ML19325E461

Forwards Rev 1 to Inservice Test Program for Review & Approval.Program Changes Resulted from Design Change Being Implemented Adding Four New Check Valves at Containment Bldg Sys/Rhr Sys Interfaces & Repairs Made on Eight Sys Valves

ML19325E461
Person / Time
Site:	Seabrook
Issue date:	10/30/1989
From:	Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-89131, NUDOCS 8911070170
Download: ML19325E461 (44)

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• New Hampshme Tod C. F:', * : -

1 Senior Vice President and J Chief Operating Officer. 'i NYN-89131 l i. j' October 30,-1989 l United States Nuclear Regulatory Cosunission Washington, DC '20555 Attention . Document Control Desk

References:

a) Facility Operating License NPF-67. Docket No. 50-443 i i' b) NHY Letter NYN-89052 dated May 1, 1989 ' Residual Heat Removal / Containment Building Spray' System Interface' G. S. Thomas to USNRC +

Subject:

Inservice Test Program (IST), Revision 1, Chanjes Gentlemen This letter submits for NRC review and approval, proposed changes to the New Hampshire Yankee (NHY)' Inservice Test Program'(IST), Revision 1. The IST l Revision 1-changes described below result from (1) the design change which is currently being implemented adding four new check valves at the CBS/RHR l systems. interfaces and (2) repairs made on eight SI system check valves subsequent to low power testing. CBS/RHR Systems Interface Check Valves i In Reference (b), NHY submitted a description of the Residual Heat l Removal (RHR)/ Containment Building Spray (CBS) Systems interface design . upgrade. The design upgrade adds an additional check valve in series with each of the four existing check valves which provide isolation at the RHR/CBS systems interfaces. Subsequent to the submittal of Reference (b), NHY and NRC representatives participated in telephone conferences on July 18, 1989, July 19, 1989 and July 27, 1939. The telephone conferences focused on the .t inservice testing requiremento applicable to the four new check valves and the a four existing check valves. During the course of the telephone conferences, NHY described the intended flow testing for aach of the valves and also y - committed to perform a backseat verification test on each valva. Changes to the NHY Inservice Test Program, Revision 1, which reflect the flow testing and backseat verification testing commitments are included in the following g; enclosures: .oWQ $0" Enclosure As " Figure 5.3, Valve Testing Requirements, System - .g Containment Spray,' added valves CBS-V147 and CBS-V148 l coo to the IST Program, "oM l .Q Enclosure B: ' Figure 5.3, Valve Testing Requirements, System - op Residual Heat Removal," added valves CBS-V145 and '[ CBS-V146 to the IST Program. N Enclosure C: Valve Testing Requirements Notes, revised notes 29 and f 80'O' 36, added note 62. F New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300

• Seabrook, NH 03874
• Telephone (603) 474 9521

V1 y! ~ ~ } i: Mi j S' R-United States Nuclear Regulatory Commission October 30, 1989 Attention: Document Control Desk Page 2 l Enclosure D Relief Request V-28, added valves CBS-V147 CBS-V148 and revised relief request V-28. T Enclosure E Relief Request V 31, added valves CBS-V145, CBS-146 and revised relief request V-31. Additionally, the following items which support the enclosed changes to the IST Program are also enclosed: Enclosure F: Outline for performance of a backseat verification test. on the A train CBS/RHR system interface check valves. IST procedures for the Train A and Train B valves will be consistent with the steps contained in I the enclosed outline. Enclosure G Analytical verification that the backseat verification i test acceptance criteria (differential pressure across each check. valve greater than or equal to 50 psi maintained for 15 seconds) provides adequate assurance that any leakage into the CBS system is below the capacity of the CBS system relief valves (30 gpm). Enclosure H: Annotated FSAR Table 3-9(B)-23 sheets 30, 32, 54 and i 55 to reflect the inservice testing for these valves. l These FSAR revisions will be included in a future FSAR Amendment. SI System Check Valves Subsequent to low power testing, eight Safety Injection (SI) system check f valves were disassembled, repaired, and reassembled. The various types of i repairs made to these valves included blue checks, lapping, disc and spring i-replacement, valve replacement, etc. l Due to the repairs / replacement performed on these check valves, tests [ must be performed to demonstrate that the performance parameters which could be affected by the replacement or repair are within acceptable limits (ASME Section XI, Paragraph IWV-3200). The pressure isolation function of these valves will be verified and quantified to be within acceptable limits in accordance with the NHY IST Program. Technical Specifications, and existing plant survelliance procedures. The full stroke exercise test of these check valves would be impractical to perform in the present plant cold shutdown condition due to the necessity that the Reactor Vessel Head must be removed before a SI pump can flow to the vessel. Vessel head disassembly is an extremely arduous process that would significantly impact the current schedule. The inability to exercise these check valves on a quarterly p frequency and during cold shutdown has already been identified in the current l NHY IST Program and relief has been approved to perform the full stroke l exercise test during refueling outages, (Reference Relief Request V-18). c

r LE ' i .'o~ E 4-i United States Nuclear Regulatory Commission October 30, 1989 Attention: Document Control Desk Page 3 i-In accordance with Attachment i of USNRC Generic Letter 89-04 Items 1 and 2, it is proposed that relief be granted due to the impracticality of performing a full flow test, and that the check valve disassembly and inspection be utilized to verify capability of each valve to be full stroke exercised. In addition, it is proposed that radiographs will be performed on the reassembled check valves to verify orientation of the internals to preclude any potential binding of the check valve due to incorrect reassembly. This would be a 'ONE TIKE" relief request and future testing will be performed in accordance with the approved NHY IST Program. The following enclosures provide changes to the IST Program Revision 1: Enclosure I: " Figure 5.3, Valve Testing Requirements System - Safety Injection High Head', added Note 63 to valves + SI-V81. V86. V106, V110 Vil8, V122 V126, and V130 on the Valve Testing Requirements Table. s Enclosure J: Valve Testing Requirements Notos, provided Notes 10 and 19 for information, and added Note 63. Enclosure K: Relief Request V-10, provided Relief Request V-10 for information. Enclosure La Relief Request V-18, provided Relief Request V-18 for information. Enclosure M Relief Request V-49, added (new) Relief Request V-49. 1 1 Enclosure N: Information Only copy of NHY P&ID 1-SI-B20446 detailing the valves discussed in Enclosure I. New Hampshire Yankee would greatly appreciate an expeditious NRC review and l approval of the enclosed changes to the IST Program Revision 1. If you have any questions on the enclosed material please contact Mr. Robert E. Sweeney in our Bethesda Office at (301) 656-6100. L Very trul) yours, h WL -~ Ted C. Fe baum Enclosures l l

v--. m (-- n (' i I 4 United States Nuclear Regulatory Commission October 30, 1989 k h_ ' Attention: Document Control Desk Page 4 k cci Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission i Region I 475 Allendale Road l King of Prussia, PA 19406 Mr. Victor Nerses. Project Manager Project Directorate I-3 United States Nuclear Regulatory. Commission Division of Reactor Projects Washington, DC 20555 Mr. Antone C. Corne NRC Senior Resident Inspector P.O. Box 1149 Seabrook, NH.03874 t h t -. - ~ < - ,,y-e-- v g-

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.? l ENCLOSURE A l l FIGURE 5.3 VALVE TESTING REQUIREMENTS SYSTEM - CONTAINENT SPRAY F&ID NO. 805023/1-CBS-820233/1-Iffy-804979 l C C C C C C C C C C C C C C C C C C C C C C C B B B B B B B R B B B. B B B B B B B B S S B B S S S S S S S S S S S S S S S S S S S S 5 L L V V V V V V V V V V V V V V V V V V V C C V V VALVE 2 3 5 7 8 9 1 1 1 1 1 1 2 2 3 3 3 3 4 V V 1 1 1 2 4 5 7 8 5 6 1 2 3 8 3 1 1 4 4 1 1 7 8 2 2 D E COORDINATES B3 B3 B2 B2 B1 83 D1 D1 81 A2 C1 C1 A2 C4 D1 02 D1 D4 D3 D3 DJ C4 C2 FUNCTION A A A A A A A A A A A A A A A A A A A A A A A CODE CLASS 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 CATEGORY B C B C B C A AC B C A AC C C B B B B B B B C C SIZE (IN.) 12 12 12 12 10 12 8 8 IE 12 8 8 IE 10 4 4 4 6 6 8 8 1E 1E VALVE TYPE G C G C G C G C G C G C C C B B B G G G G C C ACTUATOR H M M M M M P P P M M M M NORM POSIT 0 C 0 C C C C C C C C C C C C C C C C C C C C LEAK TEST REQ 2 2 2 2 LEAK TEST REL LEAK TEST ALT EXER TEST REQ 1 3 1 3 1 3 1 3 1 3 1 3 3 3 1 1 1 1 1 1 1 3 3 EXER TEST REL X X X X X X X X X X X X EXER TEST ALT 3 3 3 3 3 3 3 3 2 2 3 3 F.S. TEST REQ X X X PDS IND TEST X X X X X X X X X X X X X NOTES: 47 47 29 28 29 28 29 29 31 31 29 29 62 62 62 62 REMARKS: X X X X Rev. 1 , ~ - -..,.

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C 5 4 c l 1 v e R ~ ~ e 1 2 6 2 CBS - V1 4 6 C A 2 C 1 C C 3 X 3 3 6 l S 4 2 6 2 T CBS - V1 4 5 C A 2 C 1 C C 3 X 3 3 6 F 9 E 7 1 /4 1 M 9 RH - V28 D A 2 B 3 G A C 1 X X E 4 R 0 1 / 4 L 8 Rh - V27 D A 2 B 3 G A C 1 X X B I

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Q Y 1 R 5E H RH - FCV61 1 C A 2 B 3 G M 0 1 X U R M S E A O RG 1 RH - FCV61 0 C A 2 B 3 G M 0 1 X L UN / C GI 3 2 N I T 3 RH - V70 D A 2 B 8 G M C 1 X 2 X 7 E FS 2 E 0 l 7 T 2 RH - V4 0 A A 2 C 8 C C 3 X 2 3 8 E 2 V S RH - V3 5 C A 2 B 8 G M C 1 X L B A C 3 V RH - V35 C A 2 B 8 G M C 1 X 1 / 2 8 RH - V32 D A 2 B 8 G M C 1 X 2 X 7 00 1 C 0 5 5 RH - V31 D A 1 A 6 C C 1 X 1 3 X 2 1 1 08 1 C 0 5 RH - V30 C A 1 A 6 C C 1 X 1 3 X 2 1 1 O 1 C 0 5 N RH - V29 C A 1 A 6 C C 1 X 1 3 X 2 1 1 D 2 0 I RH - V26 C A 2 B 8 G M 0 1 X 2 X 3 &P 3 E RH - V22 B A 2 B 8 G M 0 1 X 2 X S L 2 E A RH - V21 B A 2 B 8 G M 0 1 X 2 X 5 VO 1 C 0 5 M RH - V1 5 D A 1 A 6 C C 1 X 1 3 X 2 1 1 ER 2 2 RH - V1 4 D A 2 B 8 G M 0 1 X 2 X 3 T A 4 7 RH - V4 A A 2 C 8 C C 3 X 2 3 E 1 2 E 2 L CBS - V56 C A 2 C 1 C C 3 X 3 3 6 AU 4 2 6 2 D CBS - V55 C A 2 C 1 C C 3 X 3 3 6 I SE Q L T Q L T Q R E E L E E L E T S R R A R R A R S E S ) E T E T S P I T T T T T T T T M E A N A Y N Y R S S S S S S S S E V N O L R I T O O E E E E E E E D S T L I I C O ( T P T T T T T T T N K S A D T G E A I S R Y V R C E E E V U M K K K R R R E A S O N D T Z L T R A A A E E E S. S T M O U O A I A C O E E E X X X O O E C F C C S V A N L L L E E E F P N R

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t n' s ENCIASIRE C r VALVE TESTING REQUIREMENTS NOTES 27. N/A 28. These valves cannot be exercised without the initiation of containment spray flow into the containment building quarterly during power operation or during cold shutdowns. These valves shall be partially disassembled, inspected, and manually exercised on a staggered s'ampling basis each refueling outage. (Relief Request V-27) F 29. This valve cannot be exercised by system flow without substantial amounts of water in the containment sumps being pumped by the containment spray and RHR pumps. This valve will be exercised during refueling outages by disassembly, inspection and manual exercise on a staggered sampling basis (Relief Request V-28) 30. This check valve is normally open during plant operation. Its function is to prevent reverse flow, and shall be tested during cold shutdown. It is impractical to shut down at three month intervals to perform a full closure test. (Relief Request V-6) 31. Exercising this valve during power operations is impractical and would align the charging pump suctions of the RWST which could cause a sudden increase in the reactor coolant system boron inventory. This valve be shall full-stroke exercised during cold shutdowns. (Relief Request V-26)

• 3 2.' N/A 33.

N/A 34. N/A 35. N/A 36. It is impractical to full-stroke exercise these valves on a quarterly basis because these valves are not in the pump test flow path. Thess valves cannot be full-stroke exercised during cold shutdowns because there is no flow path back to the RWST. Testing during cold shutdowns would require flow to be established into the RCS where there is no additional volume to add the additional inventory. These valves will be full-stroke exercised during refueling outages. (Relief Request V-31) (* - Relief Requests refer to relief requested in IST submittal to the NRC.) Rev. 1

'e; j ENCLOSURE C (rontinued) i i VALVE TESTING REQUIREMENTS NOTES i 60. Full flow through these valves quarterly during power operations would unnecessarily introduce' cold water into the steam generators causing thermal shock to the feed nozzles. These valves shall be full-stroke exercised during cold shutdowns. (Relief Request V-48) CO-V-340 is also partially stroked on a quarterly basis. e 61. This valve is additionally local leak rate tested in accordance with l 10CFR50 Appendix J, at least once every two years. r 62. These valves shall additionally have a backseat verification test perfcrmed each Refueling following all scheduled valve disassemblies or full-stroke exercises. Should the backseat verification test fail, a leak rate verification shall be performed to quantify the amount of i check valve leakage (30 gpm maximum allowable). f i n l l l I Rev. 1

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' Relief Reauest:- V-28 l .2 j' . Valves: CBS-V9, CBS-V15 CBS-V25, CBS-V26. CBS-V147, CBS-VJ.' l <l Catenorve C i I Code Classi-2 h. -{ }, Functions (Active) prevent backflow to the containment recirculation i ~ sumps f Test Recuirements: IWV-3520 (3 months) t Basis for Relief: These valves cannot be full-stroke exercised or partially exercised by system flow with substantial amounts'of water' ? in the containment sumps being drawn by the containment spray and residual heat removal pumps. Alternate Testinn These valves will be partially disassembled, inspected and n manually exercised on a staggered sampling basis (one valve i l in each group) each refueling outage. One group includes CBS-V9 and CBS-V15.' The other group includes CBS-V25, CBS V26, CBS-V147 and CBS-V148. At each disassembly, it l shall be verified that the disassembled valve'is-capable r full stroking and that its internals are structurally sound (no loose or corroded parts). In the event that a valve's i full-stroke capability is in question, the remaining valves in the respective group shall be disassembled, inspected. and manually exercised. J lt i 6 Rev. 1

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m[0 : v. [. I. lch e, 'y.l r. ,s t DICLOSURE E ,1 1 Relief Reauests-V-31 L ' Valves .CBS-V55 CBS-V56, CBS-V145, CBS-V146' l. Ca t e nory_i_ C' Code Class: 2 Function RHR Suction from the RWST (Active) 9 ? Test Reauirements: IWV-3520 (3 months) Basis for Relief ' .It-is impractical to full-stroke exercise these valves on a quarterly basis because these valves are not in the pump test flow path. These valves cannot be full-stroke l exercised during cold shutdowns because there is no flow path back to the RWST. Testing during cold shutdowns would require flow to be established into the RCS where there is not additional volume to add the additional inventory, b Alternate Testinni These valves will be full-stroke exercised during refueling 1..-< outages. ( 'r ly + l l l i 6 Rev. 1 3

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p :.*,[*5 C l c + 3 },a { i 1 i f g 8 hm This outline provides a proposed method for performing a backseat . verification test on the A train CBS/RHR system' interface check valves. LThe B train valves would be tested in a sLailar fashion. Should th ' backseat verification test fail, a leak rate verification would have to l be. performed ~to quantify the amount of check valve leakage (30 gpm maximum allowable) and corrective action performed as appropriate. - q lThis is.only an outline and is not meant to serve as a detailed test j procedure.; For convenience, a description of the ve.rious functions of 'l n; .the valves. listed in this procedure is'provided below, r CBS-V2' A Train'RWST Isolation A Train Containment Sump Isolation CBS-V8 CBS-V10 CBS-P-9A Suction Isolation A Train Containment Spray. Header Isolation CBS-V11 A Train CBS Sump Line Check Valve CBS-V26 'r LCBS-V31 ' CBS Recirculation Line Isolation CBS Recirculation Line Isolation CBS-V32 CBS Recirculation Line Isolation i CBS-V33 P' CBS-V55 A Train RWST Outlet Line Check Valve CBS-V93' High Point' Vent Valve downstream of CBS-V8 High Point Vent Valve downstream of CBS-V8 CBS-V127 A Train.RWST' Outlet Line Check Valve CBS-V145 CBS Swmp Line Check Valve CBS-V147 Bypass valve for CBS-V145 CBS-V153 Bypass valve for CBS-V145 CBS-V154 Bypass valve for CBS V55 CBS-V155 Bypass valve for CBS-V147 CBS-V156 Bypass valve for CBS-V147 CBS-V157 Bypass valve for CBS-V26 -CBS-V158 N ) J + 4 ('

f- ' * ], Y jf : *%t t g6. 1. A. Train CBS Suction Check Valys Backseat ' Verification Test >J -Q. n A. Prerequ* sites t i 1) The fall flow 18 month valve esercise surveillance required [ t 1) for CBS-V55 and.145, and'all required disassembly and C inspection tests scheduled to be perf ormed during the e current refueling outage on CBS V26 and 147. are complete. e ?? 2) C . Place or verify the valves listed below in the positions indicated r. a) CBS-V2 Open .g b) CES-V8s 10, 11. 31, 32, 33, 155, 154, 155, 156, 157 'and 158 -- Closed s. 3 )' A 0 - 500 psig'(minimum) pressure gauge is installed i between CBS-V153 and CBS-V154. l[ 4)- A 0 - 500 psis (minimum) pressure gauge is installed ll between CBS-V156 and CBS-V157. l gn:,yXJi: i d

5) Establish / verify t,he following conditions in the A train i

RHR systems {; j[ a) System pressure in suction line of RH.P-8A stabilised between 250 - 500 psig.- .L b) System temperature < 200'F. l i Note: The A train say be running on RCS recirculation [ flow path, be isolated from the RCS and pressurized 'l.. with a test pump or be unisolated from the RCS with r suction valves RC-V22 and R.? V23 open and RH.P-BA secured. q, Perform the following steps to verify A train test boundary [ B. 9 isolation valves (CBS-V2, CBS-V! and CBS-V10) are not leaking i sisch that unsatisfactory leakage on the check valves being ( . testing (CES-V26 CBS V55, CBS-V145 and CBS-V147) would be 6 undetected. .I i 1) Shut / check shut CES-Y2 2) Shut / check shut CBS-V8 f l

3) Shut / check shut CBS-V10 l

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r D .Q' e c' L 4) Shut / check shut CBS.V11

5) Shut / check shut CBS.V31, 32 and 33 i

6) Open/ check open CBS.V153, 134, 155, 156, 157 and 158.

7) Check boundary valve isolation capability by performing the following verifications after a minimum 5 minute l

hold period a) The A train CBS sump suction line has < 1 gpm flow into the sump or CBS.V8 is determined to be leak ( tight using acoustical monitoring equipment. ,s, b) The A train CBS system pressure is less than 100 psig and stable or CBS.V10 is determined to be leak tight l using acoustical monitoring equipment. ( c) CBS.V2 is determined to be leak tight using ( acoustical monitoring equipment. NOTE: For steps 7 (a), (b) and (c) above, ' leak tight' is defined to mean no detectable leakage. Should i the acoustical monitor detect any flow noise past the valve, that leakage must be verified to be within acceptable limits by using the alternate method of leak detection in steps 7(a) and/or 7(b) I or a leak test must be performed on the check valves to verify 130 gpm check valve leakage. i d) Perform a comprehensive walkdown of the CBS suction l piping bounded by check valves CBS.V26 and CBS.V55 j and gate valves CBS.V2. CBS.V8 and CBS. ',0. Verify that there is no leakage from the following vent, drain and relief valves:

1) CBS.V93. Vent Valve

2) CBS.V121. Orain Valve 3)

CBS.V127, Vent Valve i i

4) CBS.V141. Drain Valve

5) CBS.V169, Relief Valva

6) CBS.V151, Relief Valve i

2-

I } / h' ,i l' NOTE: Any leakage past the six valves listed in step 7d ) above would go directly to atmosphere and would be i inmediately apparent to the test engineer. I. 9) Shut CBS V155 and 158. j

10) Open CBS V10, 31, 32 and 33 to vet, the CBS system i

D back to the RVST. 11) Shut CBS V153, 154, 156 and 157. l C. Verify CBS-V55 and 145 (A train RWST outlet check valves) are backsested. i

1) open CSS-V153 and 154.

2) Close CBS V2.

Note: The above valve manipulations will establish a differential pressure across CBS-V55 to perform the backseat verification. i

5) Verify a minimum 50 psid pressure difference (botveen the l

RRR suction pressure and the test gage installed between CBS-V153 and 154) is present for at least 15 seconds after step 2 above is complete. {

4) Close CBS-V154.

5) Open CBS-V155 to bypass CBS-V55.

6) Cycle CBS-V2 open and close to relieve any residual line pretsure, t

Note: The above valve manipulations will establish a differential pressure across CBS-V145 to perform the backseat verification. 5 I

7) Verify a minimum 50 psid pressure difference (between the RER suction pressure and the test gage downstream of CBS-V153) is present for at least 15 seconds after step 6 l

above is complete. B) Close CBS-V153 and 155. l l r 9

,,., fi a 'A D. Verifying CBS-V26 and 147 (A Train CBS Sump Check Valves) are i backseated.

1) Open CBS V156 and 157.

i

2) Depressurize the upstream side of CBS.V26 by relieving residual pressure through high point vent valve CBS.V93 and/or 127.

3) Shut / check shut CBS-V93 and 127. Note: The above valve manipulation = will establish a differential pressure acre. CBS-V26 to perform the backseat verification.

4) Verify a minimum 50 psid pressure difference (between the RHR suction pressure and the test gage installed between CBS.V156 And 157) is present for at least 15 seconds after step 3 above is complete.

5) Close CBS.V157.

6) Open and CBS-V158.

7) Depressurite the upstream side of CBS-V147 by opening and then closing high point vent valves CBS-V93 and/or 127.

Note: The above valve manipulations will establish a differential pressure across CBS-V147 to perform the backseat verification.

8) Verify a minimum 50 psid pressure difference (between the RHR suction pressure and the test gage downstream of CBS-V156) is present for at least 15 seconds after step 7 above is complete.

9) Close CBS-V156 and 158. l l L l ~,n 9,w - w, n- 'w-n,- .m >,4 w -_ c \\ o l' ',s.L ' i l i i i i i ENCLOSURE G TO NYN.89131 -~

Q* d j' (- r. New Hampshire Yankee '"i October 30, 1989 l l I ANALYTICAL VERIFICATION OF BACKSEAT VERITICATION TEST l ACCEPTANC:: CRITERIA FOR CBS/RHR CHECK VALVES i l The acceptance criteria for the backseat verification test is that the check l valve disk must hold a differential pressure of 50 psi for at least 15 seconds. l Since the CBS system can accommodate a Rl!R to CBS check valve leakage of 30 gpa t with no adverse effects on the CBS piping system or the stress analysis, the NRC requested analytical verification that the test will detect leakage greater than 1 30 gpm. The change in volume to increase pressure from the RWST head to 50 psi below l the test pressure can be calculated using the following equations i Ln (V2 / V1) = A (T2

71) - B (P2 - P1) (1) 3 where V = Volume, it l

l T = Temperature. 'F A = Cubicle Expansion Coefficient, 1 / 'F P = Pressure, psia B = Isothermal compressibility Coefficient, 1 / psia. f The process is examined in reverse. That is, the volume is assumed pressurized to 50 psi below the test pressure and expanded to the RWST outlet pressure. The two volumes are subtracted to find the change in volume to increase the pressure to 50 psi below the test pressure. For Seabrook conditions the initial test pressure is 314.7 psia. This avoids lifting the thermal relief valve set at 325 psig. j V1 = 205 f t3 P1 = 264.7 psia P2 = 55.4 psia B = 3.15 x 10 -6 j p.g. This results in a final volume of 205.135 ft3 or a difference in volume of 0.135 ft3 or 1.1 gallons in 15 seconds. This is equivalent to 4.4 gpm. Thus, if the check valve disk leak rate is greater than 4.4 gpm, the valve will fail the test criteria. This ensures that the 30 gpm check valve leak rate used in the analysis will not be exceeded. 1 Ving Y. Vong, ' Safer Relief Valve Sizing', Chemical Ennineerina. May, 1989, pp. 137-140.

4 a i New Hampshire Yankee October 30, 1989 The backseat verification test for Train A will examine backleakage across the following check valves: CBS.Vlas CBS-V26. CBS-V55, CBS-V347. The method i. utilised consists of establishing approxinately 300 psig in the RHR suction piping and verifying that a minimum differential pressure of 50 psi exists upstream of the check valve being tested for at least 15 seconds following application of the test pressure. The calculation demonstrates that the maximum leakage allowed by the acceptance criteria for this test would be 4.4 gpm. providing a substantial margin below the maximum allowable of 30 gpm. It does this by assuming that the entire 205 ft.3(V1) of piping between the boundary valves CBS.V2, V10, V8, V145, & V147 is preesurized to the maximum acceptable pressure of 250 psig (P1) and calculating the additional volume (V2) of water required to increase the it.itial static pressure of 40.7 psig (P2) to P1 by the proceeding equation. The additional volume of water results from the slight compression of the initial volume within the piping, and results in an additional 1.1 gallon ot water. Since this leakage occurs in 15 seconds, this infers a leak rate of 4.4 gpm. The calculation above assumes that the test volume is leak-tight. Leakage from any potential leak path is detectable by visual means with the exception of the boundary gate valves, CBS.V2, V8 & V10. A system walk-down to visually detect leakage & acoustical monitoring of leakage beyond CBS V2, V8 & V10 will be performed as part of the test procedure. The margin between the umrimum allowable check valve leakage and leakage detectable by the test, assuming no boundary leakage, is over 25 gpm. This indicates that concurrent leakage of over 8 gpm per boundary gate valve will not mask unacceptable check valve leakage of 30 gpm. Since 8 gpm flow is readily detectable by acoustical means and leakage from any other point will be visually detected and isolated, the test will verify conclusively that backleakage of 30 gpm does not exist. I l

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n ENCLO5tRE Z-o FIGURE 5.3-VALVE TESTING REQUIREENTs SYSTEM - SAFETY IK3ECTION HIGt HEAD P&ID NO. 805010/1-51-870446 l lC C C C C C C a a a a s s s s s s s sl s s s s s s 's s s C s s s s s C a s s '8 8 8 8 s s s H H H H I I I I I I I I I I I I I I I I I B I I I I I B M I I s s 5 s 5 s V V V V V Y Y V V V V V V V V V V V V V V V V V V V V V V V V V V V V V 4 4 4 5 5 5 5 7 7 8 8 8 8 8 9 9 9 1 1 1 1 1 1 1 Y 8 9 1 1 1 V 4 1 1 VALVE 4 4 5 5 6 6 7 0 1 2 3 1 7 1 2 6 7 9 0 3 6 0 0 1 1 1 1 1 4 8 1 2 2 3 5 9 3 3 7 8 1 2 0 1 5 2 6 0 1 2 4 8 9 2 6 0 3 1 4 COORDINATES 81_81 82 C4 81 81 81 C3 83 C4 C4 82 83 84 84 84 84 82 C2 81 C2 C3 C3 C3 82 C2 83 A3 81 82 82 A3 A4 A4 82 83 83 83 FUNCTION A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A' A A A A A CODE CLASS 2 2 2 2 2 2 2 1 1 1 1 2 2 1 1 1 1 2 2 2 2 2 1 1 2 2 2 1 2 2 2 1 1' 1 2 2 2 2 CATEGORY B C 8 C 8 8 8 AC AC AC AC C 8 AC AC AC AC 8 8 8 C 8 AC AC 8 8 8 AC 8 C C AC AC AC 8 8 8 8

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3/ 3/ 3/ SIZE (IN.) 8 8 8 8 6 6 6 8 8 6 6 4 4 2 6 2 6 5 5 2 4 4 2 2 4 4 4 2 6 2 2 2 2 2 6 4 4 4 VALVE TYPE G C G C G G G C C C C C G C C C C GL GL GL C G C C G G G C G C C C C C G GL E GL ACTUATOR M M M M M M M M M M M M M M M' A A A NORM POSIT 0 C 0 C C C 0 C C C C C C C C C C 0 0 0 C C C C 0 0 0 C 0 C C C C C 0 C 'C C LEAK TEST REQ 1 1 1 1 1 1 1 1 1 1 1 1 1 1 LEAK TEST REL X X X X X X X X X X X X X X LEAK TEST ALT 1 1 1 1 1 1 1 1 1 1 1 1 1 1 EXER TEST REQ 1 3 1 3 1 1 1 3 3 3 3 3 1 3 3 3 3 1 1 1 3 1 3 3 1 1 1 3 1 3 3 3 3 3 1 1 1 1 EXER TEST REL X X X X X X X X X X X X X X X X X X X X X X X X EXER TEST ATL 2 3 2 3 3 3 3 3 3 2 3 3 3 3 2 3 2 3 3 2 3 3 3 3 F.S. TEST REQ X-X X POS IND TEST X X X X X Y. X X X X X X X X X X X X MOTES: 18 39 18 39 10 10 10 10 7 10 10 10 10 7 10 10 18 10 10 10 10 40 40 40 40 41 19 19 19 19 41 19 19 19 19 19 15 63 63 63 63 63 63 63 63 l REMARKS: Rey _ 1 ,___,.._.,,,_..._____._________..__m

n, -u 1 .4 c (. i l i i I l i l i t i l i i i l. i I, ) 4 ENCLOSURE J TO NYN-89131 'l 1 i l 1 f, t 4 i i I i s ( 1 [

m: ENCLOstRE 7 VALVE TESTING REQUIREMENTS NOTES j \\ 1. The frequency and quantity of safety valves subject to test at each refueling outaga is in accordance with Section XI. IWV-3500. j l 2. Valve full closure time on any closure actuation signal will be j l verified while in hot standby during each reactor shutdown except j

t. hat this verification need not be determined more than once per 3 sienths for multiple shutdowns. Shutdown will not,be required for the sole purpose of performing the full closure test. As an alternative the valve will be part stroked every 3 months.

(Relief Request V-1 and V-4) L. 3. N/A ( 4. This valve will be exercised during cold shutdowns since operation of l this portion of the feed system will introduce cold water into the i F steam generator feed nozzles. (Relief Request V-2 and V-5) 5. N/A 6. N/A 7. The valves are required by technical specifications to be shut and power removed from their operators during Modes 1, 2, 3. They will be full-stroked exercised during cold shutdown. (Relief Request V-13) 3. Opening this valve during operational modes other than cold shutdown is prohibited by tech specs. This valve will be exercised during cold shutd owr.s. (Relief Request V-7) 9. N/A 10. This valve is a boundary valve between high-pressure RCS piping and adjacent low-pressure systems. As such, it is Category A and/or AC per IWV-2200. It will be leak tested in accordance with technical specifications. (Relief Request V-10) 11. This valve will be exercised during cold shutdown. (Relief Request V-11) 12. N/A 13. Full stroke exercise tests of these valves shall be performed during each cold shutdown. (Relief Request V-12) 14. N/A (* - Relief Requests refer to relief requested in IST submittal to the NRC) Rev. 1

~ ng 2 O .o BCLOSURE 7 (contimwd) ) \\ VALVE TESTING REOUIRDiERTS NOTES (continued) J 1 15. Quarterly full stroke exercising this normally closed check valve would require that reactor coolant system pressure be below RHR pump discharge pressure. This valve will be verified as operable during i L cold shutdowns. (Relief Request V.15) l 16. N/A 17. N/A L 18. This normally open valve is in the position required for accident i t conditions and, per technical specifications, must remain open during j power operations. These valves shall be full-stroke exercised during cold shutdowns. (Rellef Request V-14) 1 19. Exercising this valv,e requires flow to the RCS using the sciety j injection or residual heat removal pumps. During operation, RCS pressure will be higher than pump discharge pressure. As an i alternative, this valve will be exercised at refueling outages. J (Relief Request V-18) 20. Exercising this valve requires initiating flow to the RCS using the charging pumps. If charging flow was directed to the RCS in this manner, it could create a loss of charging flow control during normal operation resulting in pressurizer level changes and possibly a plant trip and cause low-temperature overpressurization of the RCS during cold shutdowns. As an alternative, this valve vill be exercised at refueling outages. (Relief Request V-20) 21. This valve cannot be exercised during power operation when charging system is in operation. It will be exercised at cold shutdowns. (Relief Request V-21) l i 22. To protect reactor coolant pump seals, flow to them is required at all times during power operation and startup. It will be exercised during cold shutdowns when risk of equipment damage is eliminated by se<:uring the pumps. (Relief Request V-22) 23. N/A 24. Exercising this valve during power operations could cause e sudden increase in RCS boron inventory. It will be exercised at cold shutdown when the RCS is already borated to, shutdown conditions. (Relief Request V-24) 25. N/A 26. Exercising these valves could isolate cooling water to many vital components, in the event a valve were to fail in the closed position. These valves will be exercised during cold shutivn when non-essential loads can be isolated. (Relief Request V-25) (* - Relief Requests refer to relief requested in IST submittal to the NRC) l Rev. 1

$s j.r DCL0$153.7 (contit.ued) l* ':F YALVE TESTING REOUIRDENTS NOTES (continued) l 60. Full flow through these valves quarterly during power operations would l unnecessarily introduce cold water into the steam generators causing i thermal shock to the feed noaales. These valves shall be full-stroke l exercised during cold shutdowns. (Relief Request V-48) CO.V.340 is also partially stroked on a quarterly basis. 61. This valve is additionally local leak rate tested in accordance with l 10CFR50. Appendix J. at least once every two years. l 62. These valves shall additionally have a backseat verification test l L performed each Refueling following all scheduled valve disassemblies or full-stroke exercises. Should the backseat verification test fail, t l a leak rate verification shall be perfortned to quantify the amount of [ check valve leakage (30 gpm maximum allowable). l 63. Full or partial stroke exercising of these check valves during cold shutdowns would be impractical since it would require removal of the l reactor vessel head. Check valve disassembly and' inspection shall be l used to verify ILg.h valve's capability to be full stroke exercised. In addition, radiographs shall be performed on tish reassembled check i, valve te verify proper valve hternals orientation. This is a 'One Time' application (1989 Outage) and future testing shall be performed in accordance with ine approved IST program plan (Reference Relief Request V-18) (calief Request V.49). i i I i f f I Pev. 1

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IN ~ ' ' 1 ] o DICLOSURE 6 i I h' - H Relief Recueste V.10 l Valves RC.V22. RC.V23. RC.V88 RH.V15. RH.V29. RH.V30. RH.V31, SI.V6. SI.V21. SI.V36, SI.V51 RH 750 RH.V50, RH.V51, s f RH.V52. RH.V53 SI.V81. SI.V82, SI.V86, SI.V87, 61.V106, t SI.V110. SI.V118, SI.V122. SI.V126, SI.V130, SI.V140, I j SI.V144, SI.V148, SI.V152 SI.V156, $1.V5, SI.V20, SI.V35, [ SI.V50 t ? Categorvt A/C and A j Code Class 1 l o l ,h Function Reactor coolant pressure isolation valve t Test Renuirements: IWV.3420 (2 years) tasis for Relief These valves are reactor coolant pressure isolation valves and vill be leak tested in accordance with Technical i specifications Section 4.4.6.2.2. These valves are Category i F A per IW.2200. I Alternate Testine: Each reactor coolant pressure isolation valve shall be demonstrated operable by verifying leakage to be within its l limit a. at least once per 18 months: b, prior to entering Mode 2 whenever the plant has been in cold shutdown for 72 hours or more, and if leakage testing has not been performed in the previous 9 months: c. prior to returning the valve to service following l maintenance, repair or replacement work on the valves and d. i within 24 hours following valve actuation due to automatic or manual action or flow through the valve. I Rev. 1

s sp,; gg, s n pr ov >% + r 1 A e .k O.., sb q e .r. .(T 5 1 e, .(.\\C \\ e ( .i t1 ENCLOSURE L TO NYN-89131 t h-c 6 frh

J,a anciastasI.- Relief Recuesti V 18 i Valvest SI.V118. SI.V122, $1.V126. SI.V130. $1-V106. SI.V110, T SI.V81. SI.V82. SI.V86 $1 V87 u. Catenorve AC/C i Code Class: I and 2 Funetfon (Active) reactor coolant pressure isolation valves i Test Recuirereatti IWV.3520 (3 months) l r 111 s for Relief: Erercising these valves per the frequency described in IWV. 1 3S?0 is not practical. Exercising these valves during plant operation would require initiating flow to the reactor coolant system using the safety injections pumps. During l plant operation..the reactor coolant pressure will be greater l than the safety injection pump discharge pressure. These valves cannot be exercised during cold shutdowns because SI t pump flow could possibly risk low-temperature overpressurization of the RCS. p Alternate Testine These valves vill be full-stroke exercised during refueling outages. l i I f i i L i ? i L Rev. 1

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1. .o l l 'I $NCLOSURE Af 1 i ? O m f.I Relief Reauesti V.49 Valvest. SI.V81, SI.V86, SI.V106, SI.V110, 61-V118, SI-V122, l SI-V126, SI.V130 j l Categorvi AC j i i Code Classi 1 Functioni (Active) Reactor coolant pressure isolation valves l Test Recuirements: IWV-3200. IWV.3520 i Basis for Relief: During the Low Power Test Program, leakage was observeo l through the above listed Safety Injection System valves. l Subsequently, these valves were repaired and/or replaced. l Full or partial stroke exercising of these check valves during cold shutdowns would be impractical since it would require removal of the reactor vessel head before a safety t injection pump can flow to the vessel (low-temperature overpressuriaation of the RCS). Vessel head disassembly is an extremely arduous process that would significantly impact the current schedule. The inability to exercise these check valves on a quarterly frequency and during i cold shutdowns has already been identified in Relief L Request V-18. Check valve disassembly and inspection in accordance with USNRC Generic Letter 89 04 shall be i used to verify each valve's capability to be full stroke exercised. In addition, radiographs shall be performed [ on eigh reassembled check valve to verify proper valve internals orientation. Also, leakage tests (PIV) shall I be performed in accordance with the IST program plan, (Reference Relief Request V-10). This is a 'One Time' l relief request (1989 Outage) and future testing shall be performed in accordance with the approved IST program plan, (Reference Relief Request V-18). j t Alternste Testinni Each check valve shall be disassembled, inspected and manually exercised during the 1989 Outage. Each valve shall be verified that it is capable of full stroking i and that its internals are structurally sound (no loose or corroded parts). In addition, radiographs shall be performed on each reassembled check valve to verify proper valve internals orientation. Alro, leakage tests shall be performed in accordance with Relief Request V-10. This is a 'One Time' relief request and future testing shall be performed in accordance with the IST Program Plan. 1

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