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| {{#Wiki_filter:g~~~ENCLOSURE TO AEP:NRC:0773J STATUS REPORT IMPLEMENTATION PLAN OF REGULATORY GUIDE 1.97, REVISION 3, FOR THE DONALD C.COOK NUCLEAR PLANT UNITS 1 AND 2 8503050268 850228 PDR ADOCK 050003i5 l F PDR TABLE OF CONTENTS I.Background II.Status Report III.Tables IV.Footnotes AEPSC hired, in August 1984, the engineering consulting firm of DiBenedetto, Farwell&Hendricks in order to perform the detailed design study required to determine the Donald C.Cook Nuclear Plant (DCCNP)Units 1&2 compliance with Regulatory Guide 1.97, Revision 3.A final report on this subject is expected by June, 1985.This document presents preliminary findings that have resulted from our discussions with the consultant. | | {{#Wiki_filter:}} |
| This report may be modified at the time we receive the final report, and for that reason we are expecting to update this status report later this year.The dates for modifications contained in this report are currently scheduled target dates.It must be recognized however, that equipment delivery delays, test difficulties, or other problems may cause delays in this schedule.Certain requirements of Regulatory Guide 1.97 were judged to be unreasonable to backfit in an operating plant.Justification is provided for these requirements to which.we take exception.
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| The table included with this enclosure contains information regarding instrument range, environmental qualification, seismic qualification, quality assurance, redundancy, power supply, location of display and required actions and schedule for each type A,B,C,D, and E variable listed in Regulatory Guide 1.97, Revision 3.This table is consistent in organization with Table 3 (PWR Variables) of Regulatory Guide 1.97, Rev.3 dated May, 1983.In some instances, the.Type B-E variables are duplicated by the Type A variable listing.In these instances, reference back to the Type A variable is made because the requirements for Type A variables are the most stringent.
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| The schedule and status for each instrument indicates when the requirements of Regulatory Guide 1.97 as described in this enclosure will be met.Open items are indicated by TBD (To Be Determined).
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| Deviations from the Regulatory Guide and justification for the deviations are given in the footnotes located at the end of this enclosure.
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| The following general notes provide clarifications for each category of information requested by section 6.2 of Supplement 1 to NUREG 0737 with the exception of instrument range, which is self explanatory:
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| 1.Sensor Location The"sensor(s) location(s)".information requested in Section 6.2(e)of Supplement 1 to NUREG 0737 is assumed to mean the application and not physical plant location.This information i's provided in the column labeled"variable." 2.Environmental uglification Instruments reported as environmentally qualified (marked"yes" in the column labeled"EQ")are planned to meet the provisions of 10 CFR 50.49.As allowed by 10CFR 50.49(k), original DCCNP instrumentation located in a potentially harsh environment has been qualified in accordance with the"DOR Guidelines".
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| Equipment ordered after February 22, 1983, is to have environmental qualification in accordance with Category I of NUREG 0588 (For Comment)(i.e.IEEE Std 323-1974)unless there are sound reasons to the contrary.Consistent with 10CFR 50.49, DCCNP is not required to environmentally qualify equipment located in a mild environment.
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| 3.Seismic uglification 4.Instruments reported as seismically qualified (i.e., marked"yes" in the column labeled"SQ")are planned to meet the provisions of the DCCNP Updated FSAR p.7.2-12 (i.e., protection grade equipment is designed such that for a design basis earthquake, the equipment will not lose its capability to perform its design objective; namely, shut the plant down and/or maintain the unit in a safe shutdown condition.)
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| Typical equipment of this type originally installed at DCCNP was seismically tested by Westinghouse Electric Corporation as documented in WCAP-7397-L,"Topical Report Seismic Testing of Electrical and Control Equipment".
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| No industry standards regarding seismic qualification existed at that time.Equipment ordered for Regulatory Guide 1.97 upgrading is planned for seismic qualification in accordance with Regulatory Guide 1.100 (i.e., IEEE Std.344-1975)unless there are sound reasons to the contrary.ualit Assurance Instruments reported as meeting quality assurance requirements (i.e., marked"yes" in the column labeled"QA")are planned to meet the provisions of the DCCNP QA program as described in DCCNP Updated FSAR Section 1.7.This program, as described, satisfies the requirements of 10CFR 50, Appendix B.The implementation of specific Regulatory Guides and ANSI standards regarding quality assurance are consistent with the commitments of DCCNP FSAR Section 1.7 Appendix A.Instruments reported as meeting the single failure criterion or redundancy requirements (i.e., marked"yes" in the column labeled"SF")are planned for a minimum of two (2)redundant, electrically independent channels up to and including any isolation device.The display may be a common multi-pen recorder or a dual indicator.
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| The redundant channels are also physically separated in accordance with the DCCNP Updated FSAR p.7.2-4.Physical separation requirements for redundant Post Accident Monitoring Instrumentation channels will be established in a manner consistent with the application of separation criteria to existing plant IE instrumentation 6 control circuits.The extent of conformance to Regulatory Guide 1.75 for D.C.Cook Plant IE systems was given in the answer to question 40.6 in FSAR Appendix Q, Unit 2 p.40.6-2.In some instances, redundancy will be provided by measurement of a diverse"variable.
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| Instruments reported as meeting Class IE power supply requirements (i.e., marked"IE" in the column labeled"PS")are planned to be powered from IE power supplies such as the 120V AC instrument buses or the 250 V DC buses as described in the DCCNP Updated FSAR Sections 8.1 and 8.3.7.Dis la Location The display will be indicated either inside the control room or at another location as permitted by Regulatory Guide 1.97.8.Schedule The implementation schedule provided for each variable is the current best estimate of the completion of the final configuration for the associated instrument including redundancy, final displays, power supplies, documentation of qualification and turnover to plant operations.
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| The schedules are based on anticipated delivery and plant outage schedules.
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| Equipment delivery delays, environmental qualification test difficulties, or other problems, however, may cause delays in these schedules beyond our reasonable control.Since the Consultant's engineering study has not yet been completed and a final report has not been issued, some items listed may require revision or deletion.In some instances equipment may be added to the list.The final configuration will not be determined until the EOP's and DCRDR program have been implemented and integrated with the Regulatory Guide 1.97 schedule.Considering these factors, our overall target date for completion of work undertaken in r'esponse to Regulatory Guide 1.97 is December, 1991.Most variables presently listed are measured with fully operational instruments, however, the instruments are not considered complete for the purposes of this enclosure until they meet Regulatory Guide 1.97 requirements as described in this enclosure.
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| Note that instruments previously reported to the staff as meeting the requirements of NUREG 0737 or IE Bulletin 79-01B do not, in all cases, meet all of the requirements of Regulatory Guide 1.97.The schedules provided in this enclosure for meeting Regulatory Guide 1.97 requirements are not intended to change any previous commitment regarding NUREG 0737 or 10CFR 50.49, whose requirements may be different.
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| I I I.-TABLES These tables represent the status of the Donald C.Cook Nuclear Plant when'e have completed all of the requirements associated with Regulatory Guide 1.97, Rev.3.It does not, nor is it intended to reflect the status of the plant as of the date of this letter.
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| Type A Variables: "those variables to be monitored that provide the primary information required to permit the control room operator to take specific manually controlled actions for which no automatic control is'rovided and that are required for safety systems to accomplish their safety functions for design basis accident events.Primary information is information that is essential for the direct accomplishment of the specified safety funtions;it does not include those variables that are associated with contingency actions that may also be identified in written procedures." Note: These variables are plant-specific and based on review of the D.C.Cook Nuclear Plant Emergency Operating Procedures (EOP's)plus anticipated future changes to the EOP's.The schedule and status for each instrument indicated is for when all of the requirements of Regulatory Guide 1.97, Rev 3 will be met.Item No.Purpose Variable Tag No.s Range E S Q S P Display Remarks/Action Req'd A F S Location U-1 U-2 Schedule Schedule A-1 Maintain Prcssur-Centrifigal IFI-51,52, 0-200 GPM Y Y Y Y IE Control Room Replace, control room izer Level during Chg Pump Flow 53,54 Panel SIS indicators with seismic S/G Tube rupture qualified equipment 1987 re-1987 re-fueling fueling outage outage A-2 Manual Trip of RC Pumps based on RCS pressure RCS Pressure (wide range)NPS-121,122 0-3000psig Y Y Y Y IE Control Room Replace control room 1987 re-1987 re-Panel RHR recorder with seismic fueling fueling qualified equipment outage outage A-3 NOT USFD A-4 See footnote (n)RCS Hot Leg NTR-110,120, 32-700'F Y Y Y Y IE Control Room Replace recorders Temperature 130,140 Panel DTU with seismic quali-fied equipment 1987 re-1987 re-fueling fueling outage outage A-5 Set makeup for RCS Soluble automatic control Boron Concen-tration.NSX-101,103 NA NA NA NA NA NA NA See footnote (a)NA NA A-6 See footnote (n)RCS Cold Leg Temperature NTR-210>220>
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| 32-700 F 230,240 Y Y Y Y IE Control Room Replace recorders Panel DTU with seismic quali-fied equipment 1987 re-1987 re-fueling fueling outage outage Item No.Purpose Variable Tag No.s Range E S Q S P Display A F S Location Remarks/Action Req'd U-l U-2 Schedule Schedule A-7 Determination of required core exit temperature by S/G Prcssure (ruptured)
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| S/G Prcssure MPP-210,211, 0-1200psig 212,220, 221,222, 230,231, 232,240, 241,242 Y Y Y Y IE Control Room Replace control room 1987 re-1987 re-Panel SG indicators with seismic fueling fueling qualfied equipment outage outage A-8 Determination of adverse containment Containment Sump Level NLA-310 NLI-311,320, 321 589.5 to 614 ft.el-evation (bottom uf sump to max flood level)Y Y Y Y 1E Control Room Replace control room Panel RHR indicators with seismic qualified equipment 1987 re-fueling outage 1987 re-fueling outage A-9 Manual Reduction of ECCS Flow S/G Level Narrrow range BLP-110,111, 112%120, 121,122, 130,131, 132,140, 141,142 29-137" wc Y Y Y Y IE Control Room Replace control room Panel SG indicators and/or recorders with seismic qualified equipment 1987 re-fueling outage 1987 re-fueling outage A-10 Manual Reduction of ECCS Flow Pressurizer Level NLP-151,152, 153 0-1002 (essent-ially top to bottom not includ-ing rounded portions)Y Y Y Y IE Control Room Replace control room Panel PZR indicators and/or (NLP-151 also recorders with seis-HSD)mically qualified equipment 1987 rc-1987 re-fueling fueling outage outage A-11 See footnote (n)Primary System QR-107 A,B,'afety Relief C,D Valve Position NA Y Y Y NA IE Control Room See footnote (b)Panel RC NA NA Item No.Purpose Variable Tag No.s Range E 8 Q S P Display Q Q A F S Location Remarks/Action Req'd U-l U-2 Schedule Schedule A-12 Determination of adverse containment Containment Area Radiation Monitor Nigh Range VRA-1 310>1410, (Unit I)2310, 2410 (Uni.t 2)I R/ljtR to Y NA Y Y IE Control Room IX10 R/1lR Panel RMS See footnote (c)NA A-13 Manually establish or trip containment spray Lower Contain-, ment Pressure PPP-300,311, 302,303-5 to+l2 Y psig Y Y Y IE Control Room Panel SPY Replace transmitters, indicators with qualified equipment 1987 re-fueling outage 1987 re-fueling outage A-14 Manually establish or trip containment spray Upper Contain-ment Pressure PPA-310,3ll>
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| 312,313-5 to 36psig Y Y Y Y IE Control Room Panel SPY Replace transmitters, indicators, recorders, with qualified equipment 1987 re-1987 rc-fucling fueling outage'outage A-15 Manual Reduction of Auxilliary FFI-210,220, ECCS Flow Fccdwater Flow 230,240 0-250 KPPN Y Y Y Y IE Control Room Panel SC Redundancy provided by diverse variable-S/C narrow range level which is qualified.
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| Replace indicators with seismic qualified equipment 1987 re-fueling outage 1987 re-fueling outage A-16 Manual Transfer to RWST Level cold leg recircula-tion in low level in RWST ILS-950,951 essentially NA Y Y Y IF.Control Room Top to Panel SPY Bottom Replace indicators, recorders with seismic qualified equipment.
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| Also see footnote (d)1987 re-fueling outage 1987 re-fueling outage A-17 Manual Trip or re-duction of Press-urizer Spray and ECCS Flow Degrees Sub-NA cooling 0-199'F sub-Y cooling 0-199'F Superheat NA Y NA IE Control Room See footnotes (b)and (c)Panel BA which apply beyond the isolating devices NA NA A-I8 Control Makeup Flow Make up FInw-QFI-200 During S/C Tube in Rupture 0-200 CPM NA Y Y Y IE Control Room Replace control room Panel BA and indicators with seismic HSD qualified equipment (QFI-200).
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| Add second redundant qualified channel 1988 re-1989 re-fueling fueling outage outage
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| Item No.Purpose Variable Tag No.s Range E S Q S P Display Remarks/Action Req'd Q Q A F S Location U-I 11-2 Schedule Schedule A-19 Control Letdown Letdown flow-QFI-301 Flow during S/C out Tube Rupture 0-200GPH NA Y Y Y IF.Control Room Replace control room Panel BA and indicators with seismic HSD qualified equipment (QFI-301).
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| Add second redundant qualified channel 1988 rc-1989 re-fueling fueling outage outage A-20 Hanual Control of RCP Seal In-Seal injection flow jeccion Flow to establish minimum charging flow QFA-210,220.
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| 230,240 0-15 GPH Y Y Y Y IE Control Room Replace transmitters with 1990.rc-Panel RCP qualified equipment.
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| Add fueling redundant, qualified outage channels.Replace exiscing control room Indicators with seismic qualified equipment 1989 re-fueling outage A-21 See footnote (n)RHR Flow IF1-310,311, 0-8000 GPH Y Y Y Y IE Control Room Replace control room 1987 re-1987 re-320,321, Panel RHR indicators with seismic fueling fueling qualified equipment outage outage A-22 See footnote (n)Lower Contain-ment'pray Flow NA NA NA NA NA Nh NA NA See footnote (c)NA A-23 See footnote (n)Intermediate Range Flux N-35, N-36 Nh Nh Nh NA NA NA NA Sce footnote (f)NA A-24 See footnote (n)Reactor Cool-ant Inventory NLI-110,111, Essentially 120,121, Top to Hot-130,131 tom of Ves-sel Y Y Y Y IF.Control Room None required Panel SIS N*NA A-25 Manual Reduction Core Exit of ECCS Flow T/C's 141,142 T/C 1-65 200-2300.F Y Y Y Y IF.Control Room All required cables, Panel FI connectors, indicators, signal processing equipment to be replaced with qualified equipment t See foot-See foot-note (g)note (g)
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| Item No.Purpose Variable Tag No.s Range E S Q S P Display A F S Location Remarks/Action Req'd U-I U-2 Schedule Schedule A-26 Determining Status of RCP during DBE and allow for manual trip if necessary RCP Pump Status Ql,Q2,Q3,Q4 0-1200A NA TBD Y Y IE Control Room See footnotes (d), (k), TBD Panel RCP&(m)TBD A-27 See footnote (n)Pressurizer Neater Status Croup AI,A2, A3,CI,C2,C3 ON/OFF NA TBD Y Y IE Control Room See footnotes (d)&(k)TBD Panel PZR TBD A-28 A-29 Manual trip of RCP's Manual trip of RCP's CCP Breaker Status SI Pump Breaker Status Pump IE,IW OPEN/CLOSE NA TBD Y Y Pump IN,1S OPFN/CI.OSE NA TBD Y Y IE Control Room Panel BA IE Control Room Panel SIS See footnotes (d)&(k)TBD See footnotes (d), (k), TBD&(m)TBD TBD A-30 Manual trip of RCP's RCP Breaker Position QI,Q2,Q3,Q4 OPEN/CLOSE NA TBD Y Y IE Control Room Panel RCP See footnotes (d), (k), TBD TBD&(m)A-31 See footnote (n)Lower CS Pump Breaker Posi-tion Pump IE,1W OPEN/CLOSE NA TBD Y Y IE Control Room Panel SPY See footnotes (d)and (k)TBD TBD A-32 See footnote (n)RNR Pump Breaker Posi-tion Pump IE,1W OPEN/CLOSE NA TBD Y Y IE Control Room See footnotes (d)and (k)TBD TBD Panel RHR A-33 See footnote (n)Valve Position TBD Limit Switches (various)OPEN/CI.OSE OPEN/NOT OPEN CLOSF/NOT CLOSE TBD TBD TBD TBD TBD TBD See footnote (k)TBD TBD A-34 See footnote (n)Safety Infec-tion Pump Flow IFI-260,266 0-200GPM Y Y Y Y IE Control Room Panel SIS Replace control room indicators with seismic qualified equipment 1987 re-fueling outage 1987 re-fueling outage A-35 See footnote (n)S/G Blowdown Radiation DRA-300,353 TBD TBD TBD TBD TBD IE Control Room TBD Panel RMS TBD TBD A-36 Manual Switchover to alternate water source on low level in CST Condensate Storage Tank Level CLI-113 CLR-110, 111 Essentially Top to Bot-tom Y Y Y Y IE Control Room Panel CP Replace indicator with seismic qualified equipment See footnote (d)1987 re-fueling outage l987 re-fueling outage Item No.Purpose Variable Tag No.s Range E S Q S P Display Q A F S Location Remarks/Action Req'd U-l U-2 Schedule Schedule A-37 See footnote (n)Upper Contain-IFI-330,331 0-2500 CPM TBD TBD TBD TBD IE Control Room TBD ment Spray Panel SPY Flow TBD TBD
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| <~
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| Type B Variables: "those variables that provide information to indicate whether plant safety functions arc being accomplished.
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| Plant safety functions are (1)reactivity control, (2)core cooling, (3)maintaining reactor coolant system integrity, and (4)maintaining containment integrity (including radioactive effluent control)." Note: The schedule and status of each instrument is for when all of the requirements of Regulatory Guide 1.97, Rev 3 will be met.Item Purpose No.Variable Cat.Tag No.s Range E S Q S P Display Remarks/Action Req'd A F S Location U-l U-2 Schedule Schedule B-1 Reactivity Neutron 1 Control Flux NE-41A,41B, 42A,42B, 43A,438, 44A,44 8 0-120X full NA Y power Y Y IF.Control Room See footnote (f)Panel NIS NA NA B-2 Control Rod 3 Position Full in or NA NA NA NA NA Control Room None required not full in Panel NA NA B-3 RCS Soluble Boron Con-centrate See item A-5 B-4 RCS Cold Leg Temp-erature See item A-6 B-5 Core Cooling RCS Hot Lcg Water Temperature Sce item A-4 8-6 RCS Cold Leg Water Temperature See item A-6 B-7 B-B RCS Pressure Core Exit Temperature See item A-2 See item A-25 B-9 Coolant Inventory Sec item A-24 B-10 Degrees of Subcooling See item A-17 Item Purpose No.Variable Cat.Tag No.s Range B S Q S P Display Remarks/Action Req'd U-1 V-2 Q A F S Location Schedule Schedule B-11 Maintaining RCS Prcssure RCS Integrity See item A-2 B-12 Containment Sump Water Level See item A-8 B-13 Containment Pressure Sce items A-13 and A-14 B-14 Maintaining Containment Integrity Containment Isolation Valve Posi-tion (ex-cluding check valves)1 TBD CLOSFD-TBD TBD TBD TBD TBD TBD NOT CLOSFD Isolation Valve Limit S~itch information and schedule will be provided with the update to this report to be issued as noted in thc cover letter this enclosure TBD TBD B-IS Containment Pressure See items A-13 and A-14 Type C Variables: "those variables that provide information to indicate the potential for being breached or the actual breach of the barriers to fission product releases.The barriers are (I)fuel cladding, (2)primary coolant pressure boundary, and (3)containment." Note: The schedule and status for each instrument is for when all of the requirements of Regulatory Guide 1.97, Rev 3 will be met.Item No.Purpose Variable Cat.Tag No.s Range E S Q S P Display Remarks/Action Req'd A F S Location U-I U-2 Schedule Schedule C-1 Fuel Cladding Core Exit Temperature See item A-25 C-2 Radioactive concentra-tion or Radiation Level in Circulating Primary Coolant NSX-IOI,I03 Ii Tech Spec NA Y Y NA NA NA Limit to 100 Times Tech Spec Limit See footnote (h)NA C-3 Analysis of Primary Coolant (Gamma Spectrum)10cm Ci/ml to 10cm Ci/m or TID-14844 Source Term in Coolant Volume See item C-2 C-4 Reactor Cool-RCS Pres-ant Pressure sure Boundary See item A-2 C-5 Containment Prcssure See items A-13 and A-14 C-6 Containment Sump Water Level See item A-8 C-7 Containment Area Radi-ation See item A-12 Item No.Purpose Variable Cat.Tag No.s Range F.S Q S P Display Q A F S Location Remarks/Action Req'd U-I V-2 Schedule Schedule C-8 Fffluent 3 Radioactiv-ity-Noble gas Ffflucnt from Con-denser Air Removal Sys-tem Exhaust TBD TBD.NA NA NA NA TBD TBD TBD TBD C-9 Containment C-IO RCS Pressure Containment llydrogen Concentra-tion TBD TBD TBD TBD TBD TBD TBD TBD See item A-2 See footnote (k)TBD TBD C-11 Containment Pressure See items A-13 and A-14 C-12 Containment Effluent Radioactiv-ity-Noble gases from identified release points 2 TBD TBD NA NA NA NA IE Control Room See footnote (d)Panel MDG NA NA Item No.Purpose Variable Cat.Tag No.s Range E S Q S P Display Q A P S Location Remarks/Action Req'd U-l U-2 Schedule Schedule Effluent 2 Radioactiv-ity-Noble.Cases (from buildings or areas where penetra-tions and hatches are located, eg, secondary containment and AUX buildings that are in direct con-tact with primary containment TBD TBD TBD NA TBD NA TBD TBD Sce footnote (k)TBD TBD Type D Variables: "those variables that provi<lc information to indicate the operation of individual safety systems and safety.These variables are to help the operator make appropriate decisions in using thc individual mitigating the the consequences of an accident." Note: The Schedule and Status for each instrument ments of Regulatory Guide 1.97, Rev 3 will be met.other systems important to syst'ems important to safety in is for when all of the requirc-Item No.Purpose Variable Cat.Tag No.s Range H S Q S P Display Remarks/Action Req'd U-I 0-2 Q Q A F S Location Schedule Schedule D-I RHR System RHR System Flow See item A-21 D-2 RHR Heat Fm-2 ITR-311,321 TBD change Out-let Temp NA NA Y NA IF.Control Room Sce footnote (d)Panel RHR NA NA D-3a SI Systems Acrumu]ator Tank Level 2 II.A-110-,111 120,121>130,131, 140,141 0-133" wc Y (wide range)105.8 to 121.7 in.(narrow range)NA IE Control Room Replace one transmitter
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| /Panel SIS tank with env.qualified equipment and make wide range 1990 re-fueling outage 1989 re-fueling outage D-3b Accumulator Tank Pres-sure 2 IPA-110,111 120,121, 130,131, 140, 14<1 0-800 psig Y NA Y NA IF.Control Room Rcplacc onc transmitter
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| /Panel SIS tank with env.qualified equipment 1990 re-fueling ou tagc 1989 re-fueling outage D-4 Accumulator Tank Isola-tion Valve Position 2 TBD Closed or TBD NA TBD NA TBD TBD Open Isolation Valve limit switch information and schedule will be provided with the update to this rcport to be issued as noted in the cover letter to this enclosure TBD TBD D-5 D-6 Boric Acid Charging Flow Flow in HPI System See item A-18 See item A-I D-7 Flow in LPI.System Sec item A-21 Item No.Purpose Variable Cat.Tag No.s Range F.S Q S P Display Remarks/Action Req'd U-l U-2 Q Q A F S l.ocation Schedule Schedule D-B RWST I.evel See item A-16 D-9 Primary Cool--RCP Status ant System See item A-26 D-10 Primary Sys-tem Safety Relief Valve Positions or Flow Thru or pressure in Relief Valve Lines Pressurizer Level Sec item A-11 Sec item A-10 D-12 Pressurizer Heater Sta-tus See item A-27 D-13 Quench Tank l.evel 3 NI,A-351 Top to Bottom NA NA NA NA IE Control Room Panel PZR None required Nh NA D-14 Quench Tank Temperature 3 NTA-351 50-750 F NA NA Nh NA IE Control Room Panel PRZ Increase Range from 50'F to 300'F to required 50-750 F 1987 re-fueling outage 1987 re-fueling outage D-15 Secondary Sys-S/0 I.evcl Ccm (Steam Generator)
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| I BL1-110,120, Essentially Y Y 130,140 from cube sheet c<>separators Y Y IE Control Room Panel SG Relocate transmitters above containment floodup elevation.
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| Replace indicators with seismic qualified equipment.
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| See footnote (I)1990 re-fueling outage 1989 re-fueling outage D-16a SafeCy/Re-2 TBD lief Valve Positions Closed-Not TBD NA TBD NA TBD TBD Closed Valve Position limit switch information and schedule will bc provided with the update to this report to be issued as noted in the cover letter to this enclosure TBD TBD item No.Purpose Variable Cat.Tag No.s Range I S Q S P Display A F S Location Remarks/Action Req'd U-I U-2 Schedule Schedule D-16b Hain Steam Flow HFC-IIO,III, 0-4x10 PPH 6 120,121, 130,131, 140,141 Y NA Y NA IF.Control Room None required Panel SO NA D-17 Hain Fecd-water Flow FFC-210,211, 0-5xlO PPH NA 6 220,221, 230.231, 240,241 NA NA NA IF.Control Room None required Panel BA NA NA D-18 Auxiliary Feed-Aux Fced-water System water Flow See item A-15 D-19 Condensatc Storage Tank Level See item A-36 D-20 Containmcnt Containment Cooling System Spray Flow Sce item A-22 6 37 D-21 liest Removal by contain-ment Neat Re-moval System D.C.Cook Plant Units 162 NA do not have a Contain-ment liest Removal System, therefore this item does not apply NA D-22 D-23 Containment Atmosphere Temperature Containment Sump Mater Temperature 2 FTR-11,12,13,-40 to 14,15,16, 400 F 17,18,19, 20,21,22, 23,24,?5.26,27 2 Y NA Y NA IE Control Room Panel A-14 Replace RTD's with envi-1990 re-ronmentaliy qualified fueling equipment.
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| Increase range outage from-40 to 300'F to as specified See footnote (j)1989 re-fueling outage Item No.Purpose Variable Cat.Tag No.s Range-E S Q S P Display A F S Location Remarks/Action Req'd U-1 U-2 Schedule Schedule D-24 Chemical and Make up Volume Control Flow-In System D-25 Letdown Flow-Out See item A-18 See item A-19 D-26 Volume Con-trol Tank Level 2 QLC-451>452 0-70" wc NA NA (essential-ly top to bottom)Y NA IE Control Room Panel BA See footnote (d)NA NA D-27 Cooling Water System CCW water Temperature to ESF Sys-tem 2 CTR-410,415, TBD 420,425 NA NA TBD NA TBD Control Room See footnote (d)Panel ESW TBD TBD D-28 D-29 Radwaste Systems CCW Flow to ESF System High Level Radioactive Liquid Tank Level 2 CFI-410,419, 420,429 3 RLS-255>256 TBD NA NA Top to Bot-NA NA tom TBD NA IE Control Room See footnote (d)Panel CCW NA NA IE Control Room None required Panel WDG TBD NA TBD D-30 Radioactive Gas Holdup Tank Pres-sure 3 RPC-310,320, TBD 330,340, 350,360, 370,380 NA NA NA NA IE Control Room None required Panel WDG NA NA D-31 Ventilation System Emergency Ventilation Damper Pos-ition 2 later Open-Closed TBD NA TBD NA TBD TBD Damper Position limit switch information and schedule will be provided with the update to this report to be issued as noted in the cover letter to this enclosure TBD TBD Item No.Purpose Variable Cat.Tag No.s Range E S Q S P Display Q Q A F S Location Remarks/Action Req'd U-l U-2 Schedule Schedule Power Supplies Status of Standby Power and other Energy Sources Im-portant to Safety D-32a Diesel Cen Status 2 DGIAB DCICD 0-800A NA NA Y NA IE Control Room See footnote (d)Panel SA NA NA D-32b 4kv Safety Related Po-wer Systems Status 2 Bus T11A, T11B, T11C, T11D 0-150V NA NA Y NA IE Control Room See footnote (d)Panel SA NA NA D-32c 250V Battery Power System Status 2 Battery AB Battery CD 0-300V NA NA Y NA IE Control Room See footnote (d)Panel SA NA NA D-32d 120VAC Safe-ty Related Power System Status 2 Channel I,II, 0-150V III, IV NA NA Y NA IE Control Room See footnote (d)Panel SA NA NA D-32e Instrument Air Status 2 XPI-100 X PI-50 XPI-20 XPI-85 0-150psig 0-100psig 0-60psig 0-160psig NA NA Y NA NA Control Room These are mechanical Panel SV devices-no electrical components NA NA Type E Variables: "those variables to be monitored as required for use in determining the magnitude of the release of radioactive materials and continually assessing such releases." Note: The schedule and status for each instrument is for when all of the requirements of Regulatory Guide 1.97, Rev.3 will be met.Iten Purpose No.Variable Cat.Tag No.s Range E S Q S P Display A F S Location Remarks/Action Req'd U-1 U-2 Schedule Schedule E-2 Containment Radiation Arcs Radiation Containment Area Radia-tion High Range Radiation Exposure Rate (in-side Build-ings or where areas of access is required to service equipment important to Safety 3 TBD TBD NA NA NA NA TBD TBD See item A-12 See footnote (k)TBD TBD E-3a Noble Cases.Containment 2 TBD and vent Flow or Purge Rate Effluent TBD TBD NA NA NA TBD TBD See footnote (k)TED TBD E-3b Reactor Shield Building Annulus 2 TBD TBD TBD NA NA NA TBD TBD See footnote (k)TBD TBD E-3c Aux Building 2 TBD TBD TBD NA NA NA TBD TBD See footnote (k)TBD TBD E-3d Condenser Air Removal System Ex-haust 2 TBD TBD TBD NA NA NA TBD TBD See footnote (k)TBD TBD E-3e Common Plant Vent 2 VRF-315 TBD TBD NA NA NA TBD TBD See footnote (k)TBD TBD Item No.Purpose Variable Cat.Tag No.s Range E S 1)S P Display A F S Location Remarks/Action Req'd U-1 V-2 Schedule Schedule E-3f F.-4 E-5a Particulates and Halogens Environ Radia-tion and Radio-activity Vent from S/0 Safety Relief Valves OCher ident-ified re-lease points All identi-fied release points (ex-cept S/C Safety Re-lief valves and Conden-ser air re-moval System exhaust)Sampling and onsite analysis Airborne Radioacti-vity and Particulates sampling and analysis 2 TBD 2 TBD 3 NA 3 NA TBD TBD TBD TBD TBD NA NA NA TBD TBD TBD NA NA NA TBD TBD NA NA NA NA NA NA NA NA NA NA NA NA See footnote (k)See footnote (k)See footnote (k)See footnote (k)TBD TBD TBD TBD TBD TBD TBD TBD E-5b Plant and Environs Radiation (Portable) 3 NA TBD NA NA NA NA NA NA See footnote (k)TBD TBD E-5c Plant and Environs Radioacti-vity (Port-able)3 NA TBD NA NA NA NA NA NA Sec footnote (k)TBD TBD Meteorology Wind Direc-tion 3 EFR-410,411, 0-360'A 420,421 NA NA NA non Control Room None required-IE Panel Fix NA NA Item Purpose No.Variable Cat.Tag No.s Range E S O S P Display A F S Location Remarks/Action Req'd U-l U-2 Schedule Schedule E-7 E-8 Wind Speed Estimation of Atmos-pheric Stability 3 EFR-400,401, 0-100 mpH 402,403 3 ETR-400,401, TBD 402,403 NA NA NA NA NA NA NON Control Room None required-1E Panel Flx NA NA NON Control Room None required-1E Panel Fix NA NA NA NA E-9a Accident Samp-Gross Acti-ling Primary vity Coolant and Sump 3 TBD TBD NA NA NA NA NA NA None required NA NA E-9b Gamma Spec-3 TBD trum TBD NA NA NA NA NA NA None required NA NA F.-9c Boron Con-tent 3 TBD TBD NA NA NA NA NA NA None required NA NA E-9d E-9f E-9g Chloride Content Dissolved H2 or total gas (issolved 2 3 TBD 3 TBD 3 TBD TBD TBD TBD NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA None required Hone required None required NA NA NA NA NA E-9h E-10a Containment Air E-10b E-10c pH H2 Content 0 2 Content Gamma Spec-trum 3 TBD 3 TBD 3 TBD 3 TBD TBD TBD TBD TBD NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA HA NA NA NA NA NA NA NA NA None required None required None required None required NA NA NA NA NA NA NA NA IV.FOOTNOTES DESIGNATING EXCEPTIONS TO REGULATORY GUIDE 1.97, REV.3 (a)The automatic injection of boric acid into the RCS by the safety injection system following a postulated LOCA/HELB will be monitored and verified through the use of qualified instrumentation.
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| In addition, since all sources of water for the safety injection system (Accumulators, Boric Acid Storage Tanks and Refueling Water Storage Tanks)are required by Technical Specifications to contain boric acid solution of a minimum concentration, the proper operation of the ECCS system ensures an adequate boron concentration in the reactor coolant to achieve and maintain the safe shutdown of the reactor core.The RCS soluble boron content is not expected to change rapidly, if at all, following the initial borating during the SI phase of an accident.Periodic analysis of RCS samples would detect any significant changes in boron concentration.
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| Instrumentation to continuously monitor RCS soluble boron concentration is not required since periodic analysis of RCS grab samples is adequate for verification of reactivity control.(b)Redundancy not required per NUREG 0737 requirements.(c)Seismic qualification not required per NUREG 0737 requirements.(d)All equipment is located in mild environment, therefore environmental qualification is not required.(e)Lack of lower containment spray flow monitoring instrumentation will not deter the operator's ability to determine adverse containment conditions (ACC).ACC can be monitored by looking at items such as containment pressure.If we see containment pressure conditions different than what is expected, then we can confirm whether ACC is due to a lack of spray flow by the monitoring of containment spray pump.discharge pressure.(f)The neutron flux monitors are not required for LOCA/HELB mitigation, therefore their environmental qualification is not required.Following a LOCA/HELB, reactivity control to accomplish reactor shutdown is automatically achieved and maintained by a reactor SCRAM and the injection of boric acid by ECCS.This can be verified through control rod position indications and analysis of RCS grab samples.Footnote (h)is also applicable.(g)Scheduled for upgrade as described in AEP:NRC: 0761 C (h)Instrumentation to continuously monitor RCS radioactivity is not required.Periodic analysis.of RCS grab samples is adequate to detect deterioration of fuel cladding.Indicative of an inadequate core cooling (ICC)event, fast deterioration of fuel cladding could be detected by sensing the ICC conditions through diverse instrumentation (i.e., RVLIS, CET's, TSAT meter).(i)Redundancy is accomplished by the measurement of diverse variables with fully qualified equipment.
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| Auxiliary Feedwater Flow is backed up by S/G level (narrow range).(j)Containment Sump Water Temperature will give no information required to mitigate and determine the consequences of an accident.Containment Sump Level, Atmosphere Temperature and pressure are adequate for operators to determine containment conditions.
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| Therefore, measurement of Containment Sump Water Temperature is not required.
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| (k)This information will be provided with our update to this report to be issued as noted in the cover letter to this enclosure.
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| (1)INTENTIONALLY LEFT BLANK (m)Redundancy is accomplished by verifying pump flow from qualified instrumentation.(n)This item may be deleted from the Type A variable list after further review of the DCCNP EOP's.If this occurs, the variable will be recategorized accordingly and the appropriate actions taken.The update to this report, to be submitted as noted in the cover letter to this enclosure, will reflect any changes of this nature.
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