ML20236P322

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Forwards Response to 870313 Generic Ltr 87-06, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves. Encl Lists 46 Pressure Isolation Valves in Each Unit Which Ensure Integrity of Low Pressure Sys in RCS
ML20236P322
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 11/12/1987
From: Alexich M
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: Murley T
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
AEP:NRC-1041, GL-87-06, GL-87-6, NUDOCS 8711170240
Download: ML20236P322 (30)
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Columbus, OH 43216 E DNDIANA MICHIGAN POWER AEP:NRC:1041 GL 87-06 Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 GENERIC LETTER 87-06, PERIODIC VERIFICATION OF LEAK TIGHT INTEGRITY OF PRESSURE ISOLATION VALVES U.S. Nuclear-Regulatory Commission . Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley: November 12, 1987

Dear Dr. Murley:

This letter is in response to Generic Letter 87-06, " Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves," dated March 13, 1987. Our submittal due date extension was discussed with our Project Manager, Mr. D. L. Wigginton. The fourth paragraph of the Generic Letter states that the Donald C. Cook Nuclear Plant is one of the 32 older PWR plants identified for the performance of periodic valve leak testing of certain valves in accordance with the " Event V" Order. The Generic Letter, to the best of our understanding, is requesting information concerning all. pressure isolation valves including those identified as " Event V" valves. Pressure isolation valves (other than " Event V") which could fail end could cause the high pressure reactor coolant to pass to a low pressure piping system, have been identified. Attachment 1 lists a total of 46 pressure isolation valves in each unit which we believe ensure the integrity of the low pressure systems attached to the reactor coolant system. describes the measures taken, including periodic tests or verifications, to assure the integrity of each of the valves. The valve numbers listed in the table are applicable to both Cook units and are uniquely identified with a prefix number, e.g., 1-SI-151E or 2-SI-151E. J l I The technical specifications referenced herein are provided as. Paragraphs IWV-3420 through IWV-3427 of the ASME B&PV Code Section XI, 1983 Edition with addenda through summer 1983 are provided as Attachment 4. k [ P r ____________________d

m- -) s- - t.. Dr. T. E. Murley-AEP:NRC:1041 e. 1 This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned, i Sincerely, i t s M. Alex h Vice President cm j Attachments i cc: ' John E.'Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman A. B. Davis - Region III i l l l

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PAGE' 1' PRESSURE' ISOLATION VALVES 0.C. COOK NUCLEAR PLANT UNITS 1 & 2 AEP:NRC 1041 e a ATTACHNENT 1 PRESSURE ISOLATION VALVES D.C. COOK NUCLEAR PLANT UNITS 182 MEASURES TO ASSURE INTEGRITY AND VALVE NO. STSTEM FUNCTION ACCEPTANCE CRITERIA FOR LEAKAGE .............s.3 3....... ....................a sa.................................... RM 133 ECCS 2ND CK VALVE ON THE RHR LINE SEE NOTE 1 .FOR COOLDOWN TO RCS COLD LEG #2 RH 134 ECCS 2ND CK VALVE ON THE RHR LINE FOR COOLDOWN TO RCS COLD LEG #3 SI-170L2 ECCS 1ST CK VALVE ON THE INJECTION LINE TO RCS COLD LEG #2 i $1-170L3 ECCS iST CK VALVE ON THE INJECTION LINE TO RCS COLD LEG #3 1 i S! 170L1 ECCS 1ST CK VALVE ON THE INJECTION LINE SEE NOTE 2 TO ACS COLD LEG #1 SI 170L4 ECCS IST CK VALVE ON THE INJECTION LINE SEE NOTE 2 TO RCS COLD LEG #4 'l SI 152N' ECCS/$1 CK VALVE ON THE St PUMP "N" SEE NOTE 3 DISCH TO RCS HOT OR COLD LEGS i SI 1525 ECCS/S1 CK VALVE ON THE $1 PUMP "S" SEE NOTE'3 DISCH TO RCS HOT OR COLD LEGS SI 158L1 ECCS/SI 1ST CK VALVE ON THE LOW HEAD SI SEE NOTE 4 TO RCS HOT LEG #1 ) l S! 158L2 ECCS/S! 1ST CK VALVE ON THE LOW HEAD $1 TO RCS HOT LEG #2 1 SI-158L3 ECCS 1ST CK VALVE ON THE LOW HEAD $1 TO RCS HOT LEG #3 SI 158L4 ECCS 1ST CK VALVE ON THE LOW HEAD St TO RCS HOT LEG #4 y ] l I l

'PAGE '2 PRES $URE ISOLATION VALVES D.C. COOK NUCLEAR PLANT UNITS 1 & 2 AEP:NRC 1041 7; MEASURES TO ASSURE INTEGRITY AND VALVE No. SYSTEM FUNCTION ACCEPTANCE CRITERIA FOR LEAKAGE' I- -== ssanss===seassenssassassassassass======ss============sessassassassass======= s=====ss== SI 161L1 ECCS 2ND CK VALVE ON THE SI/RHR INJ. LINE SEE NOTE 4 TO RCS COLD LEG #1; l i SI 161L2 ECCS 2ND CK VALVE ON THE $1/RHR INJ. LINE TO RCS COLD LEG #2 $1 161L3J ECCS 2ND CK VALVE ON THE SI/RNR INJ. LINE TO RCS COLD LEG #3 SI 161L4-ECCS 2ND CK. VALVE ON THE $!/RNR INJ. LINE TO RCS COLD LEG #4 $1 166L1' ECCS -2ND CK VALVE ON THE ACCUMULATOR SEE NOTE 2 DISCHARGE TO RCS COLD LEG #1 St 166L2 'ECCS 2ND CK VALVE ON THE ACCUMULATOR : SEE NOTE 2 DISCHARGE TO RCS COLD LEG #2 4 SI 166L3-ECCS '2ND CK VALVE ON THE ACCUMULATOR SEE NOTE 2 DISCHARGE TO RCS COLD LEG #3 SI 166L4 ECCS. 2ND CK VALVE ON THE ACCUMULATOR SEE NOTE 2 DISCHARGE TO RCS COLD LEG #4 SI 151E ECCS CK VALVE ON THE RHR PUMP SEE NOTE 3 DISCHARGE LINES To RCS COLD OR HOT LEGS SI 151W ECCS-CK VALVE ON THE RHR PUMP SEE NOTE 3 DISCHARGE LINES TO RCS COLD OR HOT LEGS ICM 129 ECCS 2ND MOV VALVE ON THE RCS LOOP 82 HOT LEG SEE NOTE 5 RETURN TO RHR FOR COOLDOWN & HEATUP IMO-128. 'ECCS iST MOV VA ON THE RCS LOOP #2 HOT LEG SEE NOTE 6 RETURN TO RHR FOR COOLDOWN & HEATUP NRV 151 CVCS 2ND (PORV) VALVE ON THE PRESSURIZER SEE NOTE 7 I OISCHARGE LINE TO PRT I ,NRV 152 CVCS 2ND (PORV) VALVE ON THE PRESSURIZER DISCHARGE LINE TO PRT l NRV 153 CVCS 2ND (PORV) VALVE ON THE PRESSURIZER DISCHARGE LINE TO PRT l SV-45A CVCS SAFETY & RELIEF VALVE ON SEE NOT-E 8 THE PRESSURIZER I SV 458 CVCS SAFETY & RELIEF VALVE ON f THE PRES $URIZER SV 45C CVCS SAFETY & ret.!EF VALVE ON l THE PRESSURIZER Y __=_ l

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SAGE, 3 PRESSURE ISOLATION VALVES ' D.C. COOK NUCLEAR PLANT UNITS 1 & 2 AEP:NRC 1041

',f l MEASURES To ASSURE INTEGRITY AND Wf ACCEPTANCE CRITERIA FOR LEAKAGE

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FUNCTION VALVE NO. STSTEM - I SEE NOTE 9 NS0 021 RCS 1ST $0LEWol0 VALVE ON REACTOR HEAD VENT b LINE-NSO 022 RCS 2NO SOLENCID VALVE ON REACTOR HEAD VENT 4 i LINE iST SOLENCID VALVE ON REACTOR HEAD VENT NS0-023 RCS LINE NS0-024 RCS 2ND SOLEN 0!D VALVE ON REACTOR HEAD VENT Q LINE l 1., 4 SEE NOTE 9 NSO-061 RCS iST SOLEN 010 VALVE ON PRESSURIZER VENT 3 LINE v{ NSO-062 RCS 2ND SOLENCID VALVE ON PRESSURIZER VENT LINE f-NS0 063 RCS iST SOLENotD VALVE ON PRESSURIZER VENT LINE l> 1 2ND SOLENOID VALVE ON PRESSURIZER VENT l NSO-064 RCS LINE f i. [ fl SEE NOTE 10 RC 113L1 RCS 1ST MANUAL VALVE ON THE RC LOOP #1 DRAIN LINE TO PRT [ RC-114L1 RCS 2ND MANUAL VALVE ON THE RC LOOP #1 L DRAIN LINE TO PRT ) RC-113L2 RCS iST MANUAL VALVE ON THE RC LOOP #2 DRAIN LINE TO PRT RC 114L2 RCS 2ND MANUAL VALVE ON THE RC LOOP #2 DRAIN LINE TO PRT { RC 113L3 RCS 1ST MANUAL VALVE ON THE RC LOOP #3 1 DRAIN LINE TO PRT f RC 114L3 RCS 2ND MANUAL VALVE ON THE RC LOOP #3 l DRAIN LINE TO PRT l RC 113L4 RCS 1ST MANUAL VALVE ON THE RC LOOP #4 I I DRAIN LINE TO PRT l RC 114L4 RCS 2ND MANUAL VALVE ON THE RC LOOP #4 l DRAIN LINE To PRT \\ j l, j N l 1 L I i 1

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l tk V ^ L AEP:NRC:1041 k ATTACHMENT 2 EXPLANATION NOTES Note 1: These check valves are installed in series on the RCS cold-legs #'s 2 and 3 and RRR lines foricool down. These valves are normally closed during power operation. These are the " Event V" check valves that were included in the order dated ' April _20, 1981. The valves are leak tested in accordance with Technical Specification 4.4.6.2.2. I Note 2: These check valves are normally closed during power operation due to the RCS pressure. These valves are seat leakage tested in accordance with paragraph IWV-3420 of ASME B&PV Code Section XI, 1983 Edition with addenda through summer 1983. Leak test is performed at a refueling frequency in accordance1 with IWV-3422. Permissible leakage is 5 gpm. Note 3: These check valves are normally closed during normal power operation due to the RCS pressure..These valves are tested instead of IM0-315 and IMO-325, the second normally closed-valve in series from RCS hot legs 1 & 4 and 2 & 3, respectively. The pressure rating of the piping does not change upstream of IMO-315 and IM0-325. These valves are seat leakage tested in accordance with paragraph IWV-3420 of ASME B&PV Code Section XI, 1983 Edition with addenda through summer l 1983. Leak test is performed at a refueling frequency in accordance with IWV-3422. Permissible leakage is 5 gpm. Note 4: These check valves are normally closed during power operation due to the RCS pressure. They are seat leakage tested in ') accordance with paragraph IWV-3420 of ASME B&PV Code Section XI, 1983 Edition with addenda through summer 1983. Leak tests are performed at a refueling frequency in accordance with IWV-3422. The permissible leakage value is 10 gpm for each pair of valves as listed below: (a) SI-158L1 and SI 158L4 (b) SI-158L2 and SI-158L3 1-(c) SI-161L1 and SI-161L4 (d) SI-161L2 and SI-161L3 i 4 r

AEP:NRC:1041 Page 2 Note 5: This valve is seat leakage tested in accordance with Paragraph IWV-3420 of ASME B&PV Code Section XI, 1983. Edition with addenda through summer 1983. Leak test is performed at a refueling frequency in accordance with IWV-3422. Permissible leakage is 10 gpm. In addition, this valve is normally closed and cannot be operated during normal power operation because the valve is interlocked with the RCS pressure transmitter to remain closed at RCS pressure above 410 psig. The valve is. administrative 1y kept clored and control power is removed. Note 6: This double disc gate valve is located in series with ICM-129 in loop #2 RCS hot leg return to RH3 for normal heatup and cool down. This valve is normally closed during normal power l operation and is interlocked with the RCS to remain closed at RCS pressure above 410 psig. The J.nterlock.also automatically closes the valve at a RCS pressure of 600 psig. As stated in Note 5, valve ICM-129 is seat leakage tested. In addition to the administrative controls on ICM-1:29, the piping downstream of ICM-129 is protected against overpressurization due to leakage from the RCS by a safety relief valve. The safety relief valve is designed to relieve 900 gpm at set pressure of 450 psig. The safety valve discharges to the Pressurizer Relief Tank which is located in containment. Note 7: These valves are the pressurizer power operated relief valves (PORV) which discharge to the pressurizer relief tank. These valves are closed during power operation. There is an acoustic monitor and a temperature sensor in the common header downstream of these valves. Plant Technical Specification 3.4.6.2 sets allowable leakage limits of reactor coolant system inventory. Note 8: These pressurizer safety valves (Category C) are tested in accordance with Article IWV-3510 of Section XI of the ASME Code. Each valve has an acoustic monitor and a temperature sensor on the downstream pipe. Plant Technical Specification 3.4.6.2 sets allowable leakage limits of reactor coolant system inventory. Note 9: These reactor head vent and pressurizer vent valves are required to be closed during normal power operation per Technical Specifications 3.4.12.1 and 3.4.12.2, respectively. There is a temperature sensor in the common header downstream of these valves. The piping downstream of valves NS0-022 & NSO-024 and NS0 062 & NSO-064 (second valve) is vented in the containment. Plant Technical Specification 3.4.6.2 sets allowable leakage limits of reactor coolant system inventory.

AEP:NRC:1041 'Attechmsnt 2 Psgr 3-I I i Note'10: Manual valves RC-113 and RG-114 located in series in the drain line of each RCS loop to the reactor coolant drain tank i (RCDT). These. valves are closed during normal operation. The RCDT is equipped with level, temperature and pressure devices. The downstream piping and RCDT is protected against overpressurization from the RCS by a safety relief valve set at 25 psig. The safety valve discharges into the containment. Plant Technical i . Specification 3.4.6.2 sets allowable leakage limits of reactor coolant system inventory. 7 i ,i ) ) l g1 'l e l l l

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i \\ l q PLAg0RCOOLANTSYSTEM f c EF'.TIONAL LEAXAGE_ ) LPtITING CONDITION FOR OPERAT10M i 1 3.4.6.2 Reactor Coolant System leakage shall be limited to: j No PRESSURE BOUNDARY LEAUGE. .a. b. 1 GPM UNIDENTIFIED LEAXAGE, i 1 GPM total prfmary-to-secondary leakage through all steam gener-c. ators. and 500 gallons per day through any one steam generator, d. 10 GPN IDENTIFIED LEAKAGE frem the Reactor Coolant System, and e. 52 GPM CONTROLLED LEAKAGE. f. 1 GPM leakaoe fran any reactor coolant system pressure isolation valve specified in Table 3.4-0. 1 I. APPLICABILITY: MODES 1, 2, 3 and A i i ACTION: t With any PRESSURE BOUNDARY.LEAXAGE, he in at least HOT STANDBY a. within 6 hours and in COLD SHUTDOWN within the following l 30 hours. l With any Reactor Coolant System leakage greater than any one l b. of the above limits, excluding PRESSURE BOUNDARY LEAXAGE, j reduce the leakage rate is within limits within 4 hours or be ] in at least HOT STANDBY within the next 6 hours and in COLD i SHUTDOWN within the following 30 hours. j l With any reactor coolant system pressure isolation valve (s) leak- ) c. age greater than the abcve limit, except wnen: I 1 The leakage is less : an or ecual to 5.0 gpn, and

  • 1 1

2. The most recent measured leakage dces not exceed the previous measured 'eacage* by an amount that reduces the

("To sat 1sfy ALARA requirements, measured leckage may be measured indirec.ly (as from the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with the

) L leakage criteria. l April +. 1981 f 7 1.C. COOK - UMIT 1 3/a 4-16 Order dated J 1-e

i 3

ArinR C001 ANT SYSTEM ll l

LI4tTINr, CONDTTION FOR OPERATION-(Continued) 1 i margin between the most recent measured leakace and the j maximus limit of 5.0 opm by 50% or more, - declare the leaking valve' inoperable and isolate the high y pressure portion of-the affected system from the low pressum 5 portion by the use of a combination of at least two closed f valves, one of which may'be the OPERABLE check valve and t% I Verify the. other a: closed de-enercized motor operated valve. isciated condition of the closed de-enercized motor operated j valve at least once per 24 hours, or be in at least NOT j STANDBY within the next E hours and in COLD SHUTDOWN within -j the following 30 hours. i \\ SURVEILLANCE REQUIREMENTS '4 !l f 4.4.6.2.1 Reactor Coolant System leakaces shall be demonstrated to be j within each of the above limits by; Monitoring the containment atmosphere particulate radioactivity;y ~ a. 3 monitor at least once.per 12 hours. b. Monitoring the ' containment sump inventory and discharge at f least.once per 12 hours. Monitoring the CONTROLLED LEAKAGE to the reactor coolant

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j pump seals at least once per 31 days, l <I i Performance of a Reactor Coolant System wter inventory tulance .f d. at least once per 72 hours curing steady state operation, and Monitoring the reactor head flar.ge leakoff system at least e. once per 24 hours. Each reactor coolant system pressure isolation valve - 4.4.6.2.2 specified in Table 3.4-0 shall be demonstrated OPERABLE verifying leakage to be dthin its limit prior to entering MODE 3: a. After each refueling outace; Whenever the plant has :een in COLD SHUTDOWN for 72 hours :r b. more and if leakace testing has not been performed in the previous 9 months;

  • No Report required (6.9.1) unless tne valve has been declared inoperable.

l 0.C. COOK - UNIT 1 3/4 4-17 Order dated APfil -

  • INI 1

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a r x .j 1 i 1 i RtAtlun LOOLAMi SYS1tM - j l i .a SURVEILLANCE REQUIREMENTS (Continued) Prior to returnina.the valve to service following maintenance, l c. repair or replacement work on the valve. .l s ) d 1 1 l - i i i I I i I 4 1 1 1 l ) e \\ i i t O.C, COOK - UMIT-1 3/4 4 17a Order datad Anril ?),1981 l i e

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s TABLE 3.4-0 REACTOR CDOLAMT SYSTP. PRESSURE ~-IS0'J.T.10N YALVES K IOM(a) 1 - Yi1VE NUMBER Low Head Safety injection Loop 2. cold leg SI-170L2 RH133 Loop 3, cold' leg 5!-170L3 PS134 l s l i 1 4 1 i I*IMinimum test differential pressure shall not be below 150 psid. J j l' l 1 .{ 4 .I l 1e ) I l 'i D.C. COOK - W."1 3/4 4-17b Order dated April 20,1981 g C i-__ _ __ -- _ 4: l

i 3916 M AW annam m3 Aq d4hAf AW esmag; vassEL win 1g33 S miTuss CDEDiiiGui MR OFraATION 1s'least ese of the Reester Yeasel head vest paths, esasisting of / two remotely operated valus is serias, peeered free Class 15 BC 3.4.12.1 hasses, shall be CFERABLE and closed. f M t3 1, 2, 3, and 4. 1 APFLIt' ANILITY : ) M3 With both of the taaster Yessel head vest paths isoperable and at least one of the Presseriner steam space was paths GFIBABLE (se a. spesifiaaties 3.4.12.2), operation la MtBES 1, 3, ) with power removed from the valve satuaters of all the reastely l operated valves is all of the inoperable wat paths; restere at I be in EDT STAEDlY vithia 6 hears and la COLD fellowing - 30 heers. With both of the Reester Yessel head vent pathe sad both of the Pressurizer steam space wat paths inoperable; maintain the f b. iseparable vent paths closed with power remove inoperable vest paths; restere ese of the inoperable vest paths frem either the teactor fossel head vent or the Pressurizer s space withia 72 hours er be in EDT STANDST within 6 hears and COLD SEUTDOWN withis the fellevias 30 hours. The prevision of Specification 3.0.4 are not applicable. c. i D. C. COOK - UNIT 1 3/4 4-37 Amendment No. 98

a t ic. stacTOR SME.AW R M Bf meAcTag enasAWF Tmpf ETSTEM-sea.-suit Tweeer. uran Tgyr3 -,_ af' Anet ab iiEteerra Both Besator.Yessel head vent paths shall be demonstrated CFEXABLE# at 4.t.12.1 least ease per 18 months by: Yorifying' the common manual isolation valve La the Beautor vessel i 1. head vest is sealed in the opea position. e zing..oh of the remote 1r o, orated,sives in es.=,aa am.h. { 2 2. r st least one soaplete croie of full travel from the control soom while in Modes 5 or 6. Yorifying flov 'thnugh both of. the Reactor Yessel head vent paths { 3 j during venti g operation, while in Modes $ or 6. -l l I Surveillance requirements to demonstrate the operability of each Reactor Yassel head vest path will be performed the next time the unit enters MODES 5 or 6 following the issuanoe of thia Toonnical Spoo1fication, and after the appropriate'Flaat procedures have bees writtes. i Amendmena 100.98

      • N
  • W 1 3/4 4-38

e we; eLam Amr sTsrEM mea.;;; - *=r Tw w m m. Vesnute fr" Er Aen vwws nns counIT10s Poa ayenArrog ve a At least one of the Pressariant steam space vest paths, each 3.4.12.2 sessisting of two reastely operated valves is serias, powered from e Class 1E DC basses, shall be OFREAlu and closed. AFFLICA3ILITY: 5(288 1, 2, 3, and 4. AE1918 With both of the Presswiser sessa space vest paths inoperable, s. least one of the teactor Yessel head was paths CFERA3M and at (see Specification 3.4.12.1), operation la IEIDES 1, 2, 3 er 4 any contiana, provided the inoperable was paths'are asiatained closed with the power ransved from the valve actuators of all the restely operated valves is all of the inoperable wat paths; restore at least one of the Presswiser stema space vent paths within 30 days or be in 30T STA.@lT withis 6 hours and in COLD SEWDOWE in the following 30 hours. With both of the Pressurizer sesam space was paths and hath of b. the Esector Yessel head vent paths inoperable; asiatain the inoperable vent paths closed with power removed from the valve accur.cors of all of the remotely operated

  • valves in all of the inoperable vent paths; restore one of the inoperable was paths from either the Eaestor Yessel head vent or the Presswiser steam space withia 72 hours or be in EDT STAEDIT within 6 hours and in COLD SIMDOWN withis the following 30 hoars.

The previsions of Specification 3.0.4 are not applicable. c. D. C. COOK - UNIT 1 3/4 4-39 Amendment No. 98

i I i l R$MTOR SME. ANT BRM ,se ween tD eauf TENT ffff M i g -.e,maa gr*AM Spart TENTS 3RTEELLAECE REMffBENIETS 4.4.12.2 Seth uriser steam space vest paths shall-be deseastrated at least ease per 18 anatha try: 1.. Yerifying the common manual isolation valve is the Pressurizer steen space vent is sealed in the opea penittoa. 2. Cyoling,each of the remotely operated valves in each path through at least one complete cycle of full travel frge the Control toen l mile in Modea. 5 or 6. ) 3 Yorifying flew through both of the Pressurizer staan space vent paths during vesting operation, dile in Modes 5 or 6. I l I l l I Surve111anos requirements to descastrate the operability of each Pressurizer steam space feat path will be performed the anzt time the I unit _ esters NODE 3 5 or 6 following the issuance of this fochaieal Speaitication, and after the appropriate Flant procedures have been writtes. l 1 L l' f L l l eaa .ee = c. = - - 1 3,4 4-40 l

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J '*I REACTOR COOLA$ff SYSTFM 1 OPERATIONAL LEAKAGE _' !i

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LIMITING CONDITION FOR OPERATION

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3.4.6.2 Reactor Coolant System leakage shall be Ifmitad to: 1 i .Ho PRESSURE BOUNDARY LEAKAGE, l a.- b. 1 GPM UNIDENTIFIED LEAKAGE, 1 GPM total primary-to-secondary leakage through all steam gener-3 c. ators 'and 500 gallons per day through any one steam generator, l l d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and j 52 GPM CONTROLLED LEAKAGE. e. f. 1 GPM leakage from any reactor coolant system pressure isolation ' valve specified in Table 3.4-0. APPLICABILITY: MODES 1, 2, 3 and 4 J { ACTION:- With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STAND 8Y a. within 6 hours and in COLD SHUTDOWN within the following ? 30 hours. b. With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUfoutY LEAKAGE, t reduce the leakage rate to within limits within 4 hours or be l in at least HOT STANDBY within the next'6 hours and in COLD SHUTDOWN within the following 30 hours. With any reactor coolant system pressure isolation valve (s) leak-c. age greater than the above limit, except when: 1. The leakage is less than or equal to 5.0 gym, and

  • n 2.

The most recent measured leakage does not exceed the previous measured leakage

  • by an amount that reduces the I
  • To satisfy ALARA requirements, measured leakage may be measured indirectly (as from the;per#ormance of pressure indicaters) if act.xtplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with the

-leakace criteria. / D.C. COOK - UNIT 2 3/4 4-15 Order dated April 20, 1981

.:v. f!r.a.cT0P. C00LaMT SYSTE" LIMIENG CONDITION FOR OPERATION (Continued) .g

l

\\\\ u margin between the most recent measured leakaoe and the j maximum limit of 5.0 ppa by 50% or more, declare the' leaking valve

  • inoperable and isolate the hich pressure portion of the affected system from the low pressure I

portion by the use 'of at least two closed valves, ene of wnich. may be the_ OPERABLE check valve and the other a closed de. eneraized motor operated valve. Verify the isolated condition: of the closed de-enercized motor operated valve at least once per 24 hours, or be in at least HOT STANDBY'within' the next 6

hours and in COLD SHUTDOWN within the following 30 hours.,

SURVEILLANCE REQUIREMENTS Reactor Coclant System leakages shall be demonstrated to be e a.4.6.2.1 within each of the above limits by; I Monitoring the containment atmosphere particulate raffoactivity a. monitor at least once per 12 hours. Monitoring.the containment sump inventory and discharge at b. least once per 12 hours. Monitoring the CONTROLLED LEAKAGE.to the reactor coolant c. pump seals at least once per 31 days, Perfonnance of a Reactor Coolant System water inventory balance d. at least once per 72 hours during steady state operation, and I Monitoring the reactor head flange leakoff system at least a. once per 24 hours. Each reactor coolant system pressure isolation valve 4.4.6.2.2 specified in Table 3.4-0 shall be demonstrated OPERABLE pursuant *to l Specification 4.0.5, except that in lieu of any leakage testing required l by Specification 4.0.5, each valve shall be demonstrated GPERABLE by l verifying leakace to be within its limit prior to entering MX)E 3: a. After each refGeling outage; ) l Whenever the plant has been in COLD SHUTDOWN for 72 hours or b. more and if leakace testing has not been performed in the previous 9 months; f

  • No Report required (f.9.1) unless the valve has been declared inoperable.

q 0.C. COOK - tHIT 2 3/4 4-16 Order dated April 20, 1981 l \\ I-

s ~ REACTOR ~ COOLANT SYSTEM =l SilRVEILLANCE RE0VIREMENTS (Continued) 1 I :- Prior to returnino the valve to service following maintenance, l ~ c. repair or replacanent work on the valve. t i 1 q l

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'I',I l ll l.

l II i t l 1 p i t ' i (, 0 t t' O.C. C00X - UNIT 2 3/4 4 16a Order dated April 20, 19814 f ..i. L_

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..v. TABLE 3.4-0_ . REACTOR CNX. ANT SYSTEM PRESSURE -ISOLATION VALVES FUNCTION (a) j - g,,NUS Dt Low-Head Safety Injection i-' SI-170L2 Loop 2, cold leg i RH133 SI-170L3 Loop 3, cold leg l RH134 l i !l _g 'i i l I Ii i e i: (a) Minimum test differential pressure shall not be below 150 psid. b - - - - ~ cnna

1 ( .w u eron cocti M siii H i

  • Tk M E' W 18f TTyr a2ais azacret vass a nan vrzts gs commuions-rem u?Io*

l 's.4.12.1 At least one of the Rasster' Ye'ssel head wat paths, consisting. ef .two resotely eyeratei valwe is serles, paveres from Class'13 DC j basses, shall be CFI3A3LE and slesed. AFFLICA31LITT: MODES 1, 2, 3 and 4 kC1QKt With beth of the taaster 'Tessel. head wat paths inoperable, and at -1samt one ef'the Pressuriasr steam space was paths CFE243L2 (see a.- Specification 3.4.12.2), operation in MISES 1, 2, 3 er 4 any continue, provided the faoperable wat paths are safstained closed j with power removed-fros the valw acts.sters of all the remotely - operated vains 'in all ef the inoperable was-paths; restere at least one of the Rasstor Tessel head was paths within 30 days er he la EDT STARDST within 4 hours and in COLD SEUTDOWN within the following 30 heers. With both of the taaster Yassel head vent paths and both of the b. Pressurizer steaa ' space wat paths inoperable; malatain the inoperable wat paths closed.with power removed faa the valw actuators of al1~ of the ramtaly operated vains in all of the. inoperable _vont paths; restore one of the inoperable vent paths from either the teactor Yessel head was o'r the pressuriasr steam spas.e withia 72 hours or be in EDT STAND 8T with fa 6 hours and in COLD SEUTDcWI within the fallowing 30 hours. The provision of Spesifiaation 3.0.4 are not applicabla. c. l l ~ ( l l 1 I L

t [ ' ::;.i '.,.

  • J agacT01.GMI.Apf E MElf 3pacTOR CDOLAET TEIT SfMDt REACTOR TESSEL EEAD TENTS 3RITRILLAECE REQtTI.REGMTS l

4.4.12.1 Both teactor Yessel head vent paths shall be demonstrated CFEAABLE* at least case per 18 months by:~ l l ~ 1. Yorifying the common manual isolation valve. in the teactor vessel j head vest is sealed in the opea positica. ~2. Cre11ag.eech of the remotely operated valves in each path through l. at least one oosplete orole of full travel from the control Soce i while in Modes $ or 6. i 4 .3 Yorifying flow through 'both of the' Reactor Yessel head vent paths during venting operation, while in Modes 5 or 6. Surveillance requirements to demonstrate the operability of each Reactor Yassel head vent path will be performed the next time the unit enters MODES $ or 6 following the issuance of this Technical 3 - Specification, and after the appropriate Flaat procedures have been written. l s -l 1 l D. c. Cook - UNIT 2 3/4 4-35 Amendment No.65 I l

D. y.- .! q EsACf0E (DOMET STITE $1&CT01 CDOLANf TsIf STITEM nassunzzam ersau arAcI YEsrs 'NvTIEG CONDITION 101 OpenArtog E 3.4.12.2 : At least one of the Pressurizer. steam space vent paths, each consisting of two remotely operatet valves in serias, powered from Class 11 DC basses, shall be OFERAELE and closed. AFFLICABILITY MtBES 1, 2, 3, and 4. ACTION: With both of the Presswiser steen space vent paths inoperable, a. f and at least one of the teactor Yessel head wat ~ paths OPEIABLE (see Specification 3.4.12.1), operation in EDES 1, 2, 3 or 4 any l l l, contiane,- provided.the isoperable vest paths are maintained closed with the power removed from the valve actuators of all the I reastely operated valves is all of the isoperable wat paths; restore at least one of the Pressurizer steen space vent paths within 30 days or be in EDT STAEST within 6 hours and in COLD SEUTDOVE in the following 30 hours. 'b. With both of the Pressurizer steam space wat paths and both of j the Raector Yessel head vest paths inoperable; maintain the l isoperable wat paths closed.with power repoved from the valve l. actuators of all of the remotely operated valves in all of the l. inoperable wat' paths; restore one of the faoperable wat paths r from either the Reestor Yessel head vest or the Presswiser steen space withia 72 hears or be in WT STAERY within 6 hours and in COLD SEUYDOWE within the fo11eving 30 hours ~. The provisions of Specificatfaa 3.0.4 are not applicable. I c. L .c v D. C. COOK. UNIT 2 3/4 4-36 Amendment Iso. 65 -_i_- _ _ - m

p i. ~# 3EacTom aME. ANT MSTEM = seneren ener nue vuur srstax poemartetten 3FEAM 9122 Tmffs - sgITRILLAECE REQUIREMENTS .a toth Pregauriser steam space vont paths shall be demonstrated l - 4.4.12.2 OPERABLE at least oooe per 18 months by: j. 1. Verifying the common annual isolation valve in the Pressurizer 4 steam space vent is sealed in the open position. 2. Cycling each of the remotely operated valves in each path through at least one complete cycle of full travel from the Control Room elle in Modes 5 or 6. i i 3 Verifying flow through both of the Pressurizer steam space vent paths during venting operation, elle in Modes 5 or 6. l i i 6 h Surveillance requirements to demonstrate the operability of each !i Frassuriser steam space vent path will be performed the next time the i i unit enters *mES 5-or 6 follt, wing the issuance of this Technical Specification, and after the appropriate Plant procedures have been [ l written. I, fI i D. C. COOK - UNIT 2 3/4 4-37 Amendment No.65 i l

'\\ 4 '6-r .. 4 ? .'h '. ATTAC& LENT 4 TO AEP:NRC:1041~- 4 'I f _wm____

1983 Edition INSERVICE TESTINO OF VALVES IWV 3423-lWV 3514 leakage shall be adjusted to function maximum previous test by an amount that reduces the margin pressure differential value. This adjustment shall be between measured leakage rate and the maximum made by calculation appropriate to the test media and permissible rate by 50% or greater, the test frequency the ratio between test and function pressure shall be doubled; the tests shall be scheduled to differential, assuming leakage to be directly propor. coincide with a cold shutdown until corrective action l, tional to the pressure differential to the one half is taken, at which time the original test frequency shall ~

power, be resumed. If tests show a leakage rate increasing

(/) Valves not qualifying for reduced pressure with time, and a projection based on three or more i I testing as defined in (e) above shall be leak tested at tests indicates that the leakage rate of the next full maximum function pressure differential, with scheduled test will exceed the maximum permissible adjustment by calculation if needed to compensate for leakage rate by greater than 10%, the valve shall be a difference between service and test media. replaced or repaired. ~ IWV 3424 Seat I4akage Measurement . Valve seat leakage may be determined by one of the IWV 3500 INSERVICE TESTS - following: CATEGORY C VALVES (a) draining the line, closing the valve, bringing one IWV-3510 SAFETY VALVE AND RELIEF side to test pressure, and measuring leakage through a VALVE TESTS downstream telltale connection; or (b) measuring the feed rate required to maintain IWV 3511 Test Frequency pressure between two valves or between two seats of a gate valve, provided the total apparent leak rate is Valves shall be tested at the end of each time penod as dermed in Table IWV 3510-1. charged to the valve or gate valve seat being tested, and that the conditions required by IWV 3423 are satisfied. IWV 3512 Test Procedure ( Safety valve and relief valve set points shall be j IWV 3425 Test Medium tested in accordance with ASME PTC 25.3-1976. se The test medium shall be specified by the Owner. Bench testing, with suitable hydraulic or pneumatic equipment, or testing in place with hydraulic or pneumatic assist equipment, is an acceptable method 2 IWV 3426 Analysis' of Leakage Rates under PTC 25.3-1976. Valves so tested are not - Leakage rate measurements shall be compared with required to be additionally leak tested in accordance with IV!V 3420. previous measurements and with the permissible leakage rates specified by the plant Owner for a specific valve. If leakage rates are not specified by the IWV 3513 Additional Tests Owner, the following rates shall be permissible: (a) for water, at function pressure differential, 30D When any valve in a system fails to function ml/h; properly during a regular test, additional valves in the (b) for air, at function pressure differential, 7.5D system shall be tested as determined by an arbitrary standard cu ft/ day assumption that a 12 month operating period, has passed to another refueling, and the additional valves shall be tested to make the cumulative total tested at = nominal valve size, in. least N/60 X total valves m this category, where N now includes the additional 12 months (see Table IWV-3427 Corrective Action IWV 3510-1 for definition of N). If any of these additional valves fails to function properly on test, (a) Valves with leakage rates exceeding either the then all valves m the system m this category shall be values specified by the Owner or those rates given in IWV 3426 shall be replaced or repaired. (b) For valves 6 in. nominal pipe size and larger, if a leakage rate exceeds the rate determined by the IWV 3514 Corrective Action A valve failing to function properly during test shall i Vor check valves, use double the listed values. be repaired or replaced. 221 i t ___a

IWV 3413-IWV 3423 SECTION XI -- DIVISION I ISS Edleien ' Full stroke time is that time interval from initiation of - corrective action shall'be initiated immediately. If the - -I the actuating signal to the end of the actuating cycle. condition is not, or cannot be, corrected within 24 hr, (b) The stroke time of all power operated valves ' the valve shall be declared inoperative. When correc. shall be measured to the' nearest second, for stroke : tive action is required as a result of tests made during . times 10 sec or less, or 10% of the speci6ed limiting ' cold shutdown, the condition shall be corrected before stroke' time for full stroke times longer than 10 sec, . startup. A retest showing acceptable operation shall be " whenever such a valve is full-stroke tested. run following any required corrective action before the - d valve is returned to service. -IWV 3414 xValves la Regular Use J j Valves that' operate in the course of plant operation

]

at a frequency which would ~ satisfy the exercising 'IWV 3420 - VALVE LEAK RATE TEST-requirements of this Subsection need not be addition- . ally exercised, provided' the observations otherwise IWV 3421 Scope h required for testing are made and analyzed during Category A valves shall be leak tested, except'that c such operation, and are recorded in the plant record at. valves which function in the course of plant operation 1 intervals no greater than speci6ed in IWV 3411. - in a manner that ' demonstrates functionally adequate i seat tightness need not be leak tested. In such cases, the ' valve-record shall provide the basis for-the IWV 3415 Fall Safe Valves conclusion that operational observations constitute .j When practical. valves with fail safe actuators shall. be tested by observing the operation of the valves upon loss of actuator power. If these valves cannot be tested. .IWV 3422 Frequency once every 3 months, they shall be tested during each Tests shall be conducted at least once every 2 years. / cold shutdown; in case of frequent cold shutdowns, these valves need not be tested more often than once. '( every 3 months.

  • IWV 3423 Differential Test Pressure en Valve seat leakage tests shall be made' with the pressure differential in the same direction as when the

'IWV 3416 Valves in Systems Out of Service valve is performing its function, with the following For a valve in a system declared inoperable or not excepti ns. required to be operable, the exercising test schedule (a) Globe type valves may be tested with pressure need not be followed. Within 30 days prior to return of under the seat. the system to operable status, the valves shall be (b) Butterfly valves may be tested m, either direc-exercised and the schedule resumed in accordance don, provided their seat construction is designed for with requirements of this Article. seal,ing against pressure on either side. (c) Gate valves with two piece disks may be tested by pressurizing them between the seats. . (d) Valves (except check valves) may be tested in ( 1 IWV 3417 Corrective Action either direction if the function differential pressure is (a) If, for power operated valves, an increase in 15 psi or less. stroke time of 25% or more from the previous test for (e) Leakage tests involving pressure differentials valves with full stroke times greater than 10 sec, or lower than function pressure differentials are permit- -50% or more for valves with full stroke times less ted in those types of valves in which service pressure than or equal to 10 sec is observed, test frequency shall will tend to diminish the overall leakage channel 3 be increased to once each month until corrective opening, as by pressing the disk into or onto the seat action is taken, at which time the original test with greater force. Gate valves, check valves, and frequency shall be resumed. In any case, any abnor-globe type valves, having function pressure differential mality or erratic action shall be reported, applied over the seat, are examples of valve applica-(b) If a valve fails to exhibit the required change of tions satisfying this requirement. When leakage tests valve stem or disk position or exceeds its specified are made in such cases using pressures lower than limiting value of full-stroke time by this testing, then function maximum pressure differential, the obseryed ( l 220 1

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