevation (of the Control Complex) for potential seismic clearance violations. Pertains to the design change to add an oil analysis lab.
Summary The loads being added to the beams are insignificant and negligible
                                                                  ~
                .I. No.
when compared to design service loads. The structural integrity of the beams is not impaired by the additional loads.
II. No.      Attachment to the safety-related beams does not create the possibility for an accident or malfunction of a different type than previously evaluated.
III. No.           See I above.
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SE No.:      86-247 Source Document:        UR MH05 1228 Description of change Evaluation of Nonconformance Report pertaining to the use-as-is d.sposition for using the Unit 2 transmitters (2E31-N023A and 2E31-N023D) in the Unit 1 system (in lieu of 1E31-N023A which failed) (Leak Detection System).
Summary I. No. The application of 1E31N023A in the design of the Perry Plant is nonsafety and the transmitter is not discussed in the FSAR. The use-as-is disposition for the Unit 2 flow meters does not change the nonsafety design application.
II. No. See I above.
III. NO. The application of these flow meters is not described in the                             )
Technical Specifications.                                                               l SE No.:      86-248                                                                                  )
STI-B21-020, Rev. 2                                                          j Source Document:
Description of Change                                                                                ,
This safety evaluation was performed to evaluate the difference between                      )
STI-B21-020, Steam Production, Rev. 2 and FSAR Table 14.2-2, Start-up Tests.
FSAR Table 14.2-2 states that the Start-up Test Instruction is performed in Test Condition 6. The STI has been revised to schedule testing in Test Condition 8. -The initial conditions for this test have not changed.
SSER 8 Section 15.1 approved operation in this extended operating domain for plant start-up testing.
Summary I. No. This test is performed with TC-6 test conditions but is being performed in the TC-8 plateau, therefore it is evaluated for the conditions it is being performed in.
II. No. -This test collects data while the plant runs at rated conditions (100% power, 100% core flov) thus it is evaluated by the FSAR.
III. No.-    This test collects data while the plant runs at rated conditions (100% power, 100% core flov), thus it does not reduce the margin of safety as defined in the Technical Specification bases.                              ,
                                                                     - 122 -

SE No.:    86-249 Source Document:        MEI 605-1 Description of Change Evaluation for use of a fine mesh screen filter at inlet flange to 1E31N021 (Leak Detection System) thru tjuclear Heatup.
S,ummary I. No. The likelihood of a malfunction is consistent with the original design. In the possible event of the screen blocking, the potential identified leakage bypasses to the sumps.
II. No. This vill not change the function or create any new malfunctions.
III. No. The same margin of safety is maintained.
SE No.:    86-251 Source Document:        DCN 1011 Description of Change Draving change (E023-019) to eliminate door CC-507 as a required fire door. The occupancy has been changed to a light hazard office from nigh combustible loading chart storage. The need for a separate fire reea no longer exists and vill not affect safe shutdown.

==SUMMARY==

I. No. Items are within the scope of fire protection procedure and vill not affect, hinder, malfunction or cause an accident important to safety.
II. No. There are no potential initiating causes of threats to the plant.
III. No. Only administrative aspects of fire protection are in the Technical Specifications.
                                      - 123 -

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SE No.:                                       86-253 Source Document:                                                        DCP 86-0714, Rev. O Descri1 tion of Change                                                                                                                                                          s Design change to the RVCU Dif ferential Flow Heasuring System to allow for the addition of a dynamic compensator to dampen flov spikes.
Summary I. No.                       The safety analysis in Chapters 6, 9 6 15 do not take credit for RVCU isolation. The addition of qualified dynamic compensators vill thus not a'ffect any previous analyses.
II. No.                             The single failure criteria provides backup circuitry for the RWCU Flow Measuring System.                  Both A & B dynamic compensators are                                     l qualified and do not adversely affect the correct operation of the system.                  System reliability is enhanced by decreasing spurious trips of the timing relay (potential isolation).
III. No.                                   The addition vill not affect the actual setpoint, it vill only delay '                                                               s
(= 2 sec.) the signal between the summer and the trip unit'.                                                      .-
Therefore the margin of safety is not reduced. (Technical                                                         J.
Specification Table 3.3.2-3 designates the response time of this instrument channel trip function as N/A).                                                                          ,          ;
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SE No.:                                   86-254 Source Document:                                                    DCP 86-383A, Rev. O Description of Change Design change to allow for chipping of concrete dryvell floor to provide clearance for pipe clamp.
Summa,t;y I. No.                   Removal of 1" of the rebar covet does not affect the structural integrity of the floor slab.
II. No.                          The structural integrity of the floor is not impaired, therefore the possibility of an accident or malfunction is not increased.
III. No.                                See I above, s,   '
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SE No.:                86-255 Source Document:                   DCP;85-694, Rev. 4 Description of Change Design change to allov for changes in ductv rk to climinate noise probism and the installation of orifice plates to d.i .in airflov balancing for                                 '
the Radiation Protection Office.
s o Summary                                                           ~                                               ~
                                                                                                 ,8                                     \
: 1. No. The change af fects onlyl the airflow in a select area of y:he Control Complex. The Coptrolled Access Area HVAC System (non-nfety                                     '
related) overall function is not affected.
II. No.           SeeIaboh,.(
III.-No.            See I above.
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            '>,                                  y SE No.:             86-756 Source Documslitt               UCP'E6-495,Rev: 0 Description of Chany ReviewofinstallationofHilf.icbaltsinsafety-relatedconcrete(inthe Reactor Building and Auxiliarv Bjailding); pertaining to a design change C s
to install permanent mountingtbnsckets so that calibration volume chambers can be temporarily mou.)ted         '
during calibration for'various instruments.
1 Summary I. No.       HiL(1 bolts are designed such that they do not impair the structural
                                                 '\
                                                                 $ntWrity of the building.
                                                                   . ,                                             (                           .                1 II. No.         Sed'l above.              ,
(
III. No.            Sce'.I above.                                                                      (
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SE No.:   86-257 Source Document:     PNPP Emergency Plan, Rev. 6 Description of Change Revision No. 6 to the Perry Nuclear Power Plant Emergency Plan. Changes
                                                                                                      -)
pertain to editorial / administrative changes or an upgrade of the             l energency plan.
Summary-l I. No. This revision does not affect previously evaluated probabilities of an accident or malfunction of equipment.
II. No. This revision does not cause a potential for an accident or malfunction of a different type than ev-luated previously.
III. No. This~ revision does not direct any evolutions affecting the margin of   ,
safety.                                                                 <
SE No.:   86-258 Source Document:     STI-B21-025B, Rev. 2 Description of Change This safety evaluation was performed to evaluate a difference between       l STI-B21-025B, Rev. 2, Full Reactor Isolation and FSAR Table 14.2-2,          ;
Startup Tests.                                                               l FSC Table 14.2-2 states that the Startup Test Instruction is performed in Test Condition 6. The STI has been changed to perform testing in Test   ;
Condition 8.                                                                 )
Test Conditions 7 and 8 vere added to FSAR Figure 14.2-4 to rollect additional testing along the licensed load line at lov and high flow conditions (see PY-CEI/0IE-0231 L, dated August 28, 1986).
SSER 8 Section 15.1 approved operation in this extended operating domain for plant startup testing.
Summary I. No. This transient has been analyzed in the HEOD region in Chapter 15, Appendix E of the FSAR.
II. No. Operations in the HEOP regionf has been analyzed in the FSAR.
III. No. The margin of safety for any Technical Specification is not reduced by performing this. instruction.
                                                           - 126 -

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SE No.:        86-259 Source Doctrmenu           EDDR No. 230 h                                            DCP 86-646 l
Description of Change L
Design change to allow for the continued use of a non-class 1E metor in j
l Valve 1E51-FS10 (Reactor Core Isolation Cooling) until a new mot:.c
                         .(Class.1E) can be installed. This non-class 1E motor is supplied from a        l l                         class 1E power source and is.a part of the original design.
I Summary I. No. This motor is not essential to.the operation of the RCIC turbine.
Sufficient separation exists so that the 1E pn er system is unaffected for any failure of this motor.                              j i
II'. No. Failure of this motor cannot create an accident or other malfunction. The RCIC' turbine vill operate, and the 1E power system vill not be adversely affected.                                        i III. No.       The Technical Specifications do not address electrical separation. l The RCIC operation is unaffected by failure of the 1E51-F510 valve     l motor.                                                                l SE No.:         86-260                                                                ,
Source Document:-         .ST1-B21-033, Rev. 2                                       j Description of Change                                                                !
This safety evaluation was performed to evaluate a difference between        :
STI-B21-033, Drywell Piping Vibration and FSAR Table 14.2-2, Startup         l l
Tests.
FSAR Table 14.2-2 states that the s'artup Test Instruction is performed in Test Conditions HU, 1, 2, 3, 5, and 6. The STI has been changed to i
perform testing in Test Conditions HU, 1, 2, 3, 5, 6, 7, and 8.
SSER 8 Section 15.1 approved operation in this extended operating domain for plant startup testing.
Summary I. No. The above transients have been analyzed for the ME0D regions in
                                                                                                        )
Chapter 15, Appendix E, of the FSAR.
l II. No.       Operations in the MEOD regions have been analyzed in the FSAR.
III. No.        The margin of safety for any Technical Specification is not reduced by this instruction.
                                                               - 127 -                                   ;
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SE No.:                        86-261                                                                                         l Source Document:                          STI-P99-122                                                                        ;
Description of Change This safety evaluation was per?ormed to evaluate a difference between STI-P99-122, B0P Piping Expansion and Vibration and FSAR Table 14.2-2,                        ~1 l
Startup Tests.
PSAR Table'14.2-2 states that the Startup Test Instruction is performed in Test Conditions HU 1, 2, 3, 5 and 6. 'The STI has been changed to
                              ' perform testing in Test Conditions HU 1, 2, 3, 5, 6 and 8.
SSER 8 Section 15.1 approved operation in this extended operating domain for plant startup testing.
     ' Summary I. No.                  HEOD operation has been analyzed in Chapter 15 of the FSAR.
l l       II. No.                      HEOD operation has been analyzed in Chapter 15 of the FSAR.
I      III. No.                      The effect of HEOD operation is covered in Plant Technical Specifications.
SE No.:                       86-262 Source Document:.                        DCP 86-712, Rev. 0                                                                 )
Description of Change Design change to add potable water line to fire training area and as built drawing D302-382.                                                                             l Sum nory I. No.                 FSAR Section 9.2.4.3 states that potable water has no safety function.
II. No.                       The Potable Vater System is separate from, and can have no affect on any safety systems. Therefore, there exists no possibility for an accident or malfunction with any equipment important to safety.
III. No.                       Technical Specifications do not reference potable water.
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1 SE No.:         86-263
                     ' Source Document:          DCP 86-0612A, Rev. O Description of Change                                                                                           1 L                               Design change to allow for the installation of 0-ring insert to eliminate                           f aeat leakage to Safety-Related Instrument Air Valves IP57F509B and F510B.                             l l
Summary I . . No . The addition of redundant sealing surfaces on the check valve reduces.the probability of the loss of pressure in the                                       !
Safety-Related Instrument Air System.
II. No.      See I above.
III. No.       The availability of the Safety-Related Instrument Air vill increase.                         l 1
l SE No.:        86-264 Gource Document:          DCP 86-138, Rev. 0
[
Description of Change Design change to allow for clarification of viring termination for conductivity recorders OG50R424A & B (Liquid Radvaste Disposal System).
Each recorder has one log scale and one linear scale. This modification puts both log scales on the same recorder and both linear scales on the                            ,
other recorder.                                                                                   l Summary I. No. Relocating of existing channels on existing recorders does not                              )
increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR.                                                                      .
II . N.1     See I above.
III. No.       These recorders are not mentioned in the Technical Specifications.
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SE No.:     86-265                                                                                                               ,
Source Document:       DCP 86-0382, Rev. 1                                                                                      1
    -Description of Change Design change.to redefine dir4 ovs and increase fan speed (Auxiliary Building Ventilation: System) to teep constant flow under dirty filter conditions thru exhaust fans and *o maintain proper airflow direction.
                                                                 ~
(Equipment Qualification Evaluation).
Summary I. No. 'All equiptent within affected zones remains qualified under revised temperature conditions for both normal and abnormal as well as accident conditions.
II. No. Revised temperatures do not create the possibility for an accident or malfunction not evaluated previously in the FSAR, since all affected equipmei:t remains qualified.
III. No. See I above.                                                                                                        ;
SE No.:     86-266-Source Document:       DCP 86-382, Rev. 1 Description of Change i
Design change to redefine system airflows and increase fan speed.                                                        !
Changes are required to keep constant flow under all dirty filter                                                       .l conditions and to maintain proper airflow direction. (Mechanical Evaluation)
Summary, I. No. This change vill not cause a design basis accident to occur. The                                                   i Auxiliary Building Ventilation System is non-safety related, and is                                                ,
not required to safely shut down the plant.
II. No. Change in design airflows will allow the system to function as designed, to keep constant exhaust flow rate at all times, and to keep airflow in proper direction.                                                                                  l III. No. The margin of safety is not reduced.                                                                               ,
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1 SE No.:     86-267 Source Document:        DCN 01162 Description of Change                                                                                        s l'
Drawing change to provide for the addition of MPL number (0G50F618B) to                                    j I
Drawing 302-733.                                                                                          1 l
Summary
      'I. No. This change is only adding an MPL number to an existing valve. This valve serves no safety function.
II. No. Sec.I above.
III. No.-    See I above. This valve is not listed in the Technical                                             .
Specifications.                                                                                   l SE No.:      86-268-                                                                                            '
Source Document:        STCN 005-2-04 to STI-C11-005 i
   . Description of Change This safety evaluation was performed to evaluate a difference between STCN 005-2-04 (for STI-C11.-005, Control Rod Drive System) and FSAR Table 14.2-2, Startup Tests.
k FSAR Table 14.2-2Lstates that the Startup Test Instruction is performed in Test Con-l'tions OV, HU, 1, 3, and'6. The STI has been changed to perform te, .ng in Test Conditions OV, HU, 1, 3, 6, and 8.                                              i SSER 8 Section 15.1 approved operation in this extended operating domain                                ,
for plant startup testing.
Summary I. No. The plant operation in HE0D is evaluated in Chapter 15, Appendix E, of the FSAR.
See I above.
II. No.
III. No. Operation in ME0D is addressed in the Technical Specification.
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                                             - 131 -

i SE'No.:   86-269 Source Document:      FSAR CR No. 86-123 Description of Change Changes to FSAR Chapter 13, pertaining to the addition of. responsibility                                I for preparation of periodic test instructions by the Instrumentation and Control Section. Also,' adding the responsibility for preparation of                                     j special test instructions by the Maintenance, Technical, Operations,                                     i Radiation Protection and Instrumentation and Control sections. Making some corrections to preparation responsibilities.for other instruction                                   .
types contained in the operations manual. Also, the addition     of Plant                               -!
Round Instructions to Volume 4 of the PNPP Operations Manual.                                            l Summary                                                                                                       i I. No. Administrative change only. Does not change the occurrence or                                      !
consequences of an accident or malfunction of equipment.
II. No. See I above.
III. No. Te'chnical Specifications are not af fected in any manner.
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i SE No.:                                  86-270 Source Document:                                    DCP 86-0756 Description of Changa Design change to modify RHR system electrical viring and relay logic to reflect valves 1E12F037A and B actuating closed on high reactor vessel pressure in lieu of high dryvell pressure.
Summary I. No.             The RHR upper containment pool cooling lines to which Valves 1E12F037A cnd B are associated, are only utilized (opened) during Plant Mode 5, refueling and core alterations, by diverting the RHR shutdown cooling flov from the feedvater lines. FSAR Section 15.4.9 (Control Rod Drop Acc.ient) does not account for operation of the RHR upper containment pool cooling flov (or lack of it) when analyzing recovery from the rod drop accident. The proposed electrical circuit changes affecting Valves lE12F037A and B closure thus do not impact FSAR Section Analysis 15.4.9. Analysis in other sections of FSAR Chapter 15 or FSAR Chapters 6 and 9 also do not     ,
take credit for upper containment pool cooling flow.                 l II. No.                   Changing the electrical circuit viring to actuate 1E12F037A/B closed on high reactor vessel pressure does not create a different type of accident or malfunction to be analyzed in the FSAR. As noted in Item I above, lE12F037A and B are utilized in the upper containment pool cooling lines. FSAR Section 15.4.9 does not account for upper pool cooling when analyzing the control rod drop accident.
III. No.                          Technical Specification Table 3.6.4.1 and Table 3.3.2-2 currently reflect Valves 1E12F037A and B as being Group 4 valves. Group 4 valves as clarified by FSAR Table 6.2-32 actuate closed on high reactor vessel pressure in lieu of high dryvell pressute
                                                                                                                                                                       - 133 -

l SE No.:       86-271
    , Source Document,:        DCP 85-819A, Rev. 0 Description of Change Design change ',o allow for the trimming / notching of jet shield (ABIC5H7)                           i to permit thermal growth of Reactor Core Isolation Cooling lines.                                     I Summary I. No. Trimming / notching the jet shield vill not impair the structural                               l integrity or function of the jet shield.
l II. No.      The jet is adequately shielded. The notched area is outside the area where the jet vill hit the jet shield.
III. No.      See I above. The Technical Specifications are not affected.
SE No.:       86-272 Source Document:         DCN 538 Description of Change Drawing change to add MPL number for fire damper to the drawing (D-912-608).
Summary I. No. Adding an HPL numbar vill not affect the damper.
II. No.      See I above, l
III. No.      See I above.                                                     a                              q I
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SE No.s. 86-273 Source Document:                         DCP 85-0819A, Rev. 1 Description of Change
'                                   Design change to allow for additional trimming and modification of jet shield (ABIC5H7).s change needed to allow thermal growth of Reactor Core     1 Isolation Cooling piping and modification to accommodate future removal.
                                                                                                               'l Summary
                                'I. No. Trimming and modifications to the jet shield vill not impair the structural integrity or function of the jet shield.
II. No.         The jet shield is still adequate to shield the postulated jet.
Notched areas are outside where the jet hits the shield.
III. No.                   See I above.
SE No.:                  86-274 Source Document:                     DCP 86-175, Rev. O Descri]' ion of Change Design change to allow for the addition of a water trap for the service     ,
air inlet line to the condensate demineralizers to prevent back leakage     )
J of wate'r from the Condensate System.
Summary                                                                                       !
I. No. The condensate demineralizers serve no safety function.               ;
II. No.      See I above.                                                          l III. No.               This system is not a part of the Technical Specifications.
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SE No.:                                                 86-275 Source Document:                                                          FSAR CP No. 86-101 Description of Chany Change to the FSAR (Section 8.3.1.1.3.3) to clarify the HPCS diesel generator overcrank function.
Summfry I. No.                                     The subject change to the FSAR eliminating the bypass of the overcrank function of the HPCS diesel during presence of a LOCA signal vill not affect the safety evaluation of the plant with respect to the function.and reliability of the HPCS diesel. The overcrank function activates after the equipment has failed to start and failed to perform its intended safety function. The Plant Safety Analysis does not require the equipment to function once it has failed. The overcrank function provides additional reliability by ceasing additional automatic start attempts to ensure an adequate supply of starting air is available in the receiver tanks to attempt a manual start after the cause of the failure to start is corrected.
II. No.                                          This change is a clarification to the text of the FSAR and requires no physical equipment modification, since all qualifications of the equipment are maintained. The original safety evaluation is unaffected, and no physical changes to the equipment have occurred.
III. No.                                               The plant Technical Specifications are not affected by the subject change.
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i SE No.: .86-276 Source Document:            DCP 86-0008A, Rev. O i
description of Change Review of the installation of Hilti bolts in safety-related concrete in the Radvaste Building. Pertaining to-the design change to " knockout",
the reverse osmosis room vall and the relocation of a security panel and a rolling steel door operator.
Summary I. No. Hilti' bolts are designed.such that they do not impair the structural integrity of the building.
The Hilti bolts do not create the possibility for an accident or
                                                                                   ~
II. No.
malfunction of a different type than previously evaluated.
III. No.       The installation of Hilti bolts does not affect the Technical Specifications, i
CE No.:        86-277 Source Document:           DCN 0492 Description of Change Drawing' change to update varior     evings (D206-053 6 054, and                       :
D209-209-6) to match as-built            is pertaining to power sources.               ;
i Summary I. No. The feeds for 1H22-P018 and 1H22-P021 are switched from one source to the other. This does not increase the probability of an accident or malfunction of equipment important to safety.
II. No.      No possibility cf a different type of accident / malfunction is created by this change.
III. No.      The margin of safety as defined in the basis for any Technical                      i Specification is not reduced by this change as it switches the power             j source from one panel to the other panel.
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SE No.:    86-278                                                                                        j Source Document:      DCN.0532                                                                            .
                                                                                                                     'i
                                                                                                                     .l Description of Change                                                                                    j Drawing change to update various drawings to match the as-built condition                          i in the field (pertains to correct fuse sizes, correct cable sizes, etc.)                           ;
Summary                                                                                                  j i.
I. No. This change vill not increase the probability of an accident or                               ,
malfunction of equipment important to safety.                                                 )
f II. No. No' possibility of a different type of accident / malfunction is                              I created by this change.                                                                       i III. No. The margin of safety as defined in the bases for any Technical                                !
Specification is not reduced by this change.                                                  j l
l SE No.:    86-279 Source Document:       PEI-B13. TC-0?.
Description of Change                                                                                    !
l L                  . Evaluation of changes to the Plant Emergency Instructions on Reactor Pressure Vessel Control, which accomplishes the following:                                       .j
: 1. Incorporates human factor enhancements made to various control room                         .)
backpanels in an effort to optimize operator response.
: 2. Adds step to place hydrogen analyzers in service                                              l
: 3. Deletes NOTE about manually backvashin ESV strainers.
Summa ry                                                                                                 ;
i                                                                                                                      !
l               I. No. The changes do not deviate from the Perry Specific Technical i                        Guidelines. Hence, the consequences of an accident or equipment malfunction are not increased.
II. No. These changes do not create the possibility of an unanalyzed i                        accident or malfunction, because /JL       comply vith the Perry Specific L                        Technical Guidelines.
j             III. No. These changes are not related to any Technical Specification margin of safety,                                                                                    i L
                                                       - 138 -
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SE No.:             86-280                                                                                i Source Document:                FSAR CR No. 86-115
    ; Description of Change Change to FSAR Section 9.2.1.3 to show utilization of safety'related flov indication to identify when a backwash is needed (ESV System and ESV Screen Wash System, P45 and P49). This will preclude dispatching an operator to l
perform the backvash during a LOCA and LOOP when that backvash is not needed.
Summary I. No. The eight hour criteria for backvashing the P45 and P49 strainers is based on providing design P45 flow to its various heat loads during and following a LOCA and LOOP. During this event, the nonsafety electrical power is not present, .thus the automatic backvashing vill                l not occur. If these strainers become plugged, then the P45 flov vill degrade and not be able to provide sufficient heat removal for the P45 heat loads. To preclude this, the FSAR identified that the backvashing vill be performed within eight hours of the initiating events and thereafter as required. The probability of occurrence or the consequence vill not be increased if a method of equal or higher reliability is employed. Using the safety related flow indications to determine if adequate P45 flov exists is such a method of higher reliability.
All the P45 heat loads have safety related flow indications in the control room except the HPCS room coolcr. The flov to the HPCS room cooler is not needed since the other flow path, HPCS Diesel Generator, is eight times larger and thus vould indicate any                         ;
strainer plugging,                                                                    ,
For only a LOCA, nonsafety electrical power.Will automatically backwash the P45 strainers based on differential pressure. For P49 strainers an alarm vill identify the need for manual backvashing.
II. No.      LOCA and LOOP are evaluated in the FSAR.
f The eight hour criteria is not involved in Technical Specifications.
l III. No.
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                                 'SE No.:                                 86-281                                                                                      {
Source Document:                                  DCN 0410 Description of Change-Drawing change to correct error on as-built drawing to show sample hood vent flov alarm as "L" in lieu of "H" and to show measurement in exhaust duct'(D-302-771).
Summary I. No.            The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the,FSAR is not increased.
II. No.                    The addition of correction of non-safety instrument configuration does not create different types of events for analysis, III. No.                             Details of alarm / sensor configuration are not covered by the Technical Specifications.
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i SC No.:    86-282
          ' Source Document:      STI-F41-034 Description of Change This safety evaluation was performed to evaluate a difference between the test results package for STI-F41-034, Section 8.1, Pre-Nuclear Heatup Flow Test (TSN 030) and FSAR Section 3.9.2.4.
I                The : test results package for TSN 030 does not include data for the controi rod guide tubes. All strain gauges on the control rod guide tubes were inoperable during the Pre-Nuclear Heatup Flow Test.
FSAR Section 3.9.2.4 includes-a listing of sensor locations in the reactor vrssel for flow-induced vibration testing of reactor internals.                          '
Included in this listing are the control rod drive guide tubes.
General Electric has reviewed the inoperability of there sensors and                             l endorses starting nuclear heatup and continuing startup testing.                                 i Summary                                                                                               ;
I. No. 1. CRD guide tubes have historically shown very lov vibration II.             levels.
6 III.        2. Very lov strcin levels vete observed on the CRD guide tube during Perry's pre-fuel load internals vibration test.     (One sensor was operable during the preoperational internals testing).
: 3. Lov vibration levels were observed on all of the components j                            measured in the reactor vessel at various flow conditions (including full flow) during both the pre and post fuel load internals vibration tests.
: 4. FSAR Section 3.9.2.4 states " Previous vibration measurements in BVR's have shown that the fuel adds damping and reduces                                ;
vibration amplitudes of major internal structures."                                    l l
: 5.  "A formal comparison of the Perry configuration and that of other power plants where vibration data has been taken vill have been made by GE Design Engineering to provide the documented justification for this position," prior to plant                            I operation with both recirculation pumps at fast speed.
                                                    - 141 -

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SE No.: .86-283 Source Document:        STI-B33-030C, Rev. 2
!'c           .
Description of Change This safety evaluation was performed to evaluate a difference between STI-B21-030C, Rev. 2, Recirculation System Performance and the FSAR Table 14.2-2, Startup Tests.
FSAR Table 14.2-2 states that the Start'ip Test Instruction is performed in Test Condition 2, 3, 4, and 6. The STI has been changed to perform testing in Test Conditions 2, 3, 4, 6, and 8.
1 Test Conditions 7 and 8 vere added to FSAR Figure 14.2-4 to. reflect additional testing along the licensed load line at lov and high flow cor.ditions (see PY-CEI/0IE-0231 L, dated August 28, 1986).
             .SSER 8 Section 15.1 approved operation in this extended operating domain for plant startup testing.
Summary I. No. This instruction obtains steady-state data in the MEOD region which has been evaluated'in Chapter 15 of the FSAR.
II. No. See I above.                                                                                           ,
III. No. The margin of safety for any Te.anical Specification is not reduced by performing this instruction in the MEOD region.
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SE No.:     86-284 Source Document:        HFI to 1H32 Description of Change                             .
Evaluation of the removal of hydromotors to 1H32-F040 A&B (ESV Pump House Ventilation System) to allow the outside air dampers to be                    j manually opened. The hydromotor is to be replaced or repaired prior to       1 4
September 15, 1986.
Summary I.- No. The probability of occurrence or the consequences of an accident are not increased in the ESV Building provided the outside air              I temperature is greater than 33*F (based on the limiting temperature for the ESV piping). The current outside air temperature vill not be $33'F for any significant period of time prior to September 15, 1986.
II. No. See I above. A more severe environmental condition is not created in the ESV Build.ing, provided the outside air temperature is greater than 33'F.
III. No. The 1H32 System vill pro */ide adequate cooling to the ESV Building and its associated equipmeur.
SE No.:     86-285 Source Document:        HFI to 1H32 Description of Change Evaluetion of the removt 1 of hydromotors to 1H32-F050 AAU (ESV Pump House Ventilation System) to allov the recirculation dsTipers      le manually closed. The hydromotor is to be replaced or ri; tred prior to September 15, 1986.
Summary I. No. The probability of occurrence or the consequences of an accident are not increased in the ESV Building provided the outside air            i temperature is greater than 33"F (based oa the limiting temperature for the ESV piping). The current out side air temperature vill not be $33'F for any significant period of time prior to September 15, 1986.
II. No. See I above. A more severe environmental condition is not created in the ESV Building provided the outside s.ir temperature is greater than 33'F.
III. No. The 1H32 System vill provide adequate cooling to the ESV Buildin o and its associated equipment.
                                                                    - 143 -
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SE No.:     86-286 Source Document:
HFI to 1M32                                                                                  ,
Description of Change                                                                                                l l
Evaluation of the removal of hydromotors to 1M32-F070 A&B (ESV Pump House Ventilation System) to allow the exhaust air dampers to be manually opened. The hydromotor is to be replaced or repaired prior to September 15, 1986.
Summarg.
I. No. The probability of occurrence or the consequences of an accident are not increased in the ESV Building provided the outside air temperature is greater than 33*F (based on the limiting temperature for the ESV piping). The current outside air temperature vill not be $33*F for any significant period of time prior to September 15, 1986.
II. No. See I above. A more severe environmental condition is not created in the ESV Building provided the outside air temperature is greater than 33*F.
III. No. The 1H32 System vill provide adequate cooling to the ESV Building and its associated equipment.
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                                             - 144 -
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i SE No.:     86-287                                                                                                                   W Source Document:         HFI to 1H43                                                                                                 j
[
Description of Change                                                                                                                  j 1
Evaluation of removal of the hydromotor to the 1M43 (Diesel Generator
          -Building Ventilation System) outside air damper to allow damper to be                                                          i manually open. The hydromotor is to be replaced or repaired prior to September 15, 1986.                                                                                                          .
Summary 1
I. No. The probability of occurrence or the consegeences of an accident are not increased in the Division I and Division II rooms unless both fans are operating at design flovrate providing 100% outside air at a temperature less than 30 F.
In the event of a fire, the C0,3 system vill initiatc dumping CO2                                                       l into the room. The fan vill still trip, but the outside air supply damper vill not close with this MFI. This is not viewed as a problem, since the CO vill be dumped into the room and the fire                                                         ,
vill be extinguished.2 The stay time of the CO2 vill be reduced                                                         i sligh t'ly . The CO2 system vill be supplemented by a fire watch.
j Vith the system shutdown and the outside air damper open, the diesel oil heater and jacket water heater vill be able to maintain the diesel engine temperature.
II. No. A more severe environmental condition is not created in the                                                            '
Division I and II rooms unless both fans are operating at design flov and the outside air temperature is less than 30'F. Based on histor.c outside air temperatures, the current outside air temperature vill not be less than or equal to 33*F for any significant period of time prior to September 15, 1986.                                                                !
III. No. The 1H43 System vill provide adequate cooling to the diesel generator,                                                                                                             f l
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SE No.:   86-288 Source Document:     HFI to IM43 Description of Change Evaluation of removal of the hydromotor to the IM43 (Diesel Generator Building Ventilation System) recirculation damper to allow the recirculation damper to be manually closed. The hydromotor is to be replaced or repaired prior to September 15, 1986.
Summary I. No. The probability of occurrence or consequences of an accident are not 1 increased. The recirculation dampers vill be blocked closed and outside air dampers blocked open therefore providing inlet air to the fan. Based on historic outside air temperatures the current outside air temperature vill not be less than or equal to 33*F for any significant period of time prior to September 15, 1986.
II. No. Vith the recirculation dampers manually closed, it does not result in a more severe environmental condition unless the outside air temperature is less than 30*F and both fans operating are at design flov in either the Division I or Division II rooms.
III. No. The 1H43 System vill provide adequate cooling to the diesel generator.
                                         - 146 -

l SE No.:                       86-289 Source Document:                         STI-B33 029B, Rev. 2
: Description of Change This safety evaluation was performed to evaluate a difference between STI-B21-029B, Rev. 2, Recirculation Flow Control and the FSAR Section 14.2.12.2.26.2 and Table 14.2-2, Startup Tests.                          !
FSAR Section 14.2.12.2.26.2 states that the Startup Test Instruction is performed along the 100% rod line. The STI has been changed to perform testing along the bounding licensed load line.
FSAR Table 14.2-2 states that the Startup Test Instruction is performed in Test' Condition 3 and 6. The STI has been changed to perform testing in Test conditions 3, 6, and 8.                                          l l
Test Conditions 7 and 8 vere added to FSAR Figure 14.2-2 to reflect additional testing along the licensed load line at low and high flow conditions (see PY-CEI/0IE-0231 L, dated August 28, 1986).               ,
1 SSER 8 Section 15.1 approved operation in this extended operating domain for plant startup testing.
Summary I. No. Operations in the HEOD region have been analyzed in Chapter 15, of the FSAR.
II. No.        See I above.
   -III. No.                    The effect of MEOD operation is covered in the plant Technical Specifications.
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SE No.:     86-290                                                                          1 Source Documenti        LL&J 16-405 i
Description of Change Evaluation of Listed, Lead and Jumper (LL&J) to be installed to give the operator / control room the capability to reset.the turbine after a trip.
Summary I. No. The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in             )
the FSAR is not increased.                                                       l l
f II. No.. The LL&J does not create an accident or malfunction of a different
               . type than evaluated previously in the FSAR.                                   1 III. No. This is not defined or described'in Technical Specifications.                  l SE No.:      86-292 Source Document:         DCN 01112 i
Description of Change Drawing change to show the addition of temperature controller on constant           ,
temperature bath (D-302-772)' in the Reactor Plant Sampling System.                l Summary                                                                                   !
I. No. The temperature controller maintains the temperature in a water bath           ,
to cool' samples. The sampling system is not required for prevention of an accident.
II. No. The temperature controller is a secondary piece of equipment to the            i Reactor Plant Sampling System.
i III. No. The temperature controller is not in the Technical Specifications.
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SE No.:     86-293
                                                                                                              -j
    - Source Document:         DCP 85-819B, Rev. 0 Description of Change Design change to-allow for additional trimming of jet. shield ABIC5H7 to allow for pipe movements (RCIC System).
Summary                                                                                                  l I. No. Trimming of the jet ' shield vill not impair the structural integrity or function of the jet shield as described in the FSAR.
II. No. The jet shield is adequate.to shield the postulated jet.
III. No. See I above. The Technical Specifications are not affected.
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J SE No.:             86-294 Source Document:               NR MMOS - 1372, Rev. 1 Description of Change Evaluation of the addition of sealant and sealant band to the Reactor Vater Cleanup (G33) heat exchanger to stop leakage at mechanical joint.
This band is a temporary clamp which vill be removed later.
Summary I. No.           The sealant band as designed and built to the requirements of ASME     l
                                                                &                Section VIII is only a temporary pressure retaining device for the     l II.                approved sealant. This temporary sealant band does not have to meet original ASME Section III requirement and installation as design       ,
vould not affect the ability to safely shutdown the reactor.      A GE l evaluation indicated that the band has no affect on the operability of the RVCU heat exchangers.
GE has evaluated the fiber and sealant compound which vill be utilized to seal the G33 heat exchanger. They conclude that as a temporary leak sealant, this fix vill not cause any degradation to
                                                                                 .BVR material, nor cause unacceptable changes in the reactor chemistry. GE also evaluated the possibility of the sealant compound becoming loose from the heat exchanger and migrating into the RPV. Their conclusion is that a mechanical blockage or interference within the reactor vould not affect the ability to safely shutdown the reactor. Steps to prevent entry into the RPV shall include a flush to the condenser following each sealant injection and subsequent heat exchanger pressurization.
The possibility of a failure of the flange is not increased, nor is the consequence of a failure of the flange made vorse by the addition of this collar. Since the installation of the collar does not modify the existing flange, there is no new failure mechanism from this installation.
III. No.            The margin of safety is not reduced by the injection of the sealant into the RPV, nor is water chemistry affected by this compound.
                                                                                                               - 150 -
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l SE No.:                      86-295 Source Document:                        DCP 86-0729, Rev. O Description of Change Design change to allow for a revision of the electronics internal to 1N64N012A/B (Off-Gas System Hydrogen Analyzers).
Summary I. No.           The change to the hydrogen analyzer electronics vill not affect the analyzer setpoint, which is what trips on a certain amount of hydrogen in the system. The change consists of replacing some fixed resistors with potentiometers to vary the amount of resistance in the circuit. This vill increase the gain of the analyser, which in turn prolongs the life of the analyzer cells. The change does not affect system response time or accuracy. Tre design change vill increase equipment reliability, it vill not increase the probability of an accident described in Chapter 15 of t}e FSAR.
II. No.               The change to the analyzer vill not change the manner in which it operates.
III. No.                    The analyzer setpoints are not changed ar d toe new design vill make the analyzer more reliable.
SE No.:                    86-296 Source Document:                        DCN 1101 Description of Change Drawing change to show the addition of digital indicator 1B21R723 to P&ID 302-606. This changes the Nuclear Boiler Configuration P&ID in FSAR Figure 5.1.3.
sg ., g I. No.          The item to be evaluated is a change to a drawing found in the FSAR to reflect actual field conditions and does not change equipment.
The digital indicator is designated nonsafety and is not discussed in the FSAR.
II. No.              See I above.
III. No.                   The digital indicator is not described in the Technical Specifications.                                                     I 1
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b SE No.'s            86-297 DCN 0871                                                   l Source Decument:
Description of Change Drawing change to show fire damper MPL No. changes to D912-609 for existing fire dampers.                 Editorial change only, i
Summary I, No.       This change involves MPL Number changes only.
II. No.        See I above.
See I above.                                                              (
III. No.                                                                                      l l
F SE No.:             86-298 Source Document:                     DCP 85-0094, Rev. 0
                     ' Description of Change                                                                              l Design change to allow the installation of coordinated fuses in the control circuit of vent fan 1M28-B001A (Emergency Pump Area Cooling System).
Summary I. No.            The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR is not increased.                                        1 II. No.             The possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR is not created.
III. No.              The margin of safety as defined in the bases for any Techr.ical Specification is not reduced.
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SE No.1                86-299                                                                  l Source Document:                         STI-B21-027,-1.<v. 2                   3
                                                                                                                                  )
I Description of Change                                                                          i I
                                                    .This safety evaluation was performed to evaluate the performance of the       l Turbine Trip and Generator Load Rejection Tests with the core flow greater.than 100% of rated.
Figure 14m 2-4, Test Condition 6 was extended to maximum core flow to reflect tne extended operating domain.                                       j l
SSER 8 Section 15.1 approved operation in this extended operating domain for plant startup testing.                                                  ;
4 Summary i
: 1. No. 'Per Appendix 15E of the FSAR, all of the above have been evaluated and shown to have not increased.
II. No.            Since only core flov is being changed, no different accident or malfunction is being created.
III. No.               Per Appendix 15E of the FSAR, the margin of safety is not being reduced.
SE No.:               86-300                                                               i Source Docum.ent:                       DCP 85-067C, Rev. 3 Description of Change i
Evaluation of struct'ral interface for Hilti bolt installation and         !
seismic clearance violations for oil analysis lab piping and supports. i This is pertaining to the design change to install piping for the various utilities needed in the oil analysis lab (599' elevation of the Control Comnlex).
Summary I. No.         Hilti bolts installed, do not impair the structural integrity of the concrete. Also, no seismic clearance violations are created by this change.                                                              i I
II. No.            See I above.                                                            I III. No.              There is no affect on the Technical Specifications.                  3 l
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'SB No.:     86-301.
Source Document:        DCP 86-742, Rev. O Description of Change                                                                                  l
                                                                                                      .i l
Genign change to allow for the addition of polyethylene foam insulation to tis Chilled Vater System (P50) flanges / valves and miscellaneous items in containment. (Pire Protection Evaluation)
Summary I. No. The increase in combustible loading is approximately 1% for the total area. This increase vill not impact the overall fire protection adequacy for the area.                                                         ;
II. No. The material does not increase the probability of a fire occurring.                     -j The type of material is similar to other combustibles in the area.-                       !
III, No. The change vill not impact the overall program as described in                            !
Technical Specifications.
l SE No.:     86-302 Source Document:       'DCP 86-742, Rev. O Description of Change Desiga change to allow for the addition of additional polyethylene foam                         l insulation to provide antisveat coverage of valves and flanges on the                           !
Containment Vessel Chilled Vater System in containment.     (Mechanical Evaluation)
Summary I. No. No potential plugging of ECCS suction can occur when this                                ,
polyethylene foam material is added in containment. Contact cement has non-leakable chlorides.
II. No. Material is stable above maximum post LOCA temperature. Is light enough to have no damage potential if falling. Is above zone where it can be associated with pool swell loads.
III. No. Antisveat insulation applications are not a part of Technical Specifications.
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                   ,               SE No.'s' 86-303'-
Source Document:      DCN 1112-1 Description of Change Drawing change to allow for the addition af temperature controller on constant temperature bath (D302-772).
Summary i
I. No. The temperature controller maintains the temperature in a vater bath J to cool samples. The sampling systen is not required for accident      j prevention.                                                            l l
1 II. No. See I above.
III. No. The temperature controller is not mentioned .n the Technical         i Specifications.
SE No.:     86-304 Source Document:       DCN 01188
           \
Description of Change Draving change to allov for correction of alc flow pattern shown on HVAC System Diagram (D912-622, Hydrogen Analyzer Rooms).
Summary I   No. The Off-Gas Building Exhaust System (M36) function has not changed.
The airflow pattern is being revised to reflect existing building room designations.
II. No. See I above.
III. No. System requirements are being met as originally specified.
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   ,                               SE No.:            86-306                      .
                                  - Source Document:                DCN 1033
                                                                                                                              ]
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                                  - Description of Change                                                                     1
                                                . Drawing change to allow for revision of system diagrams '(D302-121,.         ,
D302-613, D914-005) for inclusion of as-built ERIS points configuration.      l (Hechanical Evaluation)
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                                   ~
Summary                                                                                    1 I . No .. As-built ERIS points on system P&ID's do not effect consequences of
                                                          ~
I an accident or malfunction important to safety.                          l l
II. No. See I above.
III. No.          The~ revision of system diagrams for as-built ERIS point configuration does not reduce the margin of safety as given in the bases of the Technical Specifications.
                                                                                                                             ]
SE No.:          86-307                                                                !
Source Document:               DCN 1033'                                                j Description of Change Drawing change to allov for revision of system diagrams (D302-121, D302-613, D914-005) for inclusion of as-built ERIS points configuration.   .
(Electrical-Evaluation)
Summary                                                                                :
I. No. ERIS points monitor the status of various valves and hence makes the  '
overall system more reliable and safe. This is a drawing update only.                                                                 !
II. No. See I above.
III. No.        This change does not affect Technical Specifications.                 ;
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P L                             SE No.:     86-308 l                             Source Document:       DCP 86-729, Rev.'l
                                                                                                                                                      ]
Description of Change l                                   Design change to allow for a revision of the electronic      .ternals to                                           <
1N64N012A/B (Off-Gas System Hydrogen Analyzers). This change is required to in rease the gain of the electronics output to extend the life of the                                           ;
cells by replacing some resistors with higher resistance potentiometers and resistors.
Summary                                                                                                             '
I. No. The change to the hydrogen analyzer electronics vill not affect the analyzer setpoint, which is what trips on a certain amount of                                              .l
                                         . hydrogen in the system. This revision vill prevent the gain of the analyzer from being too excessive, yet keeps the gain at its correct value. The change does not affect system' response time or accuracy.
The design change vill increase equipment reliability, it vill not                                           ;
increase the probability of an accident as described in chapter 15                                           '
of the FSAR.i II. No. The change to the analyzer vill not change the manner in which it operates,                                                                                                    j III. No. The analyzer setpoints are not changed and the new design vill make ,
the analyzer more reliable.
t SE No.:     86-309 Source Document:       DCP 86-434, Rev. O                                                                                !
Description of Change Design change to allow for the installation of exhaust ductwork for the                                              l respirator dryer oven in the hot laundry and mask cleaning room. This                                               j change connects the respirator dryer vent with the Control Complex Ventilation System.
Summar; l
I.'No. The installation is for a dryer which was exhausting into the room                                             l and is now being exhausted directly through the filter system.                                                 l II..No. The ductwork is being installed to exhaust air from a dryer which could potentially become contaminated.
III. No. No increase in plant gaseous effluent vill result.
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SE No.:            86-310 Source Document:              DCP 86-0338, Rev. O                                        j J
Descrip' tion of Change Design ~ change to allow for the addition of a flow control valve and flow. ,
meter for the Condensate Demineralized System (N24) anion' regeneration     l tank.
Summary I. No.          The N24 System serves no function during any accident as evaluated in the FSAR.
II. No.          The N24 System serves no safety function.
III. No.           N24 is not a part of Technical Specifications.
J ESE No.:            86-311 Source Documents'             DCP 86-338, Rev. O Description of Change Design change to allow for the addition of instrumentecion to support the anion backvash flow control valve installation.
Summary                                                                                 ,
                                                                                                         \
d I. No.       The Condensate Demineraliter System serves no function in an accident as described in the FSAR.
1 II. No.          The Condensate-Demineralized System serves no safety function.       q III. No.           The condensate Demineralized System is not a part of Technical       l Specifications. Overall Condensate Demineralized System operation    i has not changed.
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SR No.:    86-312 Source Document:       DCP 85-148, Rev. O Description of Change Design change to allow for the addition of temperature switches to stop fan, and stop airflow to allow fire dampers to close.      (Miscellaneous Ventilation Systems).
Summary I. No. The' fans which. vill trip on receipt of high temperature are nonsafety-related.
II. No. The addition of tems.orature switches and fan interlocks vill not create the possibility for an accident of a nature other than what is evaluated in the FSAR.                                            _l III. No. The system involved is not covered in the Technical Specifications.   ,
SE No.:    86-313 Source Document:        LLJED to lE12 Description of Change Evaluation of the installation of LLJED (Lifted Lead, Jumper, and Electrical Device) to defeat bypass and inop annunciator logic for valves 1E12-F037A&B (RHR A&B upper pool cooling isolation), which are deenergized in compliance with Technical Specification 3.6.4 action           -
statement.
Summary I. No. Annunciator lights are not considered equipment important to safety,      '
therefore, changing annunciator light logic does not impact mitigation of an accident as described in the FSAR. This is due to the fact that accident analysis in the FSAR does not take credit for      l annunciator logic for accident mitigation. The consequences of an accident vill not be increased because single active failure criteria is not violated, and there is no increase in the common mode of failure.
                                                                                                           )
1 II. No. The logic change does not create a scenario whereby a new category of initiating disturbances would be created that would lead to unevaluated malfunctions or accidents.
III. No. This change vill not impact safety limits as defined in the
(                                Technical Specifications.
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l SE No.:         86-314 Source Document:           .DCP 86-666, Rev. 0
            , Description of Change                                                                   b l
Design change to allow for differential pressure control for containment /dryvell supply fan (Containment Vessel and Dryvell Purge           i System). (Mechanical Evaluation)                                                 j
                                                                                                       \
J Summary                                                                                  l I. No.      The present containment /dryvell supply and exhaust fan control configurations measure fan flov (CFM). Each control system compares actual fan flow with a preset value and automatically adjusts the fan's variable inlet vanes, such that each fan volume matches its     i preset value. This control logic is unsatisfactory because hysteresis and dead band (inherent in the equipment) prevent supply   .
and exhaust fan volumes from matching exactly. This mismatch results in differential pressure across the containment due to flow mismatch.
This design change shifts the control logic from volume control to pressure control... containment pressure is sensed and is used to control supply fan volume to maintain containment pressure within a preset' range.
The probability of a control system failure of the new proposed design is no greater than the probability of a control system         i failure of the present design in use nov. This is because equipment of the same quality and design is proposed to be installed for the design change as that which is presently installed. The consequence of an accident or malfunction is not increased because the affect of control system failure in either design is exactly the same...
failure of the fans to deliver the proper volume of air. The failure / malfunction vill result in a differential pressure across the containment or dryvell vall which may result in containment (or  i i
dryvell) vacuum breaker operation. Two worst case failures were analyzed for this design change as follows:
: 1) Complete failure of the supply fan (no supply flow) with exhaust fan at maximum volume. This configuration vill produce a vacuum in containment. Containment to outside differential pressure could reach 0.40 psid if the vacuum breakers are assumed not to open. This pressure is not sufficient to challenge the .8 psig negative design pressure of the containment building.
: 2) Complete failure of exhaust fan (no exhaust flow) with supply fan at maximum volume. This configuration results in a l
                                       +.21 ps! differential between containment and outside.
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                             ' SE No. :        86-314 (Continued)
Both of the vorst case failures listed above fall within the envelope of accident conditions that the FSAR uses for accident response analysis in the containment functional evaluation (FSAR 6.2.1.1.3.3), and Mark III containment system issues (Humphrey issue 8.4, 10.2 6 20). Therefore, the consequence of an accident or malfunction previously evaluated in the FSAR is not increased by this design change.
II. No. As stated'in Item I, consequences of gross failure of the new design is the same as the old design and vill result in containment or dryvell vacuum breaker (CVB) operation. However, the new design vill prevent numerous inadvertent opening of CVB's during normal       1 operation of the H14 vent and purge system, by controlling and           !
maintaining containment pressure negative, but belov CVB opening set point. Therefore, the possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR is not created.
III. No. Opening of the containment and dryvell vacuum breakers have been      R  '
evaluated and addressed in Technical Specification Section 3.6.5.1 and 3.6.5.3 (pages 3/4 6-42 6-3/4 6-46). Failure of the differential pressure control does not reduce the margin of safety specified by the Technical Specification because a worst case failure:of the fan control system as discussed in items I 6 II above does not approach the margin of safety established by the envelope     l of accident conditions discussed in the FSAR.
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t SE No.:             86-315 Source Documents             s .DCP 86-666, Rev. O                                         i Description of Change Design change to allow for differen'tlal pressure control for the Containment /Dryvell Purge System (M14).      (I&C Evaluation)
Summary I No. With the exception of one (1) safety-related Instrument Isolation Valve (1D23F060) in the D23 - Containment Atmosphere Monitoring System, this design change addresses the control of nonsafety
                                           -related equipment and has no affect on the safety analysis evaluated in the FSAR. The instrument isolation valve has been designed, procured, and installed meeting all code, seismic, and installation   ;
requirements specified for this installation.
II. No. a. M14 - Containment /Dryvell Purge Failure of the differential pressure control vill affect nly the non-safety related equipment and vill not result in an accident or malfunction of a different type than any evaluated previously in the FSAR. The safety-related (M14) isolation
                                                 -dampers vill function as designed,
: b.   ~D23 - Containment Atmosphere Monitoring Failure of the instrument impulse.line from Valve 1D23F060 and/or differential Pressure Transmitter 1M14N223 vill cause one (1) channel only of the accident monitoring instrumentation to be lost temporarily. This channel monitors primary containment pressure only and does not perform an ESF control      j function. Failure of this channel vill not result in an         i accident or malfunction of a different type than any evaluation   j previously in the FSAR.                                           I 1
III. No.          Based on the analysis provided in Item II above, the margin of safety as described in the Technical Specifications vill not be compromised.
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l SE No.:    86-316 Source Document:      DCP 86-666, Rev. 0
   . Description of Change                                                                            !
Evaluation of the installation of Hilti bolts into safety related
,        concrete and the velding of supports to safety-related embedded plates.
l'       Pertains to the design change to allow for differential pressure control l        for the' Containment /Dryvell Purge System.    (Civil / Structural Evaluation)
Summary i
I. No. Hilti bolts.are designed such that they do not impalc the structural integrity of the vall. Velding to the embedded plates does not impair the vall, since the loads are minimal when compared to the allovable design loads for the embedded plates,                                         j II. No. See I above.                                                                           j l
,   III. No. See I above. Does not affact the Technical Specifications.
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l SE No.:     86-317 Source Document:       DCP 86-604, Rev. O Description of Change
                                                                                                      ]
i Design change to replace Pressure Transmitters 1E12N058A, B & C (Residual                     {
Heat Removal System) circuit boards with boards resistant to harsh environment radiation.
l Summary                                                                                           J l
l     I  No. The circuit board replacement of the transmitter improves the accuracy response of the trancmit ters which vill not produce any consequential effect to safety previously evaluated in the FSAR.
II. No. See I above.
l l   III. No. All design functions required for the transmitters are unaltered.
The setpoint remains the same.                                                         I i
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l SE No.:         86-318 Source Document:           SXI-0001, Rev. 0 l
Description of Change                                                                                      l Evaluation of a special test to perform functional protective relay trip                           f tests on the main generator relays, the generator'startup transformer                           .j relays, the unit auxiliary transformer relays, and the S-3-PY-BUS and                              l S-610 breaker and S-611 breaker protective relays, to. verify that the                           j tripping action of these relays are as designed. This test vill be                                {
performed one time only and will be performed before initial energization of the main generator.
Summary I. No. This testing proves design features of the plant. No abnormal alignments are involved.
II. No.-      The plant operates per design during test.
III. No.         The plant operates per design during test.
SE No.:         86-319 Source Document:           DCP 85-0067E, Rev. O Description of Change                                                                                   i Design change to install exhaust ductvork for fume hoods in oil analysis
                 . lab.    (Mechanical Evaluation)
Summary I. No. The installation is for an office which is being converted to a lab.
II. No.       The ductwork is being installed to exhaust fumes from potentially contaminated oils to be examined in the newly installed lab. Since there are no increases in plant significant gaseous effluent as a result of this change, there are no new accidents or malfunctions created.
III. No.        The margin of safety as defined in the Technical Specifications is not changed by this modification.
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SE No.:    86-320 Source Document:      DCP 85-0067E, Rev. O e         -
1 Description of Change-Evaluation of the installation of Hilti bolts in safety-related concrete.
Pertains to the design change to install exhaust duct ork'for fume hoods in the oil analysis lab.
(Civil / Structural Evaluation)
                                                                                               )
Summary
                                                                                              ]
i I. No. Hilti bolts are designed such that they do not impair the structural     i integrity of the building.                                               ]
II. No. See I above.                                                             l III. No. The installation of Hilti bolts does not affect the Technical Specifications.
SE No.:    86-321 Source Document:      Setpoint Calc. G43-C04, Rev. 1 Description of Change                                                               l Evaluation of setpoint calculation G43-C04 (Suppression Pool Hakeup System) change of the Leave-As-Is-Zones of 1G43-07001 and 1G43-07002 setpoints from +/-S seconds.to +/-30 seconds.
Summary I. No. The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety is not increased.           l II. No. The maximum timer setting of 29.9 minutos (29.4 minutes plus 30 seconds) does not exceed the 30 minute time delay setting described in Section 6.2.7 of the PSAR.
III. No. The timer setting of 29.4 minutes +/-30 seconds does not conflict with the Technical Specification allovable value of f30.0 minutes.
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r SE No.:         86-322
                    . Source Document:           DCP 86-736, Rev. 0                                                               ]
Description of Change Design change to allow for the l' installation of Pressure Switches 1R43N086A&B (Standby Diesel Generator), to add manual start and bus                                    i undervoltage start signals to-the " Emergency Start Signal Received" Annunciator. (Mechanical Evaluation)
Summary                                                                                                      j I. No.      The original design parameters for the qualified design have been maintained for this installation.                                                            ]
l II. No.      See I above. No new type of item or design has been introduced to                              l create an accident or malfunction of a different type.
III. No. .The Technical Specifications are unaffected.
SE No.:        86-323 Source Document ~          DCP 86-736, Rev. 0
                     ' Description of Change Design change to allov for the addition of the manual and undervoltage initiation signals to the Division 1 " Diesel Generator Auto' Start Received" Annunciators. (Electrical Evaluation) 1 Summary                                                                                                    ]
I. No.      This control circuitry is non-safety related and is isolated from the safety-related diesel generator control circuitry.                                     ;
I II. No.      See I above.
III. No.       The Diesel Generator Auto Start Received Annunciators are not described in the Technical Specifications.                                                    l I
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                                       .SE'No.      86-324                                                                 '
                                       . Source Document:       DCP 86-736, Rev. 0 l:
Description of Change Design change to allov for the installation of Pressure Switches             ]
1R43-N086A&B (Standby Diesel Generator) into Panels 1H51-P054A&B             1 respectively.
l                                                               (I&C Evaluation)
Summary                                                                           f I. No. The design change is consistent with the original panel design and.
fabrication requirements, plus the " Diesel Generator Auto Start Received" control circuitry is nonsafety related.
II. No. The design and. installation of the switches and their associated tubing is to-be done safety related to ensure their functionability as a pressure boundary device.
III. No. This instrumentation is not described in the Technical Specifications.
SE No.:     86-325 Source Document:        DCP 86-813, Rev. 0 i
Description of Change Design change to allow for the r alacement of current lE51K65 and 1E51K85.
(Reactor Core Isolation Cooling System) relays with time delay relays to account for oscillation in the signal of the Leak Detection Transmitters   j I
(E31-N084A & B).                                                           i Summary I. No. GE has verified that a nominal time delay of 3 seconds is bounded by their analysis in NEDE-24953 (NUREG 0737, Item II K.3.15).           l II. No. See I above.
Technical Specifications do not address the functional isolation     j III. No.
time requirements for RCIC isolation valves affected by the relay circuits.
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                               .SE No.: .86-326 Source Document:       DCP 86-0541, Rev. 1
                           . Description of Change
{
i Design change to allow for the installation of an eight inch Fire Protection System line frem the existing Fire Protection System Fire Main to fire training area to provide two new fire hydrants. Valves exist to provide adequate isolation for the plant.
Summary.
I. No. Vill not affect, hinder, malfunction or cause an accident important    l to safety. Does not affect safe shutdown.                           j i
II. No. There are no potential initiating causes of threats to the plant.      1 III. No. Only administrative aspects of fire protection are in Technical Specifications.
l SE No.:    86-327 Source Document:       DCP 86-0785, Rev. O Description of Change                                                             !
I Design change to allow for the deletion of the turbine trip and closure      !
signal to the motor operated extraction steam valves.
Summary I. No. Implementing this design change vill not increase the probability      !
and consequences of the loss of feedvater heating or other Chapter 15 transients / accidents.
II. No. This change does not create a potential accident different than already evaluated in the FSAR. The Perry design complies with ASME Standard TVDPS-1.                                                      j t
III. No. The margin of safety for fuel clad and turbine overspeed are not reduced, t
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SE No.:                        86-328 Source Document:                                                 DCP 86-224A, Rev. O Description of Change Evaluation of the installation of Hilti bolts into safety-related concrete for Emergency Service '*ater N oe Supports.
Summary I. No.                        Hilti Kvik bolts do not impair the integrity of structural concrete.
II. No.                          See I above.
III. No.                          The installation of Hilti Kvik bolts does not affect Technical Specifications, i
SE No.:                             86-330                                                                                                                                                                   '
Source Document:                                                 SXI-0004 Description of Change l
Evaluation of a Special Test Instruction for the Liquid Radvaste Disposal                                                                                                                            l System on the Evaporator Feed Strainer Initial Start Test.
Summary I. No.                           The performance of this special test does not increase the                                                                                                              i probability of a radioactive liquid release. This is a one time only test.
II. No.                             This test does not change any design configuration.
III. No.                              The performance of this test does not affect any liquid radvasto discharges.
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1 SE No.:   86-331 Source Document:      NR HMOS 1390, Rev. O Description of Change Evaluation of setpoints of various protective devices which may not conform to the. requirements as specified per FSAR Q&R 430.80 and the setpoint changes needed to bring the settings in compliance with FSAR Q&R 430.80.
l                    Summary I. No. The present settings for'the protective dev. ices protecting the 5kV safety motor loads vill aa. low for proper accident response and the new settings for these protective devices vill bring their settings
: l.                             in compliance with FSAR O&R 430.80.
II. No. The loss of a single divisional safety bus is analyzed in the FSAR, Section 15.6.5 and 15.6.6.
III. No. The setpoint values for .these protective relays are not described in the Technical Specifications.
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l SE No.:   86-332 Source Document:      NR MMOS 1391, Rev. O Description of Change Evaluation of setpoints of various protective devices which may not conform to the requirements as specified per FSAR Q&R 430.80 and the        ,
setpoint changes needed to bring the settings in compliance vith FSAR Q&R   '
l                         430.80.
Summary I. No. The present setting for the 480V safety motor protective devices will allow for proper accident response and the new settings for these protective devices vill bring their settings in compliance with FSAR 0&R 430.80.
II. No. With the present setpoint values, the motors will be capable of l
responding to an accident and these settings vill selectively I
coordinate with upstream protective devices.
1 III. No. The setpoint values for these protective devices are not described in the Technical Specifications.
                                                            - 170 -

i L             SE No.:      86-333 Source Document:        DCP 86-719, Rev. O                                           !
l Description of Change                                                                f J
Design change to allov for the addition of voltage regulators for the         '
alternate feeds to'the RPS electrical protection assemblies _(EPA's).
(Electrical Evaluation) k Summary I. No. Improves performance of system.
II. No. See I above.
III. No. The margin of safety is not reduced.
SE No.:       86-334 Source Document:        DCP 86-719, Rev. O i
Description of Change Evaluation of the installation of Hilti bolts in safety-related concrete in the Control Complex. Pertains to the design change to allow for the-addition of voltage regulators for the alternate feeds to the RPS          l electrical protection assemblies. (Civil / Structural Evaluation)
Summary I. No. Hilti bolts do not' impair the integrity of the structural concrete.
II. No. See I above.
III. No. Hilti bolts do not affect the Technical Specifications.
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SE No.:        86-335 Source Document:           DCP 86-740, Rev. O Description of Change Design change to allow for the replacement of Unit II, Division III battery charger circuit breaker (50A) and tie (Maintenance) circuit breaker (50A) with three-pole, 100A circuit breakers due to 50A breakers tripping on any branch fault or high load in a rush situation.
Summary I. No.       The proposed change vould change the circuit breakers of the
           &            Division 3 maintenance tie bus from 50 amp to 100 amp. This change, II.           which is to be performed on the Unit 2 side only,' is already in place on the Unit 1 side.
III. No.       This change does not result in a change to the Technical Specifications. The Technical Specification change, to take credit for the Unit 2 batteries in place of the Unit 1 batteries to meet the LCO, was submitted to the NRC under {{letter dated|date=July 18, 1986|text=letter dated July 18, 1986}} (PY-CEI/NRR-0496 L). The proposed Technical Specification change was found acceptable by the staff, as documentedLby Section 16.2.15 of SSER 10.
SE No.:        86-336 Source Document:           LL & J #16-684 u
Description of Change I
Evaluation'of Lifted Lead and Jumper to remove the interlock between the (Temporary Modification) Condensate Filter System (N23) and the Liquid Radvaste System (G50).
l Summary I. No.       The interlock is a backup to level indications from the Radvaste Control Room. The Radvaste Control Room is reading a true signal and can accurately assist the N23 operator.
II. No.        See I above.
III. No.        The interlock on the G50 receiving tank does not have any connection with plant liquid effluent discharges.
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SE No.:       86-337 Source Document:                   HFI 16-683 Description of Change Evaluation of griffolyn plastic to shield the Control Rod Drive (C11)
System Transponders / Reactor Plant Sampling Panel from the Containment Vessel Chilled Vater / Containment Vessel Cooling "Sveating" on pipes and dropping on components.
i Summary l
The griffolyn plastic that vill be used to shield the C11 System I. No.
Transponders / Reactor Plant Sampling Panel vill be secured and tied down in containment, such that it vill not become dislodged due to seismic events. Griffolyn plastic is flame retardant and vill produce no detrimental residues on decomposition.
II. No. See I above. The griffolyn plastic vill be installed above the maximum solid water impact and maximum froth impact.
III. No.      The griffolyn vill be sufficiently tied down and monitored.
SE No.:       86-338 Source Document:                   DCP 86-804D, Rev. O Description of Change Design change to allow for the installation of a core drill for the relocation of Reactor Vater Cleanup flow transmitters (lE31-FT-N075A and 1E31-FT-N075B) for leak detection. These transmitters monitor main condenser dump line flow. (I&C Evaluation)
Summary I. No.      Isolation signals to the containment isolation valves are not affected.
II. No.      The possibility for an accident or malfunction different than those already evaluated in the FSAR is not increased.
III. No.      The system functionability has not changed.
                                                     - 173 -

ia SE No.:         86-339 Source Document:           DCP 86-804D, Rev. O Description of Change Design change to allov for a three inch core drill to be installed to allow for the relocation of the RVCU flow transmitters from their present location in the Auxiliary Building to inside of containment.
(Civil / Structural Evaluation)
Summary I. No. This core drill is being installed through a construction boxout that was grouted after the installation of a remote valve operator.
II. No. The integrity of the vall is not compromised.
III. No.        This core drill does not af fect the margin of safety in the                                                      l Technical Specifications.                                                                                       1 1 1
1 SE No.:         86-340 Source Document:            DCP 86-498, Rev 0                                                                                   '
Description of Change Evaluation of structural interface for addition of aluminum cap to                                                   ;
Auxiliary Building roof parapet. Cap is necessary to provide a ground                                                '
reference for proper E-Field operation.
Summary J
I. No. Drilling shallow, small diameter holes into a concrete vall vill not affect the ability of the vall to adequately support the required design loads.
II. No.      See I above.
III. No.         See I above.
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SE No. 341 Source Document:-                     DCP 86-804B, Rev. O l
Description of Change-L                          Design change to allow for the electrical installation of cable, conduit,   j terminaticus and viring changes for the relocation of Reactor Vater       _{
Cleanup flow transmitters (lE31-FT-N075A and lE31-FT-N075B) for leak        j deteetion. These transmitters monitor main condenser dump line flov.        ;
(I6C' Evaluation) 1 Summary                                                                                          !
t I.~No.                  Isolation signals to the containment isolation valves are not affected.                                                             }
I II. No.                   The possibility for an accident or malfunction different than those .l already evaluated _in the FSAR is not increased.
III. No.                   The system functionability has not changed.
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l SE No.:                    86-342                                                                i Source Document:                      DCP 86-804B, Rev. O                                        ;
i-    Description of Change                                                                            t I
Evaluation of the installation of Hilti bolts in safety-related concrete    l and the attachment of Nelson studs to the containment vessel. Pertains      l to the design change to relocate the RVCU flov transmitters for leak        l detection. (Civil / Structural Evaluation)                                  l Summary I. No.                  The installation of Hilti bolts does not impair the concrete          I structure. The studs apply less than the design tensile load to the   <
containment vessel.
II. No.                   The Hilti bolts and Nelson studs do not create the possibility for an accident or malfunction of a different type than previously evaluated.                                                            i III. No.                   The installation of Hilti bolts in safety-related concrete and the    ;
attachment of studs to the containment vessel do not affect the       t Technical Specifications.
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1 SE No.:               86-343 Source Document:                  DCN 0111 Description of Change                                                                                                          !
I Drawing change to allow for the deletion of note #7 on drawing number                                        )
l D302-739 to reflect as-built conditions.
Summary I.'No.      The conductivity recorders have no relation to equipment important to safety,                                                                                            t II. No.          No accident or malfunction can exist if the conductivity recorders                                     j operate continuously.
III. No.             The margin of safety in the Technical Specifications are not reduced                                  l by having a conductivity recorder that operates continuously.                                         l SE No.:. 86-344                                                                                                           :
Source Document:                 DCP 85-547, Rev. O l
Description of Change Design change to modify fasteners to meet the U-L requirements for the l
bullet resistant firevalls (620'-6" and 638'-6" elevation) in the control complex.                                                                                                   j Summary.                                                                                                                  !
I. No. The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety is not increased.                                        l II. No.        The up-grading of the vall construction vill not cause a threat to                                    !
the fuel and the reactor coolant pressure boundary. Improves fire                                  l resistance capability. Security not compromised.
III. No.           This is not within the scope of the Technical Specification.
                                                                              - 176 -

                                                                                                               .)
1 SE No.:     86-345 Source Document:      DCP 86-804C, Rev. O                                        ;
Description of Change Evaluation of installation of Hilti bolts in safety-related concrete.      f Pertains to design change to provide pipe supports for relocated leak detection transmitter piping.     (Civil / Structural Evaluation)
Summary                                                                          )
I. No. Hilti Kvik bolts do not impair the integrity of structural concrete.
II. No. See I above.                                                         j III..No. The installation of Hilti bolts does not affeet the Technical        !
Specifications.                                                      j SE No.:     86-347 Source Document:      DCP 86-804A, Rev. O Description of Change                                                            l Design change to allow for the moving of Flow Transmitters lE31-FT-N075A and lE31-FT-N075B-(Leak Detection System) from their present location in   t the Auxiliary Building to luside of containment. This change involves     !
the design of a new instrument mounting rack and the routing of           !
lastrument impulse lines.     (I&C Evaluation)
Summary i
I. No. Isolation signals to the containment isolation valves are not affected.                                                            !
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II. No. The possibility for an accident or malfunction different than those already evaluated in the FSAR is not increased.                      i III. No. The system functionability has not changed.
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  - _ _ _ _ _ _ _ _ _ _ _ _ __                                                                                   1

i SE N1.:                 86-348 Source Document:                    DCP 86-804A, Rev. O Description of Change Evaluation of the installation of Hilti bolts in safety-related concrete.
Pertains to design change to allow for the moving of Flow Transmitters
                                        .lE31-PT-N075A and lE31-FT-N075B from their present location in the Auxiliary Building to the inside of containment.                (Civil / Structural Evaluation)
Summary.
I   No. Hilti Kvik bolts do not impair the integrity of the concrete.
II. No. See I above.
III. No.             The' installation of Hilti bolts does not affect the Technical Specifications.
SE No.:            86-349                                                                                             ,
Source Document:              NR PPDN 462, Rev. O Description of Change Evaluation of lov flov at supply register RRB416 in Dryvell Cooling System. Total system flow is within 10% of design value. (See also SE 86-'368)
Summary I. No. Lov flow at this register does not affect the overall system function. Total system flow is still.within the acceptable range.
II. No. See I above.
III. No.       See I above.
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SE No.:        86-350                                                                 I Source Document:           NR PPDN 484, Rev. 0
                            - Description of Change                                                                    j Evaluation of lov supply airflow in branch duct leading to zone AB1 Easc (HVAC Supply Area - Auxiliary Building Ventilation System).
Summary I. No.        Lov airflev in this supply branch with Supply Fan H38-C001B in operation does not affect the overall system function. Total supply system. flow is within the acceptable range.
II. No.        See I above. -Does not affect the qualification of safety-related   .
equipment / instruments in the area.                                _
III. No.        The Technical Specifications addresses only the filtered exhaust      ,
portion of the Auxiliary Building Ventilation System. The exhaust system is not affected by this non-conforming condition. In addition, since there is no affect on the qualification of safety-related equipment / instruments in this area due to this nonconformance, there is no affect on the Technical Specifications.
SE No.:        86-351 Source Document:          NR PPDN-0431 Description of Change Evaluation of the Heater Bay Exhaust System (H41) which could not be balanced to meet both modes (summer /vinter) of operation. One branch of      !
the system is above designed rated flow.
Summary I. No.        An increase in airflow in one branch of the system vill allow the local area to remain cooler. Total system airflow is still.within I                                                                                                                     1 design limits.
II. No.        See I above, l
III. No.        All system requirements are being met or exceeded.                     l l
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8 SE No.:                   86-352
              ~ Source Document:                      DCP 86-644, Rev. 0
* Description of Change i
Evaluation of the installation of Hilti bolts in safety-related concrete.
Pertains to design change to add a metal storage cabinet for nuclear          l instrumentation in the Fuel Handling Building.                                ;
Summary I. No.          Hilti Kvik bolts do not impair the integrity of structural concrete.  --
The storage cabinet supports are designed for seismic loads and the concrete structures are not impaired due to the cabinet loads.
II. No.             See I above.
III. No.                The installation of Hilti bolts and support of the storage cabinet does not affect the Technical Specifications.
SE No.:                86-353 Source Document:                   HFI 16-696 Description of Change Evaluation of the installation of heat tracing on 1E31-N083B (Leak Detection System) instrument impulse line from RCIC elbow tap for system operability enhancement. Based on temporary installation of heat trace being installed up to 5% power and shift rounds by operations personnel on an hourly basis to verify satisfactory channel checks of 1E31-N683A&B and piping temperature not to exceed 575*F.
Summary I. No.         The probability of occurrence of an accident evaluated in the FSAR      j is not increased because the installation of the heat trace does not compromise or reduce the leak detections system's capability to prevent an accident.
II. No.            No new accident is created. The ability of the Leak Detection System to perform its design function of detecting a RCIC steam line break is enhanced.
III. No.              A line break vill still be detected at the required value.
                                                                         - 180 -
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1 SE No.:                                                             86-354' Source Document:                                                               MFI 16-699 Description of Change Evalu~ation of the installation of heat tracing on 1E31-N083A (Leak Detection System) instrument impulse line from RCIC elbow tap for system                             '
operability enhancement.                             Based on temporary installation of heat trace being-installed up to 5% power and shift rounds by operations personnel on an hourly basis to verify satisfactory channel checks of 1E31-N683A&B and piping temperature not to exceed 575 F.                                                          {
Summary                                                                                                                                    j I. No.                                               The probability of occurrence of an a cident evaluated in the FSAR is not increased because the installation of the heat trace does not compronilse or reduce the leak detections system's capability to prevent an accident.
II. No.                                                      No new accident is created.
l III. No.                                                            A line break vill etill be detected at the required value.
SE No.:                                                             86-355 Source Document:                                                               DCP 86-845, Rev. O Description of Change Design change to allow for the addition of local solenoids and pressure regulating valve to attain required closure times for the Extraction Steam System critical non-return check valves.
Summary I. No.                                                This modification is related to the turbine overspeed protection, which is nonsafety related.
II. No.                                                      See I above.
III. No.                                                            The extraction non-return valves are not addressed by the Technical    j Specifications.
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SE No.:    86 356 Source Document:           DCP 85-573C, Rev. O Description of Change Evaluation of the installation of Hilti bolts in safety-related concrete.
Pertains to the design change to allow for lighting, power and redesigning of the existing layout to support the installation of the dry active vaste handling area.
l                                                             Summary I. No. Hilti bolts are designed such that they do not impair the structural integrity of the building.
II. No. See I above.
III. No. The installation of Hilti bolts does not effect the Technical Specifications.
SE No.:        86-357 Source Document:           SXI-0003, Rev. O Description of Chang,e, Evaluation of Main Generator Shoct Circuit Relay Load Special Test to perform and document the initial inservice main generator load checks.
Summar_g                                                                                                                                                                                      ,
I. No.       The generator operates within its design capability during the test.
II. No.         No abnormal plant operational alignment is required.
III. No.         No operation beyond design limits is allowed per this instruction.
                                                                                                                                                     - 182 -

SE No.:     86-359 Source Document:       DCP 86-804, Rev. O                                                            !
Description of Change Design change to allow for.the installation of new flow orifice with pressure taps on orifice flanges upstream of control valve 1G33-F033 (Reactor Vater Cleanup System). This area has adequate backpressure which will decrease the fluctuation of flow ir.dication.
Summary I. No. Vill allow operations of higher blowdown flov to the condenser.
Malfunction of equipment is decreased by placement into the ASME III Section of the system. The' area of the new flov orifice is non-safety related, but is built to ASME III, ND, compared to the                        a previously installed B31.-l.                                                             I II. No. The area of the new flow orifice is non-safety related, but is built to ASME III, ND, vs. the previously installed B31.1.
III. No. Installation of a new flow orifice vill not reduce the margin of safety.                                                                                  I SE No.:     86-360                                                                                   i Source Document:        SP-2153 Description of Change Evaluation of Revision of SP-2153 entitled, " Technical Requirements for Fabrication and Installation of Structural Steel Items" to incorporate the 1985 Code Edition.of AUS Dl.l.
S,ummary                                                                                             I
    -I. No. The requirements in AVS D1.1-85 do not reduce the design and                             1 installation safety margins of velded structures previously designed                      )'
and installed per AVS DI.1-72.
II. No     See I above.
III. No. Technical Specifications are not involved.                                               I 4
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                                          - 183 -                                                         l

SE No.:      86-361 Source Document:       'PEI D23-2, Rev. 1 TCN #003 Description of Change Evaluation of Plant Emergency Instruction on Dryvell and Containment Pressure Control.
Summary
: 2. No. Actions taken in this procedure do not involve accidents evaluated in the FSAR.
II. No. The change to the containment venting steps resolves timing issues related to containment vent paths and potential containment pressurization scenarios. These changes have been evaluated in         (
SSER ?O.
The change to containment venting also included the deletion of the step that required the use of Containment Spray regardless of adequate core cooling. This step vas deleted due to the fact that j
Perry uses both Containment spray headers to vent the energy required by the generic EPGs and therefore precludes the use of RBR in the Containment Spray mode.
III. No. This change does not affect any Technical Specificat! n margin of safety.
SE No.:      86-362 i;ource Document:       DCN 0698 s
description of Change Drawing change (D302-671, D302-672) to allow for the de)-tion of pipe line spec./ safety class break symbol.
Summary I. No. Change is editorial only. The actual piping line spec. and safety class are not changed.
II, No. See I above.
III. No. Since neither the description of the plant nor plant equipment are changed. No change in safety is possible.
                                                                                    - 184 -

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,                                                                                                      l SE No.:                  86-363 DCN 1189                                                      l Source Document:
  ' Description of Change Drawing <hange (D912-617) to change MPL Number for flow indicator R710 to R711. Similar HPL numbers were assigned to different components.
Summary I. No.                Change to MPL number has no affect on system funetion.                   i l
II. No.                See I above.
I III. No.                 See I above.
SE No.:                  86-364 Source Document:                    DCN 1160                                                    .
l Description of Change                                                                           l Drawing change (D302-354) to revise jacket water drain line sizes on the lube oil coolers from 3/4" to 1". Change made to reflect as-built.
Summary
: 1. No.                This change does not increase the probability of occurrence,          l consequences of accident or malfunction of equipment important to safety.
II. No.                The possibility for an accident or malfunction of a different type    ;
than any evaluated previously is not created.                         i l
III. No.                 Increasing the drain line size from 3/4" to 1" has no impact on the margin of safety.                                                   .l l
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                , SE No.:          86-365-Source Document:            DCN 0560 Description of Change Draving change (D302-001) to clarify that "LC" and "LO" mean " Locked or Sealed in Closed Position" and " Locked or Sealed in Open Position,"
respectively.
Summary I. No. Locked means to fasten and prevent movement and that may be accomplished by locking or sealing.
II. No.        See I above.                                                          .e
                                                                                                            '\
III. No.         The margin of safety is not reduced.
SE No.:           86-366  ,
Source Document:            DCN 1249 Description of Change Drawing change to revise drawing 302-131 to show correct configuration on LS 210A/B, LS 220A/B, LS 225A/B and LS 230A/B.
Summary I. No. The. drawing changes do not affect the operation of the system.
The system operation has not changed,.therefore no new failure modes      {
II. No.
have been created.                                                      j l
III. No.         The Condenser Air Removal System is not described in the technical      j Specifications.
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                                                               - 186 -
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l SE No.:             86-367                                                                  )
Source Document:               DCN 1264                                                      j
                        ' Description of Change Draving change to allow for the addition of HPL number OP50-F0602 to P&ID Dvg. No. D-913-007, 1/4"- vent valve for chemical feed tank (P50-A002).
Summary I. No.        The item under evaluation is an editorial change which adds an MPL number-to an existing vent valve.
f' II. No.         See I above.
                         .III. No.            See I above. Containment Vessel Chilled Vater System is not addressed in Technical Specifications.
!                          SE No.:            86-368 L                          Source Document:              DCP 86-864, Rev. 0 l
Description of Change Design change to modify ductwork configuration to provide better supply air distribution for the Dryvell Cooling. System.
Summary I. No.        Total system airflow is not affected and therefore the overall l'                                             system function is not affected.
II. No.          See I above.
III. No.           This design change vill provide better supply air distribution, such l
                                              .that a lover average temperature can be realized, and thus be in l
compliance with the Technica) Specifications.
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r-SE No.:       86-369                                                                 l i
Source Document:         DCP 85-295H, Rev. 2 Description of Change Design change to allow for drilling of core drills and chipping of          ]
concrete for Tool Decontamination Room fire protection pipe.                 /
Summary 4
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I. No. The integrity of the slab is not compromised. No rebar is being cut.
II. No. See I above.
III. No.      See I above.
SE No.:       86-370 Source Document:          DCP 86-568B, Rev. O Description of Change C    'gn change to allow for the removnl of shield walls and curb and the installation of a new curb for CRD maintenance area. (Civil / Structural Evaluation)
Summary I. No. The removal of the shield wall decreases the loading on the Fuel Handling Building (599' elevation slab) and therefore increases the safety margin of the original design.
II. No. See I above.
III. No.      Since the integrity of the slab is not compromised, the margin of safety in the Technical Specifications is not reduced.
                                                 - 188 -
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l                                                                                                                l l                               Description of Change                                                             s Evaluation of rewrite to FSAR Section 11.2.2.12b to clarify the              ,
Programmable Logic Controller (PLC) operation and extended operability due date and the removal of the requirements for preoperational testing 7                                    of the automatic program so that it is consistent with other parts of the
!                                    FSAR.
                              ' Summary                                                                          )
I. No. The. consequences of an inadvertent release of liquid radvaste is not increased by not using the auto program. The Plant Radiation Monitoring System rad monitors along with the operational procedures vill prevent an inadvertent release while using the manual program.
II. No. The automatic program controls normal liquid radvaste processes.
Not using the auto program does not create a possibility for a new    i accident. By using the manual program, tank overflows are prevented by the receipt of high level alarms in the radvaste control room.
1 III. No. There is no safety reduction.
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SE No. '                         86-372 Source Document:                             EDDR 233 Description of Change
                                        ' Evaluation of a FSAR change (Section 6.2) to include a more detailed discussion regarding the situations during normal operation which could result in operation of the containment Vacuum Breakers (H17).               !
Summary i
I. No.                     Operation of the M17 Containment relief valves for reasons'other than relieving negative containment pressure due to inadvertent       ,
initiation of containment spray is expected and is not considered an ESF actuation.                                                        l The FSAR change associated with this safety evaluation is to include-  i a discussion of vacuum breaker operation due to minor differential pressures between containment interior and outside. The FSAR vill state that vacuum breaker operation is considered normal when a pressure differential between containment and outside exists due to operation of any system or atmospheric occurrence that results in a containment pressure change (i.e., operation of containment cooling; ventilation systems, plant shutdown /cooldown, changes in outside barometric pressure, etc.). The analyses which form the basis of the FSAR (6.2.1.1.4.2) section on containment vacuum breaker operation (CVB) considered all scenarios which could threaten containment and listed only those scenarios which required CVB operation to protect the containment. Statement "only" meant that those vere the only two scenarios (inadvertent containment spray actuation with and without RVCU line break which did require CVB operation to protect the containment. It has been shown by analysis that containment vill not experience a negative pressure due to containment spray operation during a design basis LOCA. All other scenarios do not threaten containment negative pressure design even if CVB's were not accounted for (Ref: Humphery issues item 8.4).
Since the containment system is designed to allow for periodic testing of peak pressure calculated to result from the postulated design basis accident (FSAR 6.2.1.1.1 G), and is also designed for a maximum negative pressure of .8 psig (FSAR 3.8.2.1.1), a degradation of containment integrity will not occur as a result of the operation described above, l
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                                                                             - 190 -

i SE No.:                    86-372 (Continued)
The cycling imposed on the vacuum breakers resulting from the above mentioned pressure change vill not cause degradation of the valves so as to affect their ability to meet containment isolation criteria. The valves are designed for a service life of 40 years and are periodically tested to ensure that they open fully at the design force (Spec. SP-635-4549-00), and leak tested to maintain containment isolation. The valves are cycle tested (full travel) at least once per 31 days and operationally tested with delta-P at least once per 18 months in e'cordance with Technical Specification 4.6.5.1. Therefore, probability of occurrence or consequences of an accident or malfunction of equipment important to                                   '
safety previously analyzed in the FSAR is not increased.
II. No.                  The only accident or malfunction associated with the M17 containment vacuum relief valves is failing to open or failing to shut. Open containment vacuum breakers has been evaluated and is addressed in Technical Specification Section 3.6.5.1, and FSAR Para. 6.2.1.1.4.2.3 (page 6.2-31). Failure of the valves to open to relieve minor negative pressures in containment during normal operation is bounded by the analysis for inadvertent containment spray actuation which only requires two of the four redundant valves to open. Therefore, the possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR is not created.
III. No.                   Operation of these valves is within the bounds of Technical Specification action statement 3.6.5.1.a. These valves are operating to maintain the primary containnant to secondary containment differential pressure within -0.1 to 1.0 psid as required by Technical Specifications (See 3.6.1.6). Therefore,          the margin of safety is not reduced.                                                                        j i
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i SE No.:    86-373                                                                  l DCP 86-176, Rev. O                                           I Source Document:                                                                   1 Description of Change Design change to reroute the industrial vaste lagoon decant line from the Vater Treatment System to the Service Water Pump House Forebay.
Summary I. No. The demineralized water make-up system is not evaluated in the FSAR and the industrial vaste lagoons are not described in the FSAR. No radioactive water vill enter the lagoons.
II. No. Rerouting of the decant line vill not affect the design bases of service water.                                                        {
III. No. The industrial vaste lagoon and service water are not defined in the Technical Specification bases.
SE No.:     86-374 Source Document:       DCP 86-405, Rev. O i
Description of Change Design change to allow for the isolation of CO2 line to chart storage room (lunch room).
Summary I. No. The FSAR (section 9A.4.4.5.1.2) already reflects that the old chart storage room is nov a lunch room, without CO2 protection.
II. No. See I above. The probability is decreased.
No Technical Specifications are affected by this design change.
                                                                                                                +
III. No.
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l SE No.a.   ' 86-3'/5 Source Document:.       DCP 86-735, Rev. O Description of Change Design change to allow for the installation of concrete fasteners for the addition of genflux seals required to support the Plant Environmental Conditions System Test. This is for the control of proper airflow in and out of certain areas.
Summary I. No. The installation of fasteners with shallow embedment depth (7/8") in the concrete cover does not af fect the structural integrity of the concrete.
II. No. See I above.
III. No. See I above.
i SE Nc.:      86-376 Source' Document:       DCN 1307 Description of Change Drawing change to correct P&ID D-913-001.       The chemical feeder tank vent valve is shown as 3/8" (F959), the vent valve is actually-1/4" in size.
                -(Control Complex Vater System).
Summary I. No. The safety analysis on the chiller system would not change due to the correction of the vent valve size from 3/8" to 1/4" on the P&ID.
II. No. Editorial change only.
III. No. The Technical Specifications do not address the Control Complex Chilled Water System.
                                                    - 193 -

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I SE Nc.:                                86-377 Source Document:                                   SCR 1-86-1289 thru 1292 Description of Change Setpoint change to increase'the "Lov Starting Air Pressure" alarm               l setpoint such that the setpoint tolerance and " Leave As Is Zone" will not      l allow the setpoint to violate the low pressure limit as described in the        j FSAR (Standby. Diesel Generator Starting Air System).                           l
                                                                                                                     )
1 Summary I. No.                   The setpoint change ensures that Standby Diesel Generator Starting Air Pressure is maintained above the low pressure limit as described in the FSAR and Technical Specifications. No equipment is modified or added by this setpoint change.
II. No.                          No new design is added by this change and all original design parameters are maintained.
III. No.                               The Technical Specifications are unaffected.                          ,
SE No.:                                 86-378 Source Document:                                   DCN 01168 Description of Change Drawing changes to provide as-built information.      (I&C Evaluation)
Sugmary I. No.                  The addition of as-built information to the radiation monitoring instrumentation diagrams has no impact on the operability of the instruments.
II. No.                         The operability of the radiation monitoring instruments is not affected by the as-built changes.
III. No.                               The addition of as-built changes has no impact on the operability requirements for specific radiation monitoring instruments.
Setpoint requirements are also unaffected.
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SE No.:       86-379 Source Document:       DCN 01168                                                                                           .l l
Description of Change Drawing changes to provide as-built information.     (Radiation Protection Evaluation) .
           $ummary l
I. No. Provides as-built information for nonsafety radiation monitoring                                                 l instrumentation,                                                                                              j II. No. Operability of the equipment is not affected.
III. No.      The margin of safety is not reduced.
SE No.:       86-380 Source Document:        DCP 86-575, Rev. O Description of Change Design change to allow for the relocation of Division III DC Bus Ammeter Shunts to show true battery amps and change out ammeters to zero center type to provide better indications.
Summary I. No. This change vill provide for better indication of the charge / discharge condition of the Division III battery, and make it consistent with Division I and II designs.
II. No. See I above.
III. No.       Technical Specifications are not affected.
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                                                    - 195 -

SE No.:     86-381 Source Document:        DCP 86-648, Rev. O Description of Change Design change to add drain lines to the Auxiliary Boiler fire box.                                 .
Summary I. No. The line.s are being added to extend present fire box drain lines to the Aux. Boiler Building's floor drains.
II. No. See I above.
III. No. The Auxiliary Boilers are not addressed in the Technical Specifications.
SE No.:      86-382 Source Document:         SXI-002, Rev. 1 Description of Change Evaluation of Safety-Related Instrument Air System (P57) Special Test that performs a post modification retest following completion of the i
design change to install low pressure air storage tanks.
Summary I. No. This. test vill ensure the new system meets the design criteria specified and therefore vill not increase the probability or l             . consequences of an accident.
II. No. Since the fundamental purpose of the system has not changed, and the                       1 output of the system remains the same, the possibility of creating a new accident or malfunction of a different type than previously l               evaluated in the FSAR therefore does not exist.
III. No. Since the P57 System vill supply air at 150 psig to the ADS accumulators and lov set relief valve accumulators in sufficient quality to ensure proper operation under accident conditions, the margin of safety is not being reduced.
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                                            - 196 -
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i SE.No.:                86-383 Source Document:                 DCN 1098 Description of Change Draving' change to update drawing 0 064-002 to reflect the present level
                           ' of construction for a portion of the Fire Main. The change reflected those portions of Unit 2 piping installed and serviceable for the Turbine Area.    (Fire Protection System)
Summary
                      . I . No . - Items are within the scope of the Fire Protection Procedures.
Change does not affect system operation nor does it affect safe shutdown.
II. No.      There are no potential initiating causes of threats to the plant.
III. No.          Only the administrative aspects of fire proteccion are in the Technical Specifications.
SE No.:           86-384 Source Document:            DCN 01130 Description of Change Drawing chango to add note to Off-Gas System (N64) P&ID to state that     ,
piping between SJAE and recombiner C3-4 line spec. does not require impact testing. GE Design Spec. 22A3089, 4.4.13a states that impact        I testing is necessary only for areas where operating temperatures are belov 32'F.
Summary I. No.      Temperatures between the SJAE and recombiners are not lov enough to require impact testing.
II. No.      No components or piping were added or deleted as a result of this change. The integrity of the piping remains unchanged.
III. No.        See II above.
                                                               - 197 -

l SE No.:    86-385 Source Document:      DCP 86-602F, Rev. 1 Description of_ Change Design change to allov for the deletion of the Safety-Related Instrument Air pressure instrumentation (EHO-11) in the high pressure side of the system, and installation of safety-related air pressure instrumentation for the new air storage tanks (1P57-A003A, B), as well as the deletion of the old alarm setpoints and addition of new alarm setpoints.
Summary I. No. Since the old viring and instrumentation was utilized for the new instrumentation (with the exception of replacing the single alarm unit with a dual alarm unit), the only aspects of the design change that needs to be evaluated are the range of the instrumentation and  .
the alarm setpoints. . Normal tank pressure vill be between 160 and 170 psig with system design limits of 150 and 180 psig. The new range for the loop is 0-300 psig which encompasses those pressures.
The alarm setpoints vill give annunciation prior to going below the 150 psig and going above the 180 psig design limits.
II. No. The'new instrument range and alarm setpoint are within system design limits, therefore no new accidents or malfunctions have been created.
III. No. The margin of safety has not been reduced.
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SE'No.:                 86-386 Source Document:                   NR-HH0S-1433, Rev. O
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Description of Change Evaluation of class I pipe support on which the final magnetic particle examination of velds was not performed as required by ASME Section III, subsection NF, Article 5212. m (These velds are to be reworked before escalation beyond 5% power.)
Summary l
I. No. The purpose of the support in question, is to restrain the piping horizontally during a seismic event and it takes no loading during I                                                     normal operation. These velds have over five times the amount of l                                                     veld necessary to safely carry the passive (not there during normal operation) loading condition.
i II. No.       See I above.
III. No.                The Technical Specifications do not address this.
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l SE No.t       86-387 Source Document:          DCP 86-602E, Rev. 1                                       f Description of Change Design change to allow for the deletion of the Safety-Related Instrument Air pressure instrumentation (EH0-08) in the high pressure side of the system and installation of safety-related air pressure instrumentation for the new air storage tanks (1P57-A003A, B), as well as the deletion of   l the old alarm setpoints and addition of new alarm setpoints.
I Summary I. No.      Since the old viring was utilized for the new instrumentation (with the exception of extending the old viring to the nev location), the only aspects of the design change that needs to be evaluated are the range of the instrumentation and the alarm setpoints. Normal tank pressure vill be between 160 and 170 psig with system design limits  3 of 150 and 180 psig. The new range for the loop is 0-300 psig which encompasses those pressures. The alarm setpoints vill give annunciation prior to going below the 150 psig and going above the 180 psig design limits.
II. No.      The new instrument range and alarm setpoint are within system design limits, therefore no new accidents or malfunctions have been created.
III. No.      The margin of safety has not been reduced.
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SE No.:                                      86-388 Source Document:                                                                  DCP 86-602C, Rev. 8 Description of Change Design change to allow for the installation of a new Pressure Switch P57-N702 (Safety-Related Instrument Air System) and to svitch over to the low pressure system.
Summary I. No.                       The replacement of the existing Pressure Switch IP57-N702 with the new pressure switch vill not incr. ease the probability of occurrence or the consequences of an accident. The new pressure svitch that controls the air compressor is non-safety related and is of the same standards and basic requirements as the original pressure switch.
The new svitch vill start and stop the air compressor at approximately 160 psig and 170 psig respectively, compared to the                                    i old values of 2,550 psig and 2,650 psig.                                                             (
                                                                                                                                                       )
II. No.                            The nev installation has applied the same methods utilized for the                                   1 original system installation to determine the effects and probability for an accident and/or equipment malfunction.
III. No.                                  The margin of safety defined in the bases of the Technical Specifications (calibration schedule) vill not be reduced.
SE No.:                                  86-389 Source Document:                                                              DCP 86-872, Rev. O Description of Change Design change to allow for the replacement of lined piping with stainless steel piping (Liquid Radvaste Disposal System).
Summary I. No.                   The replacement of lined piping with stainless steel piping exceeds the original design.
II. No.                         The addition of stainless steel piping prevents potential radioactive liquid leaks. This change meets or exceeds the original design.
III. No.                               The addition of stainless steel piping does not affect the discharge of liquid or solid radioactive vaste.
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SE No.:          86 390 Source Document:              DCP 86-602J, Rev. O Description of Change Design change to summarize the total modification to the Safety-Related Instrument Air System (P57) as depicted in previous design changes to provide an "overall" safety evaluation.
Summary I. No.       The modification to.the P57 system is to provide a low pressure stored air system in lieu of a high pressure air storage design.
The basis function of the uystem is to provide.a safety-related l
stored energy source (compressed air) for ADS operation. Since the proposed storage tank increases the air storage capacity, the P57 system design capability and function vill not be impacted.
The modified system is constructed to the same codes and standards (eg. ASME'Section III) as the original system, so that the probability and consequences of an accident are not increased from l                                         that in the FSAR. The structural alterations,.such as concrete and rebar rbmoval, do not compromise the ability of the structures to support their design loads. The new instrumentation, although covering the low pressure range, provides the same functions as before, with the same reliability and therefore does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment evaluated in FSAR. The operation of the air compressor in the low pressure range vill not alter the reliability of the nonsafety air ~ compressor or the reliability of the safety-related portion of the system, since it is consistent with the original design. The modification has no impact on the FSAR Chapter 15 analysis, in that the analysis utilized operation of the ADS valves but does NOT specifically refer to a high pressure air source. The' modification does NOT reduce the availability and reliability of the low pressure air used to operate the ADS valves, because the design and hardware comply with the same codes and standards as the criginal design, i
II. No.        The FSAR analysis utilized a single failure criteria so that accidents or malfunctions beyond this criteria vould represent a different type than that in the FSAR. This modification does NOT create possibilities of accidents or malfunction beyond the FSAR in that the same codes and standards for piping, structural,
'           '                              electrical, etc. are met after the modification as was met before it. The modified system with the increased air storage capacity is considered to be more reliable. The instrumentation and associated setpoints provide the same functions to preclude malfunctions as before. The structural capabilities such as slab capabilities are unchanged so that the possibility of an accident or malfunction is i
not increased. The ability of each structure to support the design loads is not compromised. The new storage tanks and piping do not pose new accidents or malfunctions to other existing systems.
                                                                        - 202 -

I SE No.:       86-390 (Continued)
III. No.      The margin of safety in the Technical Specifications is not reduced by the modification. The bases of Technical Specifications discuss        ;
the reliability of the ADS system, ie., ADS valves to open when          l required. This proper ADS valve operation is premised on                  i availability and reliabilities of the stored energy (compressed air)      !
of the P57 system. The availability and reliability of P57 is enhanced by this modification (more stored energy), thus the margin      j of safety is not reduced.
1 SE No.:-       86-391 Source Document:           FSAR CR No. 86-111                                         l l
Description of Change Evaluation of various editorial and organizational changes to FSAR             !
Chapter 17.
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Summary I. No. There are no possible accidents or malfunctions associated with reassigning responsibilities in a service department.
i                        II. No. See I above, l
III. No.       Not described in bases. No responsibilities have been deleted, they have been simply reassigned, l
l SE No.:        86-392 Source Document:           DCP 86-775, Rev. 0 l                    Description of Change l
Design change to allow for a field viring change to a Limitorque SMB-000      :
Torque Switch to facilitate torque switch balancing (calibration).            l l
(Liquid Radvaste Sumps) l                       Summary l                          I. No. This change faellitates testing with no change to operability.
I II. No. The function of the MOV is unchanged.
III. No. This H0V's function as a containment isolation valve is unchanged by this change. The safety margin is unaffected.                          j g
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l SE No.:      86-393 Source Document DCN 1317                                                  !
Description of Change                                                             1 Drawing change (D912-602) to add a HPL number to the system drawing.         !
Summary i
I. No. No FSAR evaluation has taken credit for the subject split ter damper having an MPL number.
II. No. No functional change is created by adding an HPL number.
III. No. See II above.
SE No.:      86-394                                                               l Source Document:        DCP 86-806, Rev. 0 l
D scription of Change Design change pertaining to the addition of terminal points to improve       !
testing (Residual Heat Removal System).       In panels 1H13-P618 and P629, i      ,             the circuit viring is to be revised and States Co. Class 1E sliding link terminal blocks installed.
Summary I. No. The overall function and integrity of the system l                           configuration / operability is not compromised. This design change   i vill reduce the potential for human error during the performance of  !
a particular surveillance instruction (in lieu of lifting leads),
thus improving the overall efficiency and methodology.               )
II. No. See I above. Also SSER Number 7, Section 7.2.2.6 provides an         I additional evaluation.                                               ,
III. No. This design change enhances the practical aspects and parameters required for testability of systems / components resulting in increased margins of safety.
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SE No.:      86-395 Source Document:        DCP 86-907, Rev. O
                                                        \                                          .
               ' Description of Change Design change to provide for a turbine driven feedvater pump casing vent addition.
J Summary
    'O               I. No. This modification affects the nonsafety portion of the Feedvater System and has no direct or. indirect affect on any safety-related                                         !
systems,                                                                                                   i i
The addition of this vent valve does not pose any new accident ~                                         '!
II. No.
potential.                                                                                                 ;
i III. No. The Feedvater System is not discussed in'the Technical                                                     l Specifications.
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SE No.:       86-396                                                                                                    ;
Source Document:-       DCP 86-818, Rev. O Description of Change                                                                                                   ;
Design change for the addition of hollov metal doors to the turbine building condenser area to control airflow patterns.                                                            .
Summary I. No. Doors are nonsafety, non security, and non fire rated doors which serve no safety. function.
II. No. .The doors are installed only to provide an air seal and they do not                                         !
interfere with any safety systems.                                                                        l III. No. No safety systems are affected.
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SE No.:       86-397                                                                   .
Source Document:          DCP 86-943, Rev. O Description of Change                                                                  ,
Design change to connect the Division 3 Diesel Generator neutral ground transformer secondary to 240V.                                                ,
Summary I. No. The transformer connection to 240V taps vill allow operation of ground fault relay as described in the FSAR.
II. No. The function of the ground fault system is not changed.                  i III. No.      The neutral ground transformer is not defined in the Technical Specification bases.                                                     3 i
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Description of Change Setpoint change for ground fault-relay (59NG) so that the relay will adequately protect the Diesel Generator while providing better selective coordination with all other ground fault detection devices on the Division 3 safety bus.
Summary                                                                              -i I. No. The functional capabilities / limitations of this relay and its effect on the Division 3 bus, including the fact that the relay's trip function is bypassed during LOCA condition are not changed by the issuance of this relay setpoint and remain as described in the PSAR. j II. No. See I-above.                                                             L l
i III. No.      The relay and its associated setpoint values are not discussed in          )
the Technical Specifications.
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l SE No.:               86'-399 Source Document:-                 DCP 86-139, Rev. O Description of Change Design change to relocate flow element (1N33-N240) in steam seal pipe.
It.is to be interchanged with pipe plug downstream.
Summary I. No.              Flow element and pipe plug locations are simply interchanged. The       l steam seal system is nonsafety.                                         (
                                                                                                                  \
II. No.'             See.I above.
III. No.              These component locations do not affect Technical Specifications.
I SE No.:                86-400 Source Document:                  NR-PPDN-477, Rev. 1 Description of Change Evaluation'of interim operation of Containment Vessel and Dryvell Purge             ,
System, Controlled Access Area HVAC System, Radvaste Building Ventilation          l System, Intermediate. Building Ventilation System, Turbine Building Ventilation System, Auxiliary Building Ventilation System, Heater Bay Ventilation System and the Turbina Power Complex Ventilation System Fans with improper motor bearing lubrication. This bearing lubrication will be replaced over time with proper lubrication.                                     ;
Summary I. No.              Redundant fans are provided for maintenance and operational flexibility. There is no impact to any ttansient or accident analysis in the FSAR as all of these fans serve nonsafety functions.
II. No.               See I above.
III. No.              Technical Specifications do not address any margin of safety for the   j subject equipment.
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- - - _ - _ _ - _ -                     -      _ _                                                                i

i SE No.:                   86-401                                                                     j Source Document:                           DCP 86-0568D, Rev. 0                                      l l
l Description of Change Design change to allow for plugging of equipment drains in the CRD maintenance room as needed for installation of the CRD Decontamination,           )
Rebuild and Reassembly System.                                                    4 Summary I. No.       All of the equipment and floor drains in this room tie into the same
                                  -run of pipe that eventually empties into the Intermediate Building         1 Dirty Radwaste sump.
II.                 No.        See I above. Plugging two of the seven drains in the CRD Maintenance Area Room does not create any new possibility for an accident or malfunction since nearby drains are to be utilized instead.
III. No.                      This design change does not affect the Technical Specifications.
         .SE No.:                         86-402 Source Document:                           DCP 86-0936, Rev. O Description of Change Design change to allow for the installation of a remote start interlock switch and actuation seal-in logic for Unit 1 & 2 Post Accident Radiation Monitoring System Vent Monitors. This change improves system reliability by providing manual start capability and avoiding deactivation.
Summary I. No.           This design improvement increases operational readiness and system availability.
II.             No.          See I above III. No.                     Margin of safety not affected.
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                                                                      - 208 -
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l SE No.:     86-403 Source Document:       DCP 86-0864, Rev. 3                                           l
                               ' Description of Change Design change to allow for the modification of design flevrates of dryvell cooling air supply ductwork to improve dryvell cooling.                j Summary                                                                              1 I. No. The original design change involved the addition and relocation of    !
supply' registers to provide better supply air distribution. This revision changes the design flovr,'tes at individual supply registers. The total system airfiov value is.not affected and         ,
therefore the overall system function is not affected.
II. No. See I above.-
III. No. This design change vill provide better supply air distribution, such that a lover average temperature can be realized.
SE No.:     86-404                                                               f Source Document:       DCN 554 Description of Change Draving change to clarify P&I-(302-002) dravitg abbreviation =, "LC" and "LO" to mean " locked or scaled in closed positton" nad " locked or sealed in open position", respectively.                                           ,
Summary I. No. This change only clarifies what was done correctly in Perry design.
This meaning of locking is consistent with that in ANSI /ANS 56.2-1984 and NUREG 0800.                                 l II. No. See I above.
III. No. See I above.
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SE No.:                            86-405                                                                                                                 '
Source Document:                                                                                                        DCN 1319 Description of Change                                                                                                                                     l Drawing changes to update drawings to reflect as-built condition, to shov                                                                           (
condenser pressure switches connected directly to condenser instead of through a common line.                                                                                                    (Nonsafety-Related)
Summary f
I. No.                            The signals to obtain the pressure readings for the turbine trip instrumentation and the steam bypass instrumentation are still                                                     l j
monitoring from the condensers. The overall design parameters are the same as the previous design.
II. No.                              See I above.
III. No.                               The system functionability has not changed or been reduced.
SE No.:                                86-406 Source Document:                                                                                                        DCP 85-0225B, Rev. O Description of Change Design change to allow for the replacement of extraction pumps (Turbine Plant Sampling System) with pumps that vill provide a greater TDH and l
supply an adequate flov to the sample panel.
Summary I. No.                                The condenser extraction pumps were not evaluated in the FSAR.
II. No.                                 None of the pumps perform a safety-related function and they are not                                           l required for safe shutdown.
III. No.                                  The condensate extraction pumps are not part of the Technical                                                  l I
Specification bases.
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i SE No.:    86-407 Source Document:      DCP 86-0568, Rev. O Description of Change Evaluation of the installation of Hilti bolts and Drillco bolts in safety-related concrete. Pertains to the design change to install the Control Rod Drive Decontamination, Rebuild and Reassembly System.
(Nonsafety-Related System)
Summary I. No. The integrity of the structural concrete is not impaired.
II. No. See I above.                                                         l III. No. See I above.
i SE No.:    86-408                                                               ,
Source Document:      SCR l-86-735 & 736                                        I Description of Change                                                           i Setpoint change to increase setpoint for HPCS diesel starting air pressure lov alarms to annunciate the Technical Specification limit.
Summary I. No. This change does not add or modify any equipment important to safety. This setpoint change is conservative with respect to system operation, such that a low pressure alarm is annunciated at a higher pressure than the original alarm setpoint. All design parameters which ensure the emergency functions and reliability of this system are maintained.
II. No. See I above.                                                          I III. No. The Technical Specifications are not affected.                         (
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      .SE No.:        86 409 Source' Document:         DCP E 5-0568D, Rev. 1                                                                  :
Description of Change Design change to trim drain lines flush with floor to accommodate a drain trough for new equipment. Pertains to the design change to install the Control Rod Drive Decontamination, Rebuild and Reassembly System.
Summary I. No. The standpipe does not influence any FSAR accidents or malfunctions and thus has no effect on them.
II. No. The standpipe height has no effect upon reactor safety.
III. No.        The margin of safety is not reduced.
i SE No.:         86-410 Source Document:          DCP 86-0919, Rev. O Description of Change Design change to allow for the i sta11ation of the NUS Process Services                                 !
                " Quick Dry" devatering process. This is necessary to remove any free                                  !
vater in the package of bead or powdered resin so that it complies with all. transportation and burial requirements.
Summary                                                                                                        i I. No. Existing equipment and structures are.available to eliminate, mitigate, or control the hazards to an acceptable level. The NUS                                 l equipment meets the intent of Regulatory Guide 1.143.                                           i II. No. See I above. The exposure limits of 40CFR190, 10CFR20, and 10CFR100                              ;
are met.
III. No. See 1 and II above.
                                                                                                                       )
                                                   - 212 -

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SE No.:    86-411 Source Document:      DCN 01272 Description of Change                                                           l P&I drawing changes to show physical boundaries, line class and MPL identification numbers (off-gas system).
Summary I. No. Drawing changes for clarification only, and does not affect equipment function or accident consequences.
1 II. No. See I above.                                                         1 III. No. See I above.
SE No.:    86-412 Source Document:      TER 80-01 Description of Change Evaluation of Traveling In-core Probe hot alignment test deferral to TC-1.                                                                      ;
                                                                                              )
Summary I. No. TIP is not safety-related and this change does not affect safety-related systems.
II. No. TIP alignment vill be performed during the same prevailing reactor condition but in Test Condition 1 instead of Heatup.
III. No. See I and II above. All subsequent manipulations of the TIP System  ,
in the Power Ascension Program have completion of the hot TIP       l alignment as a prerequisite. Therefore, this test vill be performed before such time that an LPRM calibrat'-   is needed and those results used in the determination ot       chermal limits.
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VLI-P45 Rev. 2, TC 3                                         f
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Description of Change                                                                   {
Evaluation of use of two 3 inch bypass valves for throttling flov around       j the Emergency. Closed Cooling heat exchanger's A/B Emergency Service Vater     l l                     outlet valves IP45-P541A/B.                                                    .
I 1
1 Summary                                                                                 i.
I. No. The FSAR requires in 9.2.1.2 that cooling vater be available to          l components at all times with no dependence on automatic flow control     l valvec. The new valves are manual valves as are the valves they          j bypass. The mode of operation using the 3" manual valves is              !
identical to that using the 14" valves they bypass. This conforms        .
With the FSAR requirements and poses no change in the probability        l for an accident or malfunction previously evaluated in the FSAR.         [
i II. No.      See I above.                                                             l III. No.       Since the mode of system operation with the 3" valves is identical      l to that with the 14" valves, including adherence to design heat removal capacity-for the ECC heat exchangers, no margin of safety is reduced by.the use of the 3" valves.
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1 SE No.:       86-414
              ~~~ Source Document:
S0I-G33, Rev. 3, TC 15                                      1 VLI-G33, Rev. 3, TC 3                                       l ARI-H13-P680-1, Rev. 1, TC 3 i
Description of Change 1
Procedure changes resulting from a design change to add flow sensing          l device 1G33-FE-N606 in the RVCU blovdown to Main Condenser /RV line, and      l disconnecting the existing 1G33-FE-N011 from the Leak Detection System isolation instrumentation (See also SE Pa's:     86-338, 339, 341, 342, 345,  ;
1 346, 347, 348 and 358).                                                       l Summary l
I. No. The. system is operated the same as before the modification. The changes to the procedures involve no configurations or lineups         I outside the assumptions of the FSAR.
II. No.       See I above.
III. No.       See I above.
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i SE No.:        86-415 Source Document:          SXI-0002, Rev. 1, TCN-001 Description of Change I
i Change to Safety-Related Instrument Air System Special Test to change the location of data collection to a point that-is more accurate and representative of system pressure.
Summary I. No.      Test requirements and method not altered.
II, "$.      See I above. Does not alter the method of operation or the actual l system configuration.                                                t III. No.       See II above.                                                        l l
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SE No.:         86-416 SCR 1-86-1468                                            j Source Document:
l Description of Change Setpoint change to increase the compressor stop setpoint from 170 to 185 psig to account for pressure losses between the compressor and the      !
air storage tanks for the safety-related instrument air system.
{
Summary I. No.      This design change does not impact plant systems, components or     !
structures that prevent occurrence of those accidents listed in Ch.15- of the FSAR.-
II. No.      Relief valves with set pressures lover than the respective system   j design pressures prevent the over pressurization of system          l components.
III. No.       The margin of safety is not reduced.                                ;
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SE No.:   86-417 Source Document       DCP 86-0916, Rev, 0 l
Description'of Change                                                               j 1
Design change to enlarge section of loop seal to prevent siphoning in off-gas system holdup line.
Summary I. No. Piping modification vill eliminate loop seal level drops due to siphoning. Loop seal new design vill prevent the loop from running   ,
lov and existing shutoff valves prevent the seal from going dry.     !
II. No. See I above.                                                         i III. No. The margin of safety is not reduced.                                    l
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SE No.:    86-418                                                                 ,
Source Doc'ument:     SXI-0002, Rev. 1, TCN-002 Description of Change
_ Change to Safety-Related Instrument Air System (P57) Special Test to     j change the devpoint from -40'F to 0"F.                                       !
f Summary                                                                         .
I. No. ISA Standard S7.3, " Quality Standard for Instrument Air",               f Section 4.1.2, states that devpoint at line pressure shall be at least 18'F below the minimum ambient temperature, but in no case grcater than 35'F. Since all P57 piping is indoors, the minimum     ,
ambient temperature is 60*F. The system is also tested in             j accordance with Reg. Guide 1.80 which requires a loss of instrument air supply test that simulates the loss of instrument air due to       ,
i moisture freezing and plugging the main supply line. This test verifies the safety-related function of the system is not impaired    ,
even if a supply line did freeze up,                                   i II. No. See I above.                                                          l l
III. No. The margin of safety is not reduced.
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1 SB'No.:     86-419 Source Document:        DCP 86-0981, Kev. O
\
N                                                                                                                         1 LI           ~ Description of Change                                                                                               I
  ' \m o                                                                                                                           \
    ' On 1 :        Design change to install filters in Breakers lA, 1B, 2A & 2B trip                                              i circuits (Hetal Clad Switchgear, 5-15kV, System) to reduce the noise and                                   j therefore the number of reactor recirculation pump trips.                                                     )
(Nonsafety-Related) i Summary I. No. The filter installation vill reduce the r.oise from the de bus and prevent the unnecessary tripping of the breakers, which vill minimize the potential for cavitation of the recire. pumps, jet pumps or flow control valves and supply sufficient flow for adequate mixing of the reactor water.
1 Failure of any filter will only impact a single breaker, and the other breaker vill be available to trip the pump.
(               II. No. See I above.
III. No.      See I above.
1 SE No.:       86-420 Source Document          DCP 86-0568E, Rev. 0 Description of Change                                                                                             j Evaluation of the installation of Hilti bolts in safety-related concrete.                                 l Pertains to the design change to install conduit, cables and the mounting struts for safety svitch and controller for the CRD ultrasonic cleaning                                   ,
tank.
Summary I. No. Hilti bolts do not impair the integrity of the structural concrete.
II. No. See I above.                                                                                        p III. No. See I above.
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SE No.:: 86-421
                  ' Source Documents-        PNPP Emergency Plan, Rev. 6, TCN-001 Description of Change i
                          . Change made to Emergency Plan to update position title for Technical                                         !
Support Center Operations Manager alternate (the PPTD Manager was changed to the Technical Superintendent).
Summary
: 1. No. Administrative change only.
II. No. See I above.
1 III. No.      See I above.
I SE No.:       86-422 Source Document:          DCP 86-0925, Rev. O i
Description of Change Evaluation of relocation of Hilti bolts for support 1H17-H002.                                 Pertains to design change to allow for the modification of pipe support 1H17-H002 (Containment Vacuum Relief System) to provide proper attachment to vall.
Summary                                                                                                            ;
I. No. The installation of Hilti~ bolts do not compromise the integrity of                                    !
structural concrete.
II. No. See I above.                                                                                         f III. No.      See I above.
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                                                                - 218 -
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f SE No.:     86-0423 Source Document:       DCP 86-0771, Rev. 0
                        - Description of Change Design change to add a control switch in the Liquid Radvaste Panel H51-P031-9 to override the ESV Process Radiation Monitor interlock.
(I6C Evaluation).                                                      ,
Summary I. No. The Radiation Monitor and Liquid Radvaste Systems are nonsafety.    ?
The override switch will allov discharging, per the Technical Specifications, when the radiation monitor is inoperable.           l 1
II. No. The addition of a switch vill improve discharging method and will reduce the possibility of human error.
III. No. Override is permitted when the Rad. Honitor is inoperable.
SE No.:     86-424 Source Document:       DCP 86-0771, Rev. O Description of Change l
Design change to add a control switch in the Liquid Radvaste Panel
                                !!51-P031-9 to override the ESV Process Radiation Monitor interlock.
(Electrical Evaluation)                                                  I Summary I. No. The Radiation Monitor and Liquid Radvaste Systems are nonsafety.    >
The override switch vill allow discharging, per the Technical Specifications, when the radiation monitor is inoperable.
II. No. The addition of a switch vill improve discharging method and vill   i reduce the possibility of human error,                             d 1
III. No. Override is pe'rmitted when the Rad. Monitor is inoperable.          I i
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SB No'.      86-425-Source Document:        DCP 86-0771, Rev. O Description of Change Design change to add a control switch in the Liquid Radvaste Panel
                                     .H51-P031-9 to override the ESV Process Radiation Monitor interlock.
(Chemical Evaluation)
Summary I. No. The Radiation Monitor and Liquid Radvaste Systems are nonsafety.
The override switch will allow discharging, per the Technical Specifications, when the radiation monitor is inoperable.
II. No. The addition of a switch vill improve discharging method and vill reduce the possibility of human error.
III. No. Override is permitted when the Rad. Monitor is inoperable.
                              -SE No.:      86-426
                               $ource Document:        Temporary SCR's T-1-86-007 through 014 Description of Change Temporary setpoint change to reduce the APRM hi flux setpoint to correspond to lover expected neutron flux levels during start-up tests. .
Summary I. No. This change is in the conservative direction to maintain safety margins.
II. No. The reactor protection function is retained by this change.        l III. No. See I above.
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l SE No.:       86-427' Source Document:          'PEI M51/56, Rev. O Description of Change Evaluation of use of Plant Emergency Instruction on Hydrogen Control.
Summary                                                               ,
I. No. The steps taken in this Perry Specific Instruction have been evaluated in SSER 10. The procedure is based on the latest Hydrogen Control Ovner's Group Guideline.
II. No. See I above.
III. No.       There is no effect on the Technical Specifications.
SE.No.:        86-428 Source Document:           'SOI-E12, Rev. 3 TCN-0013 Description of Change Evaluation of Operating Instruction on use of LPCI injection lines as
                  . alternate return path for shutdown cooling, when the norsial paths are not available.
Summary I. No. This return path being used leaves all protective interlocks and automatic functions intact. It uses discharge piping equally qualified to that of the normal return path with equivalent backflow protection. The method of decay heat removal is the RHR HXs used for the normal shutdown cooling flow path. The new flow path being used for shutdown cooling is within the scope of the analysis in.
FSAR Section 15.2.9 and is covered in SSER 5 Section 3.9 for emergency situations, where the normal shutdown cooling return paths are not available.
II. No. See I above.
III. No. The Technical Specification bases for RRR, Section B3/4.4.9 require that 2 loops of shutdown cooling be operable or that alternate methods of decay heat removal be demonstrated. The use of the LPCI injection lines as alternate flow paths provides 2 loops of shutdown cooling. The RHR system also remains available for overcoming accidental coolant losses satisfying the Technical Specification bases B3/4.5.1 and B3/4.5.2.
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SE No.:    86-429 Source Document:      DCP 86-0204, Rev. O I
Description of Change Design change to add an isolation valve in instrument air header for          i maintenance of RVCU filter /demin system.      (Nonsafety-Related)            i Summary 1
i I. No. System configurations for accidents previously evaluated are not affected.
II. No. Loss of air pressure due to inadvertent closure has been evaluated      l in FSAR 9.3.1.                                                          l III. No. See I & II above.
SE No.:     86-.430 Source Document:       DCP 86-877, Rev. O l
Description of Change Design change to revise circuit viring and provide different terminal-blocks to minimize the need for lifting leads and to facilitate jumper installation during repetitive surveillance tests (Nuclear Boiler            !
System).                                                                     l 1
Summary I. No. The overall function and integrity of the system configuration / operability is not compromised. This change vill reduce the potential for human error during the performance of a i
particular SVI (in lieu of lifting leads), thus improving the overall efficiency and methodology respectively.                        { 4 II. No. See I above. Evaluated previously in SSER No. 7, Section 7.
III. No. See I above. This design change enhances the practical aspects and       l parameters required for testability of systems / components resulting    l in increased margins of safety.
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l SE No.:     86-431                                                                                l Source Document:        FSAR CR No. 86-047
    . Description of Change l
FSAR change to delete the Operator Training Unit (OTU) Supervisor                         l position from the training matrix as shown on Figure 13.2-1 of the FSAR.
l Summary I. No. The OTU Supervisor position.is managerial vice technical, and is not required by Reg. Guide 1.8-1975.
II. No. See I above.
III. No. The margin of safety is not reduced.
SE No.:     86-432 Source Document:        FSAR CR No. 86-119.
Description of Change FSAR change, to change the maximum resistance for the Computer Room HVAC               i' System Roughing . Filters (in v.g.) from 0.40 (clean) to 0.60 (clean at 2000 CPH) to agree with manufacturer data.
Summary I. No. The Computer Room HVAC System is not required to operate to safely shut down the plant, nor vill it result in malfunction of equipment important to the safe shutdown of the plant.
II. No. See I above. The system vill continue to operate within its design envelope.
III. No. See I & II above.
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                                               - 223 -

:4 SE No.:   86-433 Source Document:     NR-MMOS 1850, Rev. O i
  -Description of Change Evaluation of Relay (1R2200802), whose trip function is bypassed during a diesel generator response to a LOCA signal and has a relay pick-up                                         l setpoint of 7408 amps instead of the 8000 amps specified on the Master                                      i Setpoint List.
Summary                                                                                                         i I. No. This deviation vill not affect the diesel generators ability to operate as described in the FSAR.
II. No. See I above.
i III. No. This relay is not discussed in the Technical Specifications.                                          !
SE No.:   86-434 Source Document:     NR-MMOS 1357, 1401, 1383, 1384 i
Description of Change                                                                                           i f
Evaluation of MOV's 1E22F0010, 1E22F0011, 1E22F0023 and 1E22F0012 in the HPCS system with torque switch settings less than those required by the                                    j Master Setpoint List. M0 VATS testing is to be performed by November   15,                                 '
1987. Both 1E22F0023 and 1E22F0012, which are containment isolation valves, passed their LLRT.
f Summary I. No. Adequate flow is supplied to the reactor. All four M0V's vill go:
fully closed, but possibly not tightly.
II. No. The probability of HPCS receiving an injec tion signal while in the test mode is negligible. HPCS is a back-up to RCIC as a high pressure injection system.
III. No. The operability of HPCS as defined in the Technical Specifications is unchanged.
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                                         - 224 -
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SE No.:     86-435' Source Document:        DCP 86-0749, Rev. O Description of Change Addition of vall and door to the existing NRC office located in the                              <
Service Building.
Summary-I. No. The change.to the FSAR involves only the architectural layout of the                       i l
NRC office in the Service Building.
l II. No. See I above.
III. No. See I above.                                                                               l I
i SE No.:     86-436 Source Documentt         DCP 85-0427                                                                   ,
SCR 1-86-1334, 1438 through 1441 i
Description of Change-                                                                                 ,
i Design change to replace diesel fuel oil storage tank level transmitters vith water tight, explosion proof sonic detectors and adjust setpoints.
Summary l
I. No. Reliability of measurement was improved. System is classified                         j nonsafety.
II. No. This design change enhances the fuel oil measurement.                                     i III. No. See I above. The setpoint calculations are in a conservative direction.
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i' SE No.:      86-437-Source Document:         DCP 85-0427A, Rev. 0                                                          [
Description of Change                                                                                   !
Design change to allow for the fabrication and installation of flanges                            .
and piping to accommodate the installation of new diesel generator fuel.                          !
oil storage tank-level-transmitters.      (Piping & Equipment Evaluation)                       j i
Summary i
I. No. Changing the location where the level instrumentation enters-the tank does not impact equipment important to safety.
II. No. See I above.
III. No. The margin of safety is maintained with ASME Section III, Class 3 guidelines.
l SE No.:       86-0438                                                                                   !
Source Document:        DCP 85-0427A, Rev. O Description of Change Design change to replace the diesel fuel oil storage tank level instrumentation.     (Piping Evaluation)
Summary I. No. Existing level transmitters are being replaced with new level transmitters to decrease the probability of a malfunction.
II. No. See I above.
III. No.      Diesel fuel tank level is still being monitored.
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i SE No.:      86-439 Source Document:        DCP 85-0427A, Rev. 0                                        ]
L Description of Change                                                             ]q l-Design change to allow for the fabrication and installation of flanges      f and piping to accommodate the installation of new diesel generator fuel oil storage tank level transmitters and the removal of original design-     3 i
transmitters. (Hechanical Evaluation)
Summary I. No. The scope of this change is limited to the Fuel Oil Transfer System,    l vhich by itself cannot cause a design basis accident. The function l
and reliability of the original design has been enhanced.             l 1
All original design parameters have been maintained,                  l II. No.
I III. No.      See I and II above.                                                  l SE No.:       86 440                                                               ,
DCN 01337                                                 !
Source Document                                                                    l Description of Change                                                              3 Draving change (D302-214, D302-791) to add nonsafety designation to         j instrumentation and tubing downstream of safety-class root valves in       !
ESV/ESV Screen Vash System.
i Summary
                                                                                                     .i l
I. No. Editorial change.                                                    ]
II. No. See I above.
III. No. See I above.                                                           j 1
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l SE No.:     86-441                                                                       ,
Source Document:       _DCN 01343 Description of Change Drawing change (913-001) to delete lov oil temperature alarms on control complex chiller crankcases to reflect as-built.   (HVAC Evaluation)
Summary
                   'I. No. .This change does not hamper the design intent of the equipment.
II. No. See I.above. This change is not described in the FSAR.
III. No. This subject is not described in the Technical Specifications.
i SE No.:      86-442 Source Document:       DCN 01343 Description of Change Draving change (913-001) to delete low oil temperature alarms on control          '
complex chiller crankcases to agree with as-built condition. (I&C Evaluation)
Summary l
I. No. Does not change the control design functions of the control complex vater chillers.                                                             >
II. No. See I above.
III. No. See I above.
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SE No.:                      86-443 Source Document:                            STI F41-034 Test Results Description of Change This safety evaluation was performed to evaluate operation at power without operable CRD guide tube strain gauges for prototype internals vibration testing.          FSAR Section 3.9.2.4. indicated that the guide tube vibration vould be monitored by strain gauges.during power operation of the reactor. Although the strain gauges were installed, they failed during Non-Nuclear Heatup.
General Electric evaluated the effects of the strain gauge failure on the vibration assessment of the CRD guide tubes and concluded that vibration amplitudes at povet will be about 10% of the acceptance criteria. This evaluation is based upon vibration testing at other comparible BWR/6 plants. In addition, during pre-operational testing, guide tube vibration was less than 10% of the acceptance criteria. Therefore, testing and operation at power can continue as planned.              (See also SE No. 86-282).
Summary I. No.               Based on the reference plant data and the preoperational testing results, the CRD guide tube vibration amplitudes at power vill also be about 10% of acceptance criteria.
II. No.                See I above.
III. No.                  See I above.
SE No.:                 86-444 Source Document:                      LL & J No. 15-019 Description of Change Temporary removal of fuel handling building unit heater (P55B0025G).
Summary I. No.                Is evaluated for in FSAR Section 9.4.10.3.
II. No.                Temporary removal of the building hea*.ing unit could not result in any accident or malfunction beyond those previously evaluated.
III. No.                The margin of safety is not reduced.
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SE No.:   86-445 Source Document:      FSAR CR No. 86-130                                                               j 0
Description'of Change FSAR change to reclassify dryvell vacuum breaker system as non ESP.
Summary                                                                                                j i
I. No. Design basis' for dryvell structure changed and the dryvell integrity was verified to be capable of withstanding maximum negative differential pressure. Furpose.of vacuum breakers as ESF is                               ;
therefore no long'er necessary.                                                             !
l II. No. The analysis in the FSAR bounds all scenarios.
III. No. The margin of safety is not reduced.
SE No.:   86-446                                                                                        i Source Document:      DCN 01352                                                                        i i
Description of Change Draving change (D302-772) to relocate tracer sample point used ta                                 ]
determine the reactor. steam' quality.    (Chemical Eng. Evaluation)                              i Summary                                                                                                .
i This change merely changes the location where the tracer sample is I. No.
drawn.
II. No.  "'his change only directs the people performing the tracer study where to draw the sample.
III. No. See I above.
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                                            - 230 -
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p                       t
                             .SE No.:     86-447                                                                                                 {
Source Document:      DCN 01352
                              . Description of Change l
Draving change (D302-772) to relocate tracer sample point used to                                             '
determine the reactor steam quality to the recirculation line.      (I&C Evaluation)-
Summary I. No. This change merely changes the location where the tracer sample is                                     '
drawn. It was originally shown to be drawn from the CRD sample                                      ,q point which serves no purpose.
II. No. This change only directs the people performing the tracer study as                                     1 to where to drav the sample.
III. No. Taking the tracer sample from the recirculation line is the correct location. The Technical Specifications are not affected.
SE No.:    86-448 Source Document:      DCN 01364 Description of Change                                                                                             ;
Draving change to shov that sheet metal blanks have been added to                                            !
unener31 zed Unit 2 systems to isolate them from the Units 1/2 plant                                         ;
vents (numerous drawings affected).                                                                           '
Summary I. No. The overall system function in the Unit 1 operational configuration has not changed.
II. No. See I above.
III. No. See I above.
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                            -SE No.:      86-449 Source Documents         ~SXI0001, Rev. O, TC 007 Description of Change i
j Evaluation of a change to " Generator and Power Transformer System Protective Relay Trip Tests" to correct instruction steps for testing        .
main generator out of step relays 21 and 78 and 1N41-K1 relay, which         :
enables generator protection when the generator
* is to be connected to the
                                  ,fgrid.
Summary I. No. This testing proves design features ot the plant and thus involves    !
no abnormal plant lineups.
II. No.      See I above.                                                          i III. No.       See I above.
SE No.:        86-450 Source Document:          DCP 86-620, Rev. O i
Description of Change Design change to install blanks at the discharge of the following valves:
2P54-F3410, 2P54-F3420 and 2P54-F3430 (CO2 Diesel Generator System for Unit 2).                                                                     l Summary I. No. Does not affect safe shutdown.                                        L II. NO. There are no potential initiating causes or threats to the plant.
III. No.      Only the administrative aspects of fire protection is in the          .
Technical Specifications.
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86-451.
SE No. r                                                                               '
Source Documentt            DCP 86-644A, Rev. 0                                             e     h o{
s' i 1 Description of Change                                                                      r ,g      ,q Kj Evaluation of the installation-of Hilti bolts in safety-related concrete.                   '''
Pertains to the design change to provide a metal storage cabinet.for
                                    , nuclear instrumentation in the Fuel Handling, Building.
Summary
                                  ~
I.'No.        Hilti bolts do not impair the integrity of the structural concrete.
II. No.        See I above.
III. No.         See I above.                                s SE No.:          86-452                               '
Source Documentt             NR-MHOS-1370, Rev. 2                                                           l Description of Change                                                                                       1 Evaluation of'use of torque switch settings above setpoint list setting                            }
for an emergency closed cooling valve (OP42F0255A).                                                l l
l Summary                                                                                                    ;
I. No.         Setting is within acceptable range and belov valve damage potential.
II. No.         See I above. The as-found setting is within the vendor's tolerance                        ;
i III. No.         See.I above.                                                                              ;
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SE No.:            86-453
    ,          Source Document-:                       NR-PPD?.-1861,'Rev. 1 Descriptlor: ofChangn1                              n, Evdluationof'useoftorqueswitchsettingabovesetpoint list setting for a valve (OG41-F0290) in the fuel pool cooling system.
                                     "q .
EU*2 .'l                  _
I.-No        Setting.is within acceptable, range and belov valve damage potential.
II. No. .See I aboN . The as-found set).ing is within the vendor's tolerance.
III. No.          See I above,'                                           .s
                                                   . ts             1 s                                                      ,
                                                                                        -                ,s
                                             ,          5 s
                                                                  !                               .s h 't
               '/                                                 $   .3 L2 No.:            86-454 1(R-MdQS-1819, Rev. 1 g ource Document:
S Dercr)ptionofCb,ag                                     ;
                                                                                                       )
is Evaluation of use ofptorque switch jettiogs different than setpoint list for dryvell vaNum rnlief vd suppr6ssion pool makeup valves 1M16-F0010A, 1H16-F0010Bdi1G4%F0040B.                          ,
S        1-
                                                         .,      s<1.
Summary                                                            ~
1
:~                                                  ,.
9
: 5. No.'      Set ting is ~vithin acceptable range ind belov valve darr. age pote:.'.ial.                                           l t                  N N                              5
                                     's II. No.        See I abcre. The as-founk set'.ing is within-the vendor's s, ,
                              ,'    tolerancy                       ,
w
                                                                              )                 ,
III .s .No ,                                                 ''
See I above.
                                                                                                                                                        'l s
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SE No.: 455 Source Document:       NR-MM05-1820, Rev. 1 Description of Change
!<        Evaluation of use of torque switch settings for Standby Lquid Control System valves 1C41F0001A&B, which'are not established in the Master        ,
i         Setpoint List. Acceptable function under accident conditions was           l
!         demonstrated by meeting acceptance criteria in applicable SVI.
Summary I. No. Setting is within acceptable range and belov valve damage potential.
1 l
II. No. The as-found setting is within the vendor's tolerance.
l   III. No. See above.
SE No.:     86-456 Source Document:       NR-MMOS-1836, Rev. 1 i
Description of Change Evaluation of use of torque switch settings which are below those required by the setpoint list for suppression pool makeup system (1G43F0030A&B', 1G43F0040A).
Summary I. No. Setting is within acceptable range and belov valve damage potential.
II. No. See I above. The as-found setting is within the vendor's tolerance.
III. No. See I above.
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                                              - 235 -
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SE No.:      86-457 Source Document:        NR-MMOS-1952, Rev. O Description of Change Evaluation of use of torque switch settings different from setpoint list for a liquid radvaste sump valve (lG61-F0150).                                                             !
Summery I. No. Setting is within acceptable range and belov valve damage potential.
II. No. See I above. The as-found setting is within the vendor's tolerance.
III. No. See I above.                                                                                         1 I
SE No.:      86-458 Source Document:         NR-HHOS-1953, Rev. 0 Description of Change Evaluation of use of torque switch settings above setpoint list for a combustible Gas Control System valve (1M51-F010B).
Summary I. No. Setting is within acceptable range and belov valve damage potential.
II. No. See I above. The as-found setting is within the vendor's tolerance.
III. No. See I above.
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                                               ~ 236 -                                                                 )

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SE No.:. 86-459                                                                                                           ,
Source Document:          NR-MMQS-1962, Rev. 0 Description of Change l
i l                            Evaluation of use of torque switch settings above setpoint list for an                                              j RHR valve (lE12-F026A).
                      . Summary I. No. Setting is within acceptable range and'belov' valve damage potential.
II. No. See I above. The as-found setting is within the vendor'.s tolcrance.
III. No. See I above.
SE No.:     86-460 Source Document:          NR-MM05-1888, Rev. O j
Description of Change Evaluation of use of torque switch settings above setpoint list for a Liquid Radvaste Sump valve (lG61-F0165).
Summary I. No. Setting is within allovable range and belov valve damage potential.
II. No. See I above.          The as-found setting is within the vendor's tolerance.                                  !
III. No. See I above.
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I SE No.:     86-461 Source Document:       .NR-MH05-1958, Rev. 1
                                                                                                   . .i Description of Change i
Evaluation of use of torque switch settings above setpoint list for ESV        l valves (1P45F0130A6B).
Summary I. No. Setting is within tolerance and provides acceptable function.
II. No. See I above. This change vill not effect HOV operability.
III. No. See I above.
SE No.:      86-462 Source Document:        NR-MHOS-1889, Rev. O Description _of Change Evaluation of use of torque switch settings above setpoint list for a RCIC valve (1E51-F0068).
Summary I. No. Setting is within acceptable range and belov valve damage potential.
II. No. See I above.
III. No. See I above.
                                                          - 238 -
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SE No.:      86-463 Source Document:       ~NR-MHOS-1930, Rev. 1.
(
Description of Change Evaluation of. use of torque switch settings above setpoint list settings                ,
for a KVCU valve (1G33F0040).                                                            (
1 Summary                                                                                        j l
Setting is within acceptable range within tolerance, and belov valve I. No.
damage potential.                                                                 ]t II. No. See I above.
III. No. See I above.
                     'SE'No.:     86-464 Source Document:        NR-MMQS-1821,.Rev. 1 Description of Change                                                                        r Evaluation of omission of a device to limit maximum torque switch settings (limiter plates) for designated' valves (1H16F0010A, 1H16F0010B and 1C41F0001B) in-dryvell vacuum relief and SLC systems.
Summary
: 1. No. Proper valve function does not depend on the limiter plates.
II. No. See I above.
III. No. See I above.                                                                    i i
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                                                                - 239 -

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i SE No._:     86-465-Source Document:-       NR-MMOS-1890, Rev. O Description of Change Evaluation of use of torque switch settings different from setpoint list settings for a RCIC valve (lE51-F0077).
Summary I. No. Does not affect the valve's operability and does not exceed the vendors allovable, i
II.-No. 'See I above.
                                                                                                          ~
III. No. See I above.
i SE No.:      86-466 Source Document:         NR-MMOS-1966, Rev. O Description of Change Evaluation of use of closing torque switch settings above setpoint list l
settings for various safety-related valves in the Nuclear Boiler System,
!                             RHR System, Liquid Radvaste Disposal System, Liquid Radvaste Sumps System, and the Combustible Gas Control System.
Summary I. No. Setting is in conservative direction for closing which is the safety function for' these Containment Isolation MOV's.
II. Ne. See I above. The as-found setting is within the vendor's tolerance.
III. No. See I above.
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                      ' SE No.:    86-467                                                               ]
Sourci Document:        HFI 16-771 Description of Change Evaluation of temporary use of drip pan attached to valve in the feedvater system (IN27-F560A).
Summary I. No. Drip pan is designed to survive safe shutdown earthquake without adverse interactions with other safety-related structures / systems / equipment.
II. No. Refer to I above.
III. No. Refer to I above.
i SE No.:     86-468 Source' Document:        NR-HHOS-1966, Rev. 1                                   !
1 Description of Change Evaluation of use of closing torque switch settings above setpoint list settings for a Nuclear Boiler System valve (1B21F0067A).
Summary i
I. No. Does not affect the valve's operability.
II. No. See I above.
III. No. See I above.
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SE No. ' 86-469                                                                  j Source Document:         NR-MMQS-1981, Rev. O Description of Change Evaluation of omission of a device to limit maximum torque svitch setting (limiter plate) for RCIC steam supply valve (1E51-F0063).
Summary I. No. Proper valve function does not depend on the limiter plate.
II. No. See I above.
                             'III. No.      See I above, n
1SE No.:      86 470 Source Document:         DCN 1357                                                i Description of Change Drawing change (D302-613) to identify ERIS point P43EC009 on P&ID to      '
reflect as-built configuration.
Summary                                                                           ,
i I. No.. This ERIS point monitors the status of valve P43-F410 (Nuclear         !
Closed Cooling System) and makes the overal~ system more reliable   !
and safe. This is a drawing update only.                            1 II. No. See I above.
i III. No. This change updates P&ID to identify ERIS point which is already     l as-built on system elementary and does not affect the Technical     l Specifications.                                                     !
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SE No.:     86 471
      -Source Document:         DCN 1367 Description of Change Drawing change to revise Off-Cas System P&ID D302-752 to remove reference to Note 2 for valve F632.
Summary i
I. No. This is a P&ID drawing change for clarification and does not affect equipment function or accident consequence.
II. No. The 1N64F632 valve vill close on high radiation and until levels of ;
J radiation are reduced. The F632 valve vill not open manually as stated by Note 2.                                                     i III. No. See I above, i
SE No.:     86-472 Source Document:        FSAR CR Ne. 36-124                                      ;
Description of Change Evaluation of FSAR change to revise drawings 302-6c1 and 602 which involve a deletion of a Reactor Recirculation System (B33) I&C loop.
Summary I. No. The revisions to the drawings do not affect the safety evaluations for B33 in the FSAR.
II   No. The deletion of the I6C loop function does not af fect B33 system safety and reliability.
III. No. The margin of safety is not reduced.                                 .
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i SE No.:        86-475' Source Document:         DCN 01262 Description of Change Drawing change (D302-691) to allow for the addition of information to the   i SLCS System P&ID to show the existing pump start permissive interlock       l between Valve 1C41F0031 and the SLCS injection pumps.                       '
Summary I. No. This change adds information to the P&ID concerning an already j
existing interlock.
II. No. See I above.
III. No. See I above.
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SE No.:     86-476 Source Document:       DCN 01338
                                                                                                          /
Description of Change Drawing change to update elementary diagram and inter connection drawings   l i
on viring configuration; viremarks, addition end deletion of jumpers and references to the drawing to agree with elementary diagram and as-built condition (Radvaste System).                                                l Summary I. No. The updating of viring configuration to agree with the system elementary drawing does not increase the consequences of an accident !
or malfunction of equipment.
II. No. The possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR is not created.
III. No. The margin of safety is not reduced.
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SE No.:       86-477 Source Document:               DCN 01212 Description of Change Draving change (D302-691) to add electrical components to the SLCS System P61D.
1
!           - Summary I. No. This change adds information regarding existing installed electrical components to the SLCS System P6ID and does not alter system design.
II. No. See I above.
             -III. No. See I above.
i SE No.:       86-478 Source Document:              NR-MM05-1949 Description of Change Evaluation of torque switch setpoints for 1C11F0083 and 1N27F0740 which are different from the Master Setpoint List (CRD and Feedvater Systems respectively).
Summary I. No. The setpoint (1C11F0083) is within the allowable range and valve closure has been ensured via LLRT's (1N27F0740).
II. No. The torque switch setpoints for 1C11F0083 and 1N27F0740 are within acceptable limits.
III. No.      1011F0083 is not in the Technical Specifications. 1N27F0740 is a containment isolation valve and will go 97%-99% clo<ed on limit    ,
switch befo.e    t the torque switch is necessary.
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l SE No.:         86-479
                . Source Document:            SCR 1-86-1490                                            ,
                ' Description of Change Setpoint change to revise the torque switch setpoints for 1H51F0020B (Combustible Gas control System).
Summary I. No. Through signature analysis testing (H0 VATS) of this valve and calculation, the required output of the MOV is produced at a lover setpoint than the vendor allowable.
II..No.         See I above.                                                       ;
III. No.        The operability of the MOV is not described in the Technical Specifications.
SE No.:          86 480 Source Document:            SCR 1-86-1491 Description of Change Setpoint change to revise the torque switch setpoints for 1H51F0020A (Combustible' Gas Control System).
Summary I. No. Through signature analysis testing (H0 VATS) of this valve and calculation, the required output of the MOV is produced at a lover setpoint than the vendor allowable.                                1 II. No.         See I above.
III. No.         The operability of the MOV is not described in the Technical Specifications.
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i SE No.: 482 Source Document:       DCP 86-193, Rev. 0 1
Description of Change Evaluation of the installation of Hilti bolts in safety-related concrete.      !
Pertains to the design change for the permanent installation and               i electrical viring for the radvaste resin addition hoist in the Radvaste Room.
Summary i
I. No. Hilti bolts are designed such that they do not impair the structural integrity of the structure.
II. No. See I above.                                                             !
l III. No. The integrity of the concrete is not impaired.                         i s
SE No.:    86-483 Source Document:       DCP 86-568F, Rev. O Description of Change Evaluation of the installation of Hilti bolts in safety-related concrete and attachment to embedded plates. Pertains to the design change on the installation of nonsafety pipe supports for the CRD Decontamination and Rebuilding System CRD flush tank piping.
j Summary
                                                                                                        .j I. No. Hilti bolts do not impair the integrity of the concrete. Additional loads on the embedded plates are negligible when compared to the        ,
i design capacity of the embedded plate.
II. No. See I above.
III. No. See I above.
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SE No.:       86-484-Source Document           NR-MMON-556, Rev. 1 Description of Change
                      . Evaluation of. torque switch setting on valves 1B21-F005, 1B33-F067A and 1833-F067B vhich is not in accordance with the setpoint list.
l Summary I. No. These valves are not required for safe shutdown of the reactor.       i i
II. No. See I above.                                                        1 l
III. No.      See I above.
r SE No.:       86-485.
Source Document:          DCP 85-374, Rev. O Description of Change Design change to redistribute load from MCC F1C08 to spare breaker F1C11.
Summary These nonsafety loads are only used in the event of a LOOP. The I. No.
redistribution of load vill increase breaker reliability to ensure they can operate as designed.
II. No. The redistribution of load from one breaker to another does not increase the possibility for malfunction of equipment other than   l those already evaluated by the FSAR.
III. No.      This change redistributes load to allow for more reliable breaker operation without unnecessary tripping.                            I l
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j-                                                                                                                  1 L                            .SE No.:           86-486
                              ' Source Documents           DCP 86-842, Rev. O Description of Change                                                          ]
I Design change to complete termination of safety circuit shield wires f '-                                       (ERIS system).
Summary l
I. No. Completes intended plant design.
                                    'II. No. The' termination of the shield wires improves the quality of ERIS signal and therefore reduces the possibility of a malfunction.
III. No. Not discussed in the Technical Specifications.                     l
                                'SE No.:        86-488 l                                   Source Document:       DCP 86-652, Rev. O Description of Change Design change pertaining to a computer upgrade of the fire and security computer (P56). (Fire Protection Evaluation)
Summary I No. The items utilized in this change meet all the requirements in Chapter 4 of NFPA 720.
II. No. 'The change does not affect the program or functions of systems required for detection of a design basis fire.
III. No. Does not involve the Technical Specifications.
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SE No.:                       86-489 Source Document:                         DCP 86-652, Rev. 0 Description of Change-l                                                                                                           4 l
Design change pertaining to a computer upgrade of the fire and. security computer (P36)         (Security / Electrical Evaluation)                       !
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l       Summary I. No.                    The P56. system is nonsafety. A malfunction vould not affect safety equipment.
I II . - No.                  See I above. The computer operation does not change, only_
electrical components are affected.
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III. No.                      This upgrade does not affect the margin of safety of any Technical  1
                                     . Specification.
SE No.:                       86-490 Source' Document:                        DCN 1396 Description of Change Drawing change to revise the Turbine Building Ventilation System diagram to show ductvork to panels 1N64-P001 and P002 (See also SE No. 86-072).
i Summary I. No.                    The accident analysis as described in the FSAR is not affected.      l II. No.                     Malfunctions of a different type vill not be created.              !
III. No.                      The margin of safety has not been reduced.
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SE No. 491                                                                     ;
Source Document:
DCN 1399                                                   l Description of Change                                                               f i
Drawing, change to P&ID's and isometrics to show piping during plant operation with the temporary startup strainers removed.
Summary I. No. Original design and integrity is not compromised. This editorial change reflects the plant operating configuration.
                                       ~I       o           a ov SE No.:      86-492 Source Documents'        DCN 1405 Description of Change Drawing change to relocate electrical signals for ERIS point P45EA009 and 1C61-R033B flow indicator from the input to the output of square root     - ,
extractor 1E12-K611B.                                                        '
4 Summary 4
I. No.' The P6ID is being changed to agree with field conditions and the interconnection diagrams. The readout functions in the Control' Room, ERIS and the Remote Shutdown Panel are not changed.                ,
II. No. See I above.
III. No. See I above.
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1 SE No.:                    86 493                                                                l Source Document:                      DCN 1407                                                   l l
Description of Change-                                                                          i f
Drawing change _to update one line drawings 206-017, 018 and 051 to        l reflect fuse size and/or fuse class per various as-built packages.       j Summary                                                                                        ?
I. No. This'is a drawing change only. No functional changes are involved. l II. No.              See I above.
1 III. No.                    See I above.                                                        J l
SE No.:                     86-494 Source Document:                      TER 026-01 to STI-HU-201                                 ,
Description of Change                                                                            <
Evaluation of the deferral of testing of Off-Gas Vault Refrigeration System to TC 6 (Test Condition 6) from TC Heatup.
Summary I. No. The design and operation is not affected by testing at TC 6.
II. No.        See I above. No change is made to the design or operation.
III. No.                 The margin of safety is not reduced. The performance of this test in TC Heatup is not covered in the bases for any Technical Specification,                                                     y 1
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l SE No.:       86-495 L                        Source Document:          TXI-011, Rev. O Description of Change Evaluation of temporary instruction to perform cold shutdown with RPV level below the feedvater spargers.
i Summary I. No. There is no change to the plant that vill increase the probability of an occurrence of an accident previously evaluated in the FSAR.
i II. No. All equipment involved vill perform their design function.                      j III. No. The instruction provides guidance to initiate HPCS if water level                )
decreases to 50" above TAF, LPCI and LPCS vill get an auto                      j initiation on low level 1, and alternate methods of injecting water             j vill be available.
i SE No.:       86-496 Source Decument:          Info. Tags 26-240 and 26-241 Description of Change Evaluation of valves 2P46-F501 and 2P46-F502 (Turbine Building Chilled Vater Sys tem, TBCV) which are to be closed and red tagged .vith information tags identifying them as Unit 1/2 boundaries. This vill isolate the Two-Bed Demineralized System makeup water from the non operating Unit.2 TBCW System.
Summary I. No. The 2P46 System is not required for Unit 1 operation.
II. No. See I above.
III. No.       See I above.
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SE No.:     86-497 Source' Document       OCP 861615, Rev. 0
  . Description of Change Design change.for the installation of sound barriers in the Intermediate                                        .
Building elevation 574' 10" requiring attachments to safety-related                                             !
embedded plates. (Civil / Structural Evaluation)
I i  Summary I. No. The additional loads do not overstress the embedded plate and the structural integrity of the. building is not compromised.
L See I abova.
II. No.
  'III. No. There is no. affect on the Technical Specifications.
SE No.:     86-498 Source Document:      DCP 86-0615, Rev. O Description of Change Evaluation of sound barrier material (for combustibility) that is to be used to help isolate the noise of the Containment Vessel Chilled Vater System chillers from the tool storage and tool decontamination rooms.
(Fire Protection Evaluation)
Summary I. No. There is no safe shutdown equipment in this area. There is no increase in fire potential.                                                                              :
II. No. The material does not present any increase in severity or probability of fire as previously analyzed in the FSAR.
III. No. There is no affect on the Technical Specifications.                                                         ;
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                                             - 254 -

SE No.:            86-499-Source Document:              DCP 86-176, Rev. 1                                                            ;
Description of Change I
Design change to allov for the addition of a vent valve for hydrostatic                           j testing and clarification of the scope of hydrotesting for the industrial                       i I
vaste lagoon decant line.
Summary I. No. The decant line serves no safety function. The addition of the vent valve vill not affect the operation of this system, nor any other plant system.
      'II. No.           See I above.
III. No.           The industrial vaste lagoon decant function is not described in the                      I Technical Specification bases.
I SE No.:- 86-500 Source Document:              DCP 86-866, Rev. O Description of Change Design change to replace the Bailey Alarm Cards (MPL #0G50K805A&B, Liquid Radvaste Disposal System) with a R.I.S. calibrated trip alarm unit with remote potentiometer to provide a manually adjustable high flow trip alarm to ensure liquid effluents remain within 10CFR20 limits.
Summary         <                                                                                            j l
I. No. The probability of occurrence or the consequences of an accident or                      j malfunction of equipment important to safety is not increased.                          {
II. No. The possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR is not created.
III. No.         The margin of safety is not reduced.
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1 SE No.:          86-501 Source Document:           DCP 86-878, Rev. O Description of Change Design change to allow for the addition of pressure reducing valves in the Reactor Plant Sampling System.
Summary I. No. The addition of the pressure reducing valves ensures that the system components do not fail, therefore reducing the possibility of leaking. vater inside containment.
1 II. No.      See I above.
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                            'III. No.          See I above.. This change reduces the possibility of a leak which vould be unidentified leakage.
SE No.:         86-502 Source Document:          SCR 1-86-1467 Description of Change
                                        .Setpoint changa to revise the torque switch setpoints for 1E51F0022 (RCIC System).
Summary I. No. At the vendor supplied setpoints the MOV is inoperable. The revised setpoints provide adequate output to ensure the operability of the HOV.
II. No. See I above.
III. No.        See I above. The ma rgin of safety is not reduced.
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!                   SE No.:     86-503                                                                                                                           i Source Document:       DCP 86-162, Rev. O l-                  Description of Change 4
Design change to relocate flow element 1N33-N300 (Steam Seal System) into                                                              ,
the steam seal drain line pipe. The flov element and thermevell in                                                                    l 3" diameter drain line shall be interchanged.
1 i                   Summary I. No. The flow element and thermovell locations are~just interchanged.
The Steam Seal System is nonsafety.
II. No. See I above.                                                                                                                     ,!
III. No. See I above.
<                   SE No.:      86-504 l'                  Source Document:       DCP 86-882, Rev. O Description of Change                                                                                                                        i Design change to add a permanent ladder to provide access to dampers 1M14-F561 and 1M14-F567 (Containment Vessel and Dryvell Purge System).                                                               l t
The ladder attaches to the containment vessel.
Summary I. No. The actual loads applied to the attachment pads are less than the acceptable limits.
II. No. The ladder is adequately supported.
III. No. See I above. Does not reduce the margin of safety.
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                    -                                                                                             4 SE'No.:    86-505 Source Document:      DCP 86-666A, Rev. O Description of Change Evaluation of the installation of Hilti bolts in safety-related concrete.
                       -Pertains to the design change to provide differential controls for the Containment and Dryvell Purge System. (Civil / Structural Evaluation)                     ;
Summary' I. No. Hilti Kvik bolts do not impair the structural integrity of the concrete structure,                                                                  j II. No. See I above.
III. No. See'I above.
l                 SE No.:    86-506                                                                                !
SOURCE DOCUMENT:      DCP 86-666A, Rev. 0                                                       ,
Description of Change Design change to allow for differential pressure control for containment /dryvell supply air train A&B (Containment Vessel and Dryvell Purge System - Electrical Installation).    (Electrical Evaluation)
Summary I. No. The present containment /dryvell supply and exhaust fan control configurations measure fan flov (CFM). Each control system compares actual fan flov vith a preset value and automatically adjusts the fan's variable inlet vanes such that each fan volume matches its preset value. This control logic is unsatisfactory because hysteresis and dead band (inherent in the equipment) prevent supply and exhaust fan volumes from matching exactly. This mismatch results in differential pressures across the containment due to flow mismatch.
This design change shifts the control logic from volume control to pressure control... containment pressure is sensed and is used to control supply fan volume to maintain containment pressure within a preset range.                                                                           )
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                                                          - 258 -
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SE No.:  86-506 (Continued)
                                                                                                                      \
The probability of a control system failure of the new proposed                                           j design is no greater than the probability of a control system failure of the present design in use nov. This is because equipment of the same quality and design is proposed to be installed for the design change as that which is presently installed. The consequence of an accident or malfunction is not increased, because the affect of control system failure in either design is exactly the same... failure of the fans to deliver the proper volume of air. The failure / malfunction vill result in a differential pressure across the containment or dryvell vall which may result in containment (or dryvell) vacuum breaker operation. Two worst case failures were                                      1 analyzed for this design change as follows:
: 1) Complete failure of the supply fan (no supply flow) with exhaust fan at maximum volume. This configuration vill produce a vacuum in containment. Containment to outside differential                                    1 pressure could reach 0.40 psid if the vacuum breakers are                                         I assumed not to open. This pressure is not sufficient to challenge the .8 psig negative design pressure of the containment building.
: 2) Complete failure of exhaust fan (no exhaust flov) with supply fan at maximum volume. This configuration results in a
                    +.21 psi differential between containment and outside.
Both of the worst case failures listed above fall within the envelope of accident conditions that the FSAR uses for accident                                        -
response analysis in the containment functional evaluation                                           -
(FSAR 6.2.1.1.3.3.), and Mark III containment system issues                                            j (Humphrey issue 8.4, 10.2 & 20). Therefore, the consequence of an                                         j accident or malfunction previously evaluated in the FSAR is not                                           j increased by this design change.                                                                          '
II. No. As stated in Item I, consequences of gross failure of the new design is the same as the old design and vill result in containment or dryvell vacuum breaker (CVB) operation. However, the new design                                           ;
vill prevent numerous inadvertent openings of CVBs during normal                                         )
operation of the M14 vent and purge system by controlling and maintaining containment pressure negative but below CVB opening set                                       j point. Therefore, the possibility for an accident or malfunction of                                      i a different type than any evaluated previously in the FSAR is not created.                                                                                                  I i
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                                          - 259 -
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l SE No.:    86-506 (Continued)
III. No. Opening of the. containment and dryvell vacuum breakers have been evaluated and addressed in Technical Specification Section 3.6.5.1 and 3.6.5.3 (pages 3/4 6-42 & 3/4 6-46). Failure of the differential pressure control does not reduce the margin of safety specified by the Technical Specifications, because a vorst case failure of the fan control system as discussed in Items I & II above does not approach the margin of safety established by the envelope of accident conditions discussed in the FSAF.                         1
                                .SE No.:    86-507 Source Document:      PEI D23-2, Rev. 1, TCN No. 4 Description of Change Evaluation of a change to a Plant Emergency Instruction, on Dryvell and Containment Pressure Control, to correct a step by step direction necessary to open containment spray valves when required for containment venting. Specifics that the FHB HVAC exhaust fan vice the FHB ventilation system, be running.
Summary-I. No. Actions taken are in accordance with the Perry Specific Technical Guidelines.
II. No. See I above.
III. No. This change does not-affect any Technical Specifications margin of     {
safety.
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SE No.:      86-508 Source Document:          ONI-C71, Rev. 1, TCN-04 Description of' Change Evaluation of a change to an operating instruction (Reactor Protection System) pertaining to the closure of inboard MSIVs to limit cooldown rate to less than 100*F in any one hour period following a reactor scram.
Summary I . No . - FSAR Section 15.1.3, Pressure Regulator Failure - Open, is an analyzed transient that is similar to the one caused by shutting the HSIVs following a reactor scram. The differences lie in the timing                                   ,
of MISV closure (post-scram vs. pre-scram) and the initiating event                                  l (operator;nction vs. lov main steam line pressure). In the case of                                  l the operator closing the HSIVs pcst-scram to limit cooldown rate, e               the decay heat loading on the containment vill be significantly lower than in the analyzed transient; therefore, the numbcr of cyclra required of the SRVs to remove the decay heat from the RPV and the final temperature of the suppression pool vill be lover.
Af ter closing the HSIVs, the operator is directed to proceed to the same instruction for cooldown with MSIVs closed as he would use had the HSIVs automatically closed, and from that point on, the actions vill follow those for Pressure Regulator Failure - Open. The probability of or consequences of an accident or malfunction of equipment are therefore not increased beyond that which was analyzed for in the FSAR.
II. No. As stated above, the transient introduced by closing the HSIVs post-scram is similar to the transient caused by a Pressure Regulator Fo11ure - Open and does not introduce the possibility of                                  ;
an accident or malfunction that has not already been analyzed for in                                ;
the FSAR.
III. No.      Since the reactor is shutdown with control rods prior to closing the                               ,
MSIVs, the peak neutron flux and peak RPV pressure reached vill be significantly lover than that reached when the HSIVs are the initiating event by going closed at power. Therefore, the margins of safety to MCPR and RPV pressure limits vill be significantly greater for this transient than for other MSIV closures. No other safety margins are<affected.
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SE No.:            86-509 Source Document:              DCN 1397, Rev. O Description of Change Drawing change (to 302-141) to shor corre:t operation of MCV F030'vith MCV F040, PPV F035 and PPV F150 (Steam Seal System N33).
Summary I. No. The drawing changes do not affect the operation of the system, therefore N33 vill operate as designed. Safety systems are not    i 1
affected.
See I above.
II. No.                                                                     !
III. No.            See I above. The N33 system is not described in the Technical Specifications.
I SE No.:            86-510 Source Document:'             DCN 0751 Description of Change Drawing change to the Nuclear Boiler System P&ID's to reflect the as-built configuration and to agree with the latest revision of the GE P6ID's.   (Mechanical Evaluation)
Summary I. No. This change reflects the as-built condition of the plant.
II. No. See I above.
III. No.         The margin of safety is not reduced,                               i 1
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l SE No.:     86-511 Source Document:       DCN 0751 i
Description of Change-Draving change to the Nuclear Boiler System (B21) P&ID's to reflect the as-built configuration and to agree with the latest revision of the GE                                      1 P&ID's.    (ILC Evaluation)                                                                                 1 Summary i
I. No. This change has no impact on system ope.rability requirements.
II. No. This change does not add any new plant design configurations                                         1 tmportant to safety which are not already evaluated in the FSAR.                                     l III. No. .This change has no impact on setpoint requirements / design features for systems described in the Technical Specifications.                                               ;
i SE No.:     86-513 Source Document:       HFI 16-672                                                                                )
Description of Change                                                                                            l Evaluation for temporary installation of tygon tubing for the Steam Bypass System chest drain to radvaste, to support testing.
l Summary                                                                                                          j I. No. .The dre.in line is still capable of draining to radvaste.
II. No. See I above,                                                                                         i
  .III. No. See I above.
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                                          - 263 -
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SE No.:    86-514                                                                )
bource Document:       DCN 1427 Description of Change               ,
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Drawing change to update the drawing (302-791) to the actual MPL tagging   j in the field. This change.also makes HPL tagging similar'on    "A" and "B" {
I pump circuits (Emergency Service Vater System).
Summary I. No. This is an editorial change to a drawing.
1 II. No. See I above.                                                         {
                                                                                            }
III. No. See I above.                                                         i l
l SE No.:     86-516 ,                                                             ,
Source Documents'      FSAR CR 86-138                                            )
Description of Change Evaluation of FSAR change to clarify that only two (of three) Nuclear     l Closed Cooling (NCC) System pumps are powered from a Unit 1 diesel backed  j source.
l Summary                                                                         j I. No. The NCC System can meet the design heat loads with two pumps.
I II. No. See I above.
l III. No. The NCC pumps are not covered by the Technical Specifications.
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3 SE No.:     86-517 Source Document:       SCR's 1-86-1048, 1049, 1050 and 1051
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Description of Change Setpoint change for annulus spa ~ce differential pressure (1M15-N015A/B and 1H15-N017A/B) to be more conservative.
Summary I. No'  . These devi'es c   are used for alarming only.
II. No. There is no' interlock associated with this equipment.
III. No. The Technical Specifications are uneffected by this nonsafety alarm setpoint change.                                                                  .
SE No.:     86-518 Source Document:       PAP-1104, TCN 001 to Rev. 4 Description of Change This safety evaluation was performed to evaluate changing the definition j                               of Test Condition 1 (TC-1) by revising the power boundaries from 5 to 20%
thermal power, to 5 to 32% thermal pover.
Summary                                                                                       l
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I. No. Operation of the plant to 32% thermal power does not involve                      ;
operation of the plant or equipment outside the envelope covered by               ;
the accident analysis in the FSAR. The APRM hi flux setpoint vill                 !
be set at f40% to ensure over power protection.
II. No. See I above.
III. No. Technical Specifications are not affected.
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i SE No.:     86-519 L                                                      Source Document:       DCN 1380 Description of Change l
Draving' change to add ERIS tap' points to the 302-672 drawing.
Summary I. No. This change adds to the P&ID existing ERIS tap points and is a drawing change which is in agreement with as-built conditions on B208-046. No physic'al work is being performed in the field.
l II. No. See l'above.
l-III. No. See I above.
SE No.:     86-520                                                                !
DCP 86-891, Rev. 0                                       'l Source Document:
Description of Change                                                                 .
                                                             -Design change to install a concrete pad and fencing, adjacent to Unit #1   ]
cooling tower,' for storage of concrete radvaste casks. See also           i SE 86-521. (Civil / Structural Evaluation)                                 {
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Summary                                                                            l i
I. No. This pad (slab) in the yard area northwest of the Unit #1 cooling     I
        ,                                                           tower does not increase the possibility of an accident or            j malfunction.
II. No. The slab design is adequate for the imposed loads.                     l III. No. The addition of this structural item does not reduce the margin of safety for any Technical Specification.                                    '
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i SE No.:       86 -521                                                              ,
Source Document:         DCP-891, Rev. 0                                           l Description of Change Design change to install a. concrete pad and fencing, adjacent to the Unit #1 cooling tower, for storage of concrete radvaste casks (solid l                            radvaste disposal). (Engineering Evaluation)                                ;
I Summary I. No.. There is no effect on equipment important to safety.
I II. No. Guidelines for this type of storage were outlined in NRC Generic Letter 81-38. This storage area (including the casks) meet the       l intent of Generic Letter 81-38.                                     j III. No. The margin of safety is not reduced. The site boundary dose is within acceptable limits of Reg. Guides and Regulations.
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SE No.:       86-522 Source Document:         DCP 86-291, Rev. 0
                     ' Description of Change Design change to add doors IB310, 311, 312, 313, CC607 and CC704 to the plant security system. This is necessary to allow security to adjust.      I vital area boundaries in the Intermediate Bldg. and the Control Complex.   !
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                      -Summary i
I. No. This change does not involve equipment associated with the safe operation of the plant.
II. No.      See I above.
III. No.      The security system is not in the Technical Specifications.
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          .SE No.:         86-523 Source Document:            DCP 86-227, Rev. O Description of Change Design change to provide separate flow paths for OG50-C007A/B seal water leak-off an6 neal area drain line. This is to be done by piping leak-off into the equipu>nt drain stand pipe, to avoid backup into the seal area drain.
Summary I. No. This change does not modify the processing goal of the LRW system and does not alter previously evaluated FSAR considerations.
II. No. See I'above.
III. No.         The process paths vill remain as defined. Therefore all margins of      i safety for radvaste releases as defined in the Technical Specifications vill remain as defined.
SE No.:          86-524                                                                 i Source Document:            SCR l-86-1502 Description of Change Setpoint change to remove device 81, over-frequency relay (lR2200819) from the Master Setpoint List.      (Electrical Evaluation) i Summary                                                                                4 I. No. This relay was physically removed from Division III switchgear         '
during the construction phase. Removal of this relay does not cause the electrical portions of the !!PCS system to operate dif ferently than described in the FSAR.                                           l II. No. See I above.
Ill. No.      This relay is not in the Technical Specifications.
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                         , SE'No.:      86-525 Source Document:        SCR 1-86-1502 Description of Change Setpoint change to remove Device 81 Relay (1R2200319) from the Master Setpoint List.     (Mechanical' Evaluation)
Summary I. No. -Removal of the HPCS over-frequency relay vill not cause system overpressurization, due to over-frequency in excess of ASHE Code requirements.                     ,
II. No. The removal of the over-frequency relay does not cause the HPCS      -;
system to exceed any of its mechanical design limits.                1 III. No. HPCS over-frequency protection is tot discussed in the Technical Specification Bases.
SE No.:      86-526 Source Document         DCN 1390, Rev. O Description of Change Drawing change to remove Device 81 Relay (1R2200819) from the Electrical Single Line Drawing (D-206-018). (Electrical Evaluation)
Summary I. No. This relay was physically removed from the Division III switchgear during the construction phases. The device was inadvertently left on the single line drawing when this design change was made,         l Removal of this relay does not cause the electrical portions of the HPCS system to operate differently than described in the FSAR.       ,
l II. No. See I above,                                                         t III. No. This relay is not discussed in the Technical Specifications.
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    - SE No.:   86-527 Source Document:       DCN 1390, Rev. O l
Description of Change Drawing change to remove the HPCS over-frequency protection relay from the single line drawing (D-206-018).     (Mechanical Evaluation)                                                           l
    . Summary                                                                                                                         j i
I. No. Removal of the HPCS over-frequency relay vill not cause system                                                     j overpressurization, due to over-frequency in excess of ASME Code                                                    j requirements.                                                                                                        l II. No. See I above.
III. No. HPCS over-frequency protection is not discussed in the Technical                                                   '
Specification Bases.
l SE No.:    86-528                                                                                                             I Source Document:      STI C91-013, Rev. 2 Description of Change Evaluation of the performance of selected sections of the process Computer. Dynamic System Test Case (DSTC) in Test Condition 1 in addition to Test Conditions 2,3,5 and 6.
Summary I. No. The maximum permitted power level authorized for Test Condition 1 is less than that of Test Condition 2.
II. No. See I above.
III. No. The margin of safety is not reduced.
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SE No.:    86-529 Source Documents"     STI N27-023A Description of Change I
Evaluation of deferral of Start-Up Test Instruction N27-023A (Feedvater                         l System) from Test Condition Heatup to Test Condition 1, which differs                         i from FSAR Table 14.2-2.
Summary l
I. No. This test was included in FSAR Table 14.2-2 at TC-HU so that testing                       I could be done at that test condition if practical. However, system                     !
operation during TC-HU shoved that testing would be better performed                       {
at TC-1. There is no requirement to perform this test at TC-HU.
II. No. See I above.
                                 .'III. No. The margin of safety is not reduced.
1 SE No.:    86-530 Source Document:      TXI-0013, Rev. O i
Description of Change Evaluation of temporary instruction to perform the main turbine roll and generator synchronization (at 5% license restriction).
Summary                                                                                             I I. No. There is no' deviation from the assumptions of the FSAR.                                 f II. No. The plant systems / equipment that are bypassed, are not required to be placed into service until greater than 5% reactor power.
L                                 III. No. The margin of safety is not reduced.
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l SE No.:            86-531 Source Document:               DCP 86-657, Rev.' 0 Description of Change Design change to allow for the installation of isolation valves for the pressure indicators located on the diesel generator lube oil filters.
Summary I. No.          The pressure indicators are safety-related passive components. If the isolation valves are inadvertently closed, the function of the         !
Jube oil system would not be affected.
II. No.          See I above.                                                               j III. No.           The margin of' safety is not reduced.
SE No.:            86-532 Source Document                DCP 86-1006, Rev. O i
Description of Change                                                                         j Design change to add sliding link terminal blocks and reviring in panels    <
11113P691, P692, P693 and P694 to improve testing performance and personnel safety during performance of SVI's B21-T0072A, B, C and D (Nuclear Boiler System).
Summary I. No.          Each component is qualified as Class 1E. The design change under       !
evaluation vill not reduce the overall reliability of the               '!
safety-related system relative to performing its safety function.         I II. No.          See I above. The use of sliding link terminal blocks is a positive option in lieu of lifting leads and jumpers.                              ;
III. No.           This design change does not af fect the scope of the Technical Specifications relative to a potential reduction in safety.
Conversely, this design change enhances the practical aspects and parameters required for testability of systems / components resulting in increased margins of safety.
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l SE No.:                       86-533 Source Document:                                       FSAR CR 86-141 i
Description of Change                                                                                q Evaluation of a FSAR change to clarify that prefilters are to be "DOP" tested in place only at initial installation. The prefilter cannot be i
D0P tested in place because of possible contamination of the charcoal L                                .vith the DOP gas.
Summary 1
I. No.                The probability of occurrence or the consequences of an accident or    I malfunction of equipment important to safety is not increased.
II. No.                     The prefilter vill still perform as designed.                        h
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III. No.                      The margin of safety is not reduced. This change only clarifies DOP testing and vill not increase or affect Radvaste Treatment Exhaust. i I
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              'SE No.:                       86-534                                                                 i i
Source Document:                                      DCN 1458 Description of Change
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;                                  Drawing change to correct valve MPL labeling of 1P21-F951A and 1P21-F951B on D-302-171.
Summary                                                                                             l I. No.              Editorial change with no impact on safety systems.
II. No.                    Editorial change to nonsafety drawing.
III. No.                      See I above,                                                            i l,
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          -SE No._:                       86-535 Source Document:~                         DCP 86-700, Rev. O Description of Change.                                                                                                    ;
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Design change to replace existing 1/4" sample lines ~for P20N050A/B, P20N135 and P20N250 (Makeup Water Retreatment System) with 1/2" lines.
l         ISummary I           .
I. No.         No safety related equipment is impacted by this design change.                           ]
l II. No.                  See I above.                                                                             {
l III. No.                       The Hakeup Vater Retreatment System is not addressed in the                              4 Technical Specifications.                                                                l 1
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