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Category:TECHNICAL SPECIFICATIONS
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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E4791999-09-0909 September 1999 Proposed Tech Specs Revising Allowable Values for CST Low Water Level Limits from Greater than or Equal to 59,700 Gallons to Greater than or Equal to 90,300 Gallons ML20216E4631999-09-0909 September 1999 Proposed Tech Specs Change Eliminating Requirement in EPP to Sample Lake Erie Sediment in Perry & Eastlake Plant Area for Corbicula,Since Corbicula & Zebra Mussels Have Already Been Identified & Control & Treatment Plans Are Implemented ML20211P2871999-09-0909 September 1999 Proposed Tech Specs Pages,Increasing Present 100% Authorized Rated Thermal Power Level of 3579 Megawatts Thermal to 3758 Megawatts Thermal ML20210M7851999-08-0404 August 1999 Proposed Tech Specs 3.9.1,incorporating Addl Option Into Required Actions When Refueling Interlocks Are Inoperable ML20209B3391999-06-28028 June 1999 Simulator Four Yr Test Rept ML20196A2021999-06-17017 June 1999 Proposed Tech Specs SRs Implementing 24-month Operating Cycle at Pnpp ML20205C6351999-03-16016 March 1999 Preliminary Rev 0 to Wps 01-43-T-801, Preliminary Weld Procedure for Perry Nuclear Power Plant Feedwater Nozzle Repair ML20204E4971999-03-15015 March 1999 Proposed Tech Specs,Correcting Typos Found in Table 3.3.6.1-1 ML20207K1041999-03-0404 March 1999 Proposed Tech Specs Improving Licensing & Design Basis for Isolation of FW Penetrations ML20206Q3571999-01-0606 January 1999 Proposed Tech Specs Improving Licensing & Design Basis for Isolation of Feedwater Penetrations ML20195H5381998-11-18018 November 1998 Rev 4 to Pump & Valve Inservice Testing Program Plan ML20155D9431998-10-27027 October 1998 Proposed Tech Specs 2.1.1.2,applying Addl Conservatism by Modifying MCPR Safety Limit Values,As Calculated by GE ML20155D8241998-10-27027 October 1998 Proposed Tech Specs Adding Two Paragraphs to TS 5.2.2.e, Organization - Unit Staff ML20196H5131998-10-0808 October 1998 Rev 4,Vol 1 to Inservice Exam Program for Perry Nuclear Power Plant ML20151V4831998-09-0909 September 1998 Proposed Tech Specs Stipulating That Water Leakage from Feedwater motor-operated CIVs Will Be Added Into Primary Coolant Sources Outside of Containment Program & Check Valves Do Not Need to Be Included in Hydrostatic Program ML20151V1111998-09-0303 September 1998 Proposed Tech Specs Permitting EDG TS Action Completion Time of Up to 14 Days for Div 1 or 2 EDG & Allowing Performance of EDG 24-hour TS SR Test in Modes 1 & 2 ML20151V6861998-09-0303 September 1998 Proposed Tech Specs Increasing Present Div 3 DG Fuel Oil Level Requirements to Account for Rounding Error in Calculation & Unusable Volume Due to Vortex Formation at Eductor Nozzles Located in Fuel Oil Storage Tank PY-CEI-NRR-2395, Rev 5 to Perry NPP Odcm. with1998-09-0202 September 1998 Rev 5 to Perry NPP Odcm. with ML20151S9561998-08-31031 August 1998 Proposed Tech Specs,Allowing Blind Flange in Inclined Fuel Transfer Sys (Ifts) Containment Penetration to Be Removed While Primary Containment Is Required to Be Operable ML20236T7911998-07-22022 July 1998 Proposed Tech Specs Revising MSL Leakage Requirements & Eliminating Msli Valve Leakage Control Sys ML20151P1921998-07-13013 July 1998 Proposed Tech Specs,Increasing Present +/- 1% Tolerance on Safety Mode Lift Setpoint for SRVs to +/- 3% ML20236H8411998-06-30030 June 1998 Proposed Tech Specs,Increasing Boron Concentration in Standby Liquid Control Sys for Pnpp Cycle 8 Fuel Design & Providing Margin for Future Cycles as Required ML20236T8451998-06-24024 June 1998 Rev 3,Change 3 to Vol 1 of Inservice Examination Program, for Pnpp ML20216H9361998-04-14014 April 1998 Rev 1 to Proposed TS Bases,Reflecting Changes Made Since Original Implementation of TS in Improved Format in June 1996 ML20203G4781998-02-23023 February 1998 Maint Progress Review for Perry Nuclear Power Plant ML20197F7871997-12-23023 December 1997 Proposed Tech Specs,Revising 3.8.1 Re AC Sources to Be Consistent W/Recommendations in GL 94-01, Removal of Accelerated Testing & Special Reporting Requirements for Edgs ML20217K6501997-10-22022 October 1997 Proposed Tech Specs Incorporating Temp Control Valves & Associated Bypass Lines Around Emergency Closed Cooling Sys Heat Exchanger ML20217F5911997-10-0202 October 1997 Proposed Tech Specs,Adding Note to TS 2.1.1.2 Re MCPR SL Values & Adding Footnote to TS 5.6.5.b to Reference NRC SER That Approved MCPR SL Values for Cycle 7 ML20210T9631997-09-0808 September 1997 Proposed Tech Specs 5.2.2.e,removing Reference to NRC Policy Statement on Working Hours.Rev Allows Changes to Specific Overtime Limits & Working Hours to Be Evaluated IAW 10CFR50.59, Changes,Tests & Experiments ML20210U8701997-09-0808 September 1997 Rev 3,change 2 to Vol 1 of Inservice Exam Program, for Pnpp ML20217Q4591997-08-28028 August 1997 Proposed Tech Specs 3.4.11,revising Pressure-Temp Limits,Per Reactor Vessel Matl Surveillance Program Requirements Contained in App H of 10CFR50.90 ML20148A6871997-05-0202 May 1997 Proposed Tech Specs Re Surveillance Requirement for MSIV Leakage Rate Acceptance Criteria ML20148A6591997-05-0202 May 1997 Proposed Tech Specs,Revising Existing Exception to LCO 3.0.4 as Applies to LCO 3.6.1.9 for MSIV Leakage Control Sys ML20137S7761997-04-0909 April 1997 Proposed TS Requirements 3.9.1.1 & 3.9.2.2 Re Frequency on Refueling Equipment & one-rod-out Interlocks ML20134D8251997-01-31031 January 1997 Proposed Tech Specs 1.1 Re definitions,3.6.1.1 Re Primary Containment - operating,3.6.1.2 Re Primary Containment Air locks,3.6.1.3 Re PCIVs,3.6.5.1 Re Drywell & 5.5 Re Programs & Manuals ML20147B8271997-01-24024 January 1997 Rev 3 to Vol 1 of Inservice Exam Program ML20134D8751996-10-24024 October 1996 Proposed Tech Specs 2.1.1.2,safety Limits Applying Conservatism by Increasing MCPR Safety Limit Values ML20117E7891996-08-27027 August 1996 Proposed Tech Specs,Revising Mls Leakage Requirements & Eliminating MSIV Control Sys ML20108A2581996-04-26026 April 1996 Proposed Improved Tech Specs ML20100N9501996-03-0101 March 1996 Proposed TS Pages Re Drywell Leak Rate Testing Requirements ML20100L3331996-02-27027 February 1996 Proposed Tech Specs Re Drywell Personnel Air Lock Shield Door Analyses ML20100J5971996-02-24024 February 1996 Proposed Tech Specs,Revising Definition of Core Alteration ML20149K2221996-02-17017 February 1996 Proposed Tech Specs,Reflecting Mod of Leakage Rate Requirements for Main Steam Lines Until End of Operating Cycle 6 ML20100G0161996-02-0101 February 1996 Draft Rev 0 to Pnpp NUMARC/NESP-007 Plant-Specific EAL Guidelines ML20096D4651996-01-16016 January 1996 Proposed TS Requirements for Drywell Leak Rate Testing ML20096C0591996-01-10010 January 1996 Proposed Tech Specs,Requesting one-time Surveillance Interval Extension to Support Current Schedule for Refueling Outage 5,scheduled to Begin 960127 ML20095H4721995-12-20020 December 1995 Proposed Tech Specs Re Replacement of Selected Analog Leak Detection Sys Instruments W/Ge Numac Leak Detection Monitor ML20108B2851995-11-22022 November 1995 Rev 5 to Offsite Dose Calculation Manual ML20094F2051995-11-0202 November 1995 Proposed Tech Specs for Handling Irradiated Fuel in Containment or Fuel Handling Bldg & Performing Core Alterations ML20094E6751995-11-0202 November 1995 Proposed Tech Spec,Requesting Rev to TS for Onsite Power Distribution Sys:Ts 3/4.8.3.1, Distribution - Operation 1999-09-09
[Table view] |
Text
. . .. _ _ _ . _ . . _ _ .. _ _ _ _ . - _ _ _ _ _ .
7 ., .
l CONTAlffENT SYSTEMS Attcchment 2
- 'PY-CEI/NRR-1934L' MSIV LEAKAGE CONTROL SYSTEM Page 1 of 1 LIMITING CONDITION FOR OPERATION l l
3.6.1.4 ' Two independent MSIV leakage' control system (LCS) subsystems shall be !
OPERABLE.
l l
APPLICABILITY: OPERATIONAL CONDITIONS 1*, 2*, and 3*.
l ACTION:
With one MSIV lepkage control system subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. j SURVEILLANCE REDUIREMENTS !
t 4.6.1.4 Each MSIV leakage control system subsystem shall be demonstrated !
OPERABLE: ;
- a. At least once per 31 days by verifying: f
- 1. Blower OPERABILITY by starting the blower (s) from the control room and operating the blower (s) for at least 15 minutes. .
l
- 2. Inboard heater OPERABILITY by demonstrating electrical !
continuity of the heating element circuitry by. verifying :
the inboard heater draws 8.28i 10% amperes per phase. ;
.. j
- b. During each COLD SHUTDOWN, if not performed within the previous g2 j days, by cycling each motor operated valve, including the main ;
steam stop valves, through at.least one complete cycle of full !
travel. l l
- c. At least once per 18 months by: i
- 3. Performance of a functional test which includes simulated !
actuation of the subsystem throughout its operating sequence, !
and verifying that each automatic valve actuates to its .
correct position, and the blower (s) start (s). '
- 2. Verifying that the blower (s) develop (s) at least the below .
required vacuum at the rated capacity l a) Inboard system,15" H2O at 1100 scfm. ,
b) Outboard system,15' H2 O at 1200 scfm.
$ d. By verifying the inboard flow and inboard and outboard. pressure g instrumentation to be OPERABLE by performance of a:
95/y M 1.
2.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and CHANNEL CALIBRATION at least once per 18 months.
Fg W
e Ig *The provisions of Specification 3.0.4 are not applicable from ga. date of this amendment until the completion of Operating Cycl effective j
PERRY - UNIT I 3/4 6-8 nt No.63 e
.=. -, .- -
1
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- Attcchment 3 l
- PY-CEI/NRR-1934L I Page 1 of 2 !
SIGNIFICANT HAZARDS CONSIDERATION The standards used to arrive at a determination that a request for amendment involves no significant hazards considerations are included in the commission's Regulations, 10 CFR 50.92, which state that the operation of the facility in accordance with the proposed amendment vould not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any previously evaluated, or (3) involve a significant reduction in a margin of safety.
The proposed amendment has been reviewed with respect to these three factors and it has been determined that the proposed change does not involve a significant !
hazard because:
- 1. The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
This License Amendment application proposes an extension for one operating cycle of the exception to Limiting Condition for Operation (LCO) 3.0.4 as it applies to the Technical Specification for the MSIV Leakage Control '
System. This extension is proposed for the duration of the sixth cycle of PNPP operation, to permit completion of activities necessary to implement the most appropriate permanent resolution for the issue of secondary
~
containment bypass leakage through the Main Steam Line drains. During the sixth cycle, the drains vill remain in their current configuration, which -
seals off the bypass leakage path. The sealed drain path results in a temporary inoperability of the Inboard MS1V Leakage Control System (MSIV-LCS) subsystem when the plant is operated below 50% power, due to condensate build-up in the bottom of the steam lines between the MSIVs.
The requested 3.0.4 exception is necessary to permit plant startups with this temporary inoperability, for the duration of the sixth operating cycle.
The probability of occurrence of a previously evaluated accident is not affected by the proposed extension of the LC0 3.0.4 exception since no change to the plant or to the manner in which the plant is operated is involved. The existing plant configuration vill be maintained for another operating cycle, and possible concerns resulting from that configuration have been analyzed. The extra weight of the water pooled between the MSIVs was analyzed with respect to piping supports and seismic considerations and was found to be acceptable, and any condensate that is carried past the outboard MSIVs vill be drained to the condenser by drain ;
connections downstream of the outboard MSIVs before it can reach the turbine. The temporary inoperability of the Inboard MSIV-LCS when below 50% power has no impact on accident initiation probability, since LCS does I not serve to prevent accidents, but is only used in mitigating the consequences of Loss of Coolant Accidents that have already occurred.
The consequences of an accident are not significantly increased in that the Outboard MSIV-LCS will be available to perform the MSIV-LCS function by mitigating the consequences of a Loss of Coolant Accident during the temporary period in which the Inboard MSIV-LCS is unavailable. Any condensate that is carried past the outboard MSIVs vill be drained to the condenser by drain connections downstream of the outboard MSIVs; therefore no impairment of the Outboard MSIV-LCS will result from condensed water.
3
~
- Attechment 3 '
- PY-CEI/NRR-1934L Page 2 of 2 l The Action statement for one inoperable LCS subsystem remains the same, and limits plant operation to the previously established 30-day Allovable Outage Time. The Action required if both subsystems of MSIV-LCS vere to become inoperable also remains the same. The MSIV function of isolating the Main Steam Lines is also unaffected by the existing plant configuration, since MSIV performance vill not be affected by the existence of accumulated water in the bottom of the steam lines between the MSIVs during plant operation belov 50% power. Therefore, if necessary, the Main Steam Lines vill be isolated, and leakage past the ,
MSIVs will be routed for filtration as in the design-basis radiological t analyses, and the consequences of previously evaluated accidents vill remain unaffected.
- 2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change to permit inoperability of the Inboard MSIV-LCS during periods of startup and power ascension to 50% RTP and during shutdown belov 50% RTP does not create the possibility of a new or different kind of accident from any previously evaluated. The Inboard MSIV-LCS is only credited during a Recirculation Line Break LOCA wherein Reactor Coolant System depressurization occurs. The temporary unavailability of the Inboard MSIV-LCS can be mitigated by operation of the Outboard MSIV-LCS.
The amendment to the Technical Specifications is an administrative change that does not involve any change to the current plant design or methods of operation. No new plant equipment failure modes or accident initiators are introduced by the extension of the LCO 3.0.4 exception. ,
- 3. The proposed change does not involve a significant reduction in a margin of safety.
The response to the Recirculation Line Break LOCA vill not be significantly affected since the Outboard MSIV-LCS can be assumed to be available. Allowing entry into Operational Conditions 1, 2 and 3 while utilizing the existing Action statement does not significantly reduce the margin of safety since the duration of time allowed for remaining in that Action statement is not increased. The proposed change vill have no adverse impact on the reactor coolant system pressure boundary nor vill any other system protective boundary or safety limit be affected.
l l
l l
Attachment 4 PY-CEI/NRR-1934L Page 1 of 1 CONTAINMENT SYSTEMS i
\'
BASES l
l 3/4.6.1.3 CONTAINMENT AIR LOCKS (Continued)
The administrative controls for both sentences of footnote ** include -
provisions that after each entry and,, exit, the OPERABLE door must be promptly closed. The allowances of footnote are acceptable because of the low probability of.an event that could pressurize the containment during the short time that the OPERABLE door will be open for entry into and exit from the containment.
The air supply to the containment air lock and seal system is the service and instrument air system. The system consists of two 100% capacity air compressors per unit and can be cross-connected. This system is redundant and extremely reliable and provides system pressure indication in the control room.
3/4.6.1.4 MSIV LEAKAGE CONTROL SYSTEM Calculated doses resulting from the maximum leakage allowance for the main steam line isolation valves in the postulated LOCA situations would be a small fraction of the 10 CFR 100 guidelines, provided the main steam line system from the isolation valves'up to and including the turbine condenser remains intact. Operating experience has indicated that degradation has occasionally occurred in the leak tightness of the MSIV's such that the specified leakage requirements have not always been maintained continuously.
The requirement for the leakage cont.rol system will reduce the untreated leakage is re from the 'C MSIV's when*Wh 5 CW isolation 15 Pr"of t{e d primary system and containmentOF8 Sad conA; quired. Aaam h Inb=A msw-L c s 9asys%
u ca3 Fd tac-s
% 8inopen in w aa 6 3/4.6.1.5 CONTAINMENT STRUCTURAL INTEGRITY d^5*4861Av a-
- ^ h'WS yue This limitation ensures that the structura7intYgYlTy ofth[carrveA %
containment will be maintained comparable to the original design standards for the life of
, the unit. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 15 psig in the event of a LOCA. A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.
3/4.6.1.5 CONTAINMENT INTERNAL PRESSURE
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The limitations on primary containment to secondary containment '
differential pressure ensure that the primary containment peak pressure of l 7.80 psig does not exceed the design pressure of 15.0 psig during LOCA l !
conditions or that the external pressure differential does not exceed the l design maximum external pressure differential of +0.8 psid. The limit of -0.1 to +1.0 psid for initial positive primary containment to secondary containment pressure will limit the primary containment pressure to 7.80 psig which is l less than the design pressure and is consistent with the safety analysis.
W W PERRY - UNIT 1 B 3/4 6-2a Amendment No.Ef,57 l
l l
, Attach =nt 5 :
PY-CEI/NRR-1934L MSIV LCS Paga 1 of 2 .3.6.1.9 l 3.6 CONTAINMENT SYSTEMS 1 3.6.1.9 Main Steam Isolation Valve (MSIV) Leakage Control System (LCS) ;
LC0 3.6.1.9- Two MSIV LCS subsystems shall be OPERABLE.
5 APPLICABILITY: MODES 1. 2. and 3.
kam hcon eMen t p ;
ACTIONS Mqtopusk)C)do6. .
CONDITION COMPLETION TIME p
Ill35.Es5I+~-
A. One MSIV LCS subsyst inoperable.
M_a5LMC-subsystem to OPERABLE
)
'30 days status.
B. Two MSIV LCS B.1 Restore one MSIV LCS 7 days i subsystems inoperable. subsystem to OPERABLE ;
status. ,
C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i associated Completion Time not met. AND l C.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> !
i SURVEILLANCE REQUIREMENTS ,
SURVEILLANCE' FREQUENCY SR 3.6.1.9.1 Operate each MSIV LCS blower 31 days !
= 15 minutes. .
i I
(continued) ;
i I
PERRY - UNIT 1 3.6-27 Amendment No. C 1
Attachment 5
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PY-CEI/NRR-1934L MSIV LCS
BASES APPLICABLE The MSIV LCS satisfies Criterion 3 of the NRC Policy SACETY NJALYSES Statement. !
(continued)
. LCO One MSIV LCS subsystem can provide the required processing !
'-of the MSIV leakage. To ensure that this capability is :
available, assuming worst case single failure two MSIV LCS :
subsystems must be OPERABLE. !
APPLICABILITY In MODES 1. 2 and 3. 6 DBA could lead to a fission product l release to primary containment. Therefore. MSIV LCS OPERABILITY is required during these MODES. In MODES 4 and 5. the probability and consequences of these events are .
reduced due to the pressure and temperature limitations in .
these MODES. Therefore, maintaining the MSIV LCS OPERABLE is not requircd in MODE 4 or 5 to ensure MSIV leakage is !
processed.
ACTIONS A.1 i
With one MSIV LCS subsystem inoperable. the inoperable MSIV :
LCS subsystem must be restored to OPERABLE status within :
30 days. In this Condition. the remaining OPERABLE MSIV LCS ,
subsystem is adequate to perform the required leakage :
control function. However, the overall reliability is reduced because a single failure in the remaining subsystem !
could result in a total loss of MSIV leakage control '
function. The 30 day Completion Time is based on the i redundant capabili afforded by the remaining OPERABLE MSIV '
LCS subsystem and e low probability of a DBA LOCA occurring during this period. An L C.D L M u p c6 is PN M
+o erre ;+ u.y .% opwat cmA;mrs wkar n muk {
("S l V - L c.5- sw6 s35h 6.c. 4 5 i n o per a Ma, Am 4. mAush l B.1 witA., % 4 w msiv, % %,,,. p w t ;, , g +,A >
b el .w sc'3, m M W A pwer.
With two MSIV LCS subsystems inoperable, at least one subsystem must be restored to OPERABLE status within 7 days.
The 7 day Completion Time is based on the low probability of the occurrence of a DBA LOCA. j (continued) -
1 l
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PERRY - UNIT 1 B 3.6-50 Revision No. C l
1