ML20070L677

Forwards Summary of Changes to Rev 1 of Inservice Testing Program.Piping & Instrumentation Diagrams of Sys Which Contain Components Affected by Changes Also Encl

ML20070L677
Person / Time
Site:	Seabrook
Issue date:	03/11/1991
From:	Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-91039, NUDOCS 9103200155
Download: ML20070L677 (35)

Text

{{#Wiki_filter:. _ _ _ _ _ New Hampshire Ted C. Feigenbowm President and Chief Czecutwe Officer NYN. 91039 March 11,1991 United States Nuclear Regulatory Commission Washington, D.C. 20555- . Attention: Document Control Desk

References:

(a) - Facility Operating License No, NPF 86, Docket No. 50 443 i .(b) USNRC Letter, dated April 3, 1989, ' Guidance on Developing Acceptable Inservice Testing Programs (Generic Letter No 89 04)' s Subjectt ' Inservice Testing of Pumps and Valves (Changes to Revision 1) Gentlemen: i Pursuant to 10CFR50,55a(g)(5)(1) and the Seabrook Station Safety Evaluation Report LSu(,plement 6, Appendix S, New Hampshire Yankee (N!!Y) hereby transmits changes to Revision 1 of the NHY laservice Testing Program (IST). Enclosure 1 contains a summary = of the changes to the NHY IST Program as provided in Enclosures 2 through 7. Enclosures 8 through 12 provide copies of NIIY Piping sad Instrumentation Diagrams (P&lDs) of the systems which contain the components affected by the criclosed NHY IST Program changes. , These P&lDsiare provided for informationa! purposes only and are not for inclusion la the NHY. IST Program. The' changes.provided in Enclourcs'_2 through 5 do not request' relief from the testing requirements of. ASME XI, subsection IWV, and therefore, do not require prior NRC-approval. The. changes provided in Enciosures 6'and 7 do, however, require such relief, and thus will'not;be lmplemented priorLto receipt of NRCl approval. In order to support the s current refueling -outage testing schedule, it is requested that your review and approval be? E - completed by Junc 3,1991,- ~ / Should you have questions regarding this information, please contact Mr. James M. 'Peschel, Regulatory Comp!!ance Manager, at (603) 474 9521, extension 3772. Very truly yours, h# Ted C. Peigenbaum TCF:JES/act Enclesures 9103200155 910311 gDR. ADOCK 05000443 PDR New Hampshire Yardee Division of Public Service Company of New Homphire g/ gy(j'][ P.O. Box 300

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

t i United States Nuclear Regulatory Commission March 11,1991 Attention: Document Control Desk Page two ec: Mr. Thomas T. Martin Regional Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. Gordon E. Edison, Sr. Project Manager Project Directorate 13 Division of Reactor Projects

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U.S. Nuclear Regulatory Commission Washington, DC - 20555 Mr. Noel Dudley NRC Senior Resident Inspector P.O. Box 114v Scabrook, NH - 03874 b I l l l-1

y t 2 New llampshire Yankee March 11,1991 ENCLOSURE 1 TO NYN-91039 e 'I

e

SUMMARY

OF CilANGES TO REVISION 1 OF TilR IST PROGRAM l ENCLOSURE DESCRIPTION OF CllANGE 2 Fevises NilY IST Pregram Figure 5.3, Valve Testing Requirements, to delete Main Steam Jystem isolation valves MS V127 and MS V128. These containment aclation valies are currently installed dth air operators. Per DCf. 90 032, the air operators are to be rep.=ced with manual haudwheels during the upcoming refueling outage. As provided by ASME XI, st.bsection IWV 1200 (a), valves used only for rnalntenance are exempt from the scope of IWV. The safety funnion that these valves.... form will be provided by Main Steam System valves MS V393 and MS V394. This enclosure also revises Figure 5.3 to upgrade MS V393 and MS. V394 to safety Class 2. This enables these valves to satisfy GDC57 containment isolation requirements. See N!!Y P&lDs IA 20644 and I A-20645, Enclosures 8 and 9, respectively. 3 Revises NilY IST Program Plgure 5.3 to include Instrument Air check l valves IA V547, IA.V548, IA V549 and I A V550. These valves separate the safety grade air supply to Main Steam System valves MS Y393 and MS V3M from the plant alt system. See NiiY P&lDs IA 20644 and IA. 20640, Enclosures 8 and 10, respectively. This onclosure also revises Figurn 5.3 to include lostrument Air check valves IA V545 and IA V546. The*e valves isolate the non safety grade air supply to Main Steam System valve MS V395 from the plant air system. MS V395 provides steam to the steam driven emergency feedwater pump. See NilY P&lD IA 20644, Enclosure 8. 4 - Revises N!!Y IST Program Figure 5.3 to include Instrument Air check l valves IA V8030, IA 8031, IAeV8032 and IA VR033. These valves isolate the non saf sty grade alt supply to temperature control valves in the i Primary Component Cooling Water System from the safety grade alt j system. See NHY P&lD IA 20540 Instrument Air Primary Auxiliary Dullding Detall (Enclosure 10) and 1 NilY 506212 (Enclosure 11). 5 Revises NIIY IST Program Figurc 5.3 to remove Safety injection check valve St V297 from the IST Program. A system modification (MMOD. 'l 9SG598) will be_ implemented to remove the internals from this check valve during the upcoming refueling' outage. The valve internals are to be removed from this valve _ because curlier plant designs required ' j that this valve isolate the high head safety injection line during boric acid injection tank (BIT) actuation. Since the BIT system is not in the current plant design, SI V297 no longer is required to provide a safety function. This will exempt SI V297 from the scope of ASME XI, i subsection IWV. See NilY P&ID SI 20447, Safety injection System Ifigh IIcad injection System Detail (Enclosure 12). i I g L I

ENCLOS M DESCRIPTION OF C11ANGE 6 Revises Relief Request V 42 to include the use of a non intrusive test during certain low flow conditions to determine if a forward full stroke excrelse is achievable. 7 Revises Valve Testing Requirements Note 52 to be consistent with revised Relief Request V.42 provided in Enclosure 6. 1 i l \\l

New llampshire Yankee March 11,1991 ENCLOSURE 2 O NYN 91039 a W

i i _,y FIGURE 5.3 VALVE TESTING REQUIREMENTS I ~ SYSTEM: MAIM STEAM P&lD NO. 202074/202110 VMVE: M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M M' S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S SlS P P P P 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 V V V V V V V V 6 7 8 9 1 2 2 2 2 2 3 3 3 3 4 5 5 5 5 5 8 8 9 9 9 9 2 2 2 2 3 3 3 I 3 3 3 3 0 2 3 4 5 6 6 7 8 9 0 0 1 2 3 4 6 8 0 2 4 6 0 0 0 0 9 9 9 0 0 0 0 4 5 6 7 3 4 5 0 0 0 0 1 2 3 4-i i D2 D2 C2 B2 A2 D2 C3 B3 C2 B2 A2 ' 02 C3 B3 D4 COORDINATES: C4 B4 A4 D4 C3 C3 C3 C2 C2 B3 B3 B3 B2 B2 A3 A3 A3 A2 A2 D3 03 03 FtmCTIOM: 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 2 2 2 2 2 2 2 2 2 2 2 2 2l2 2 2 2 2 2 2 2 3 3 2 2 2 2 2 2 3 CATEGORY: B B B B C C C C C C C C C C C C C C C C C C C C B B B B C C B B B B B B B SIZE (IN): 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 to 10 10 10 30 30 30 30 4 4 4 4 4 4 4 4 4 VALVE TYPE: GL GL GL GL 5 S S S S S S S S S S Sl5 S S S S S S S G G G G C C GL GL CL GL GL GL GL l ACTUATOR: P P P P -g_ P P P P M M M M A A A f NORM POSITIOM: C C C C C C C C C C C C C C C ClC C C C C C C C 0 0 0 0 t C C C C C C C C LEAK TEST REQ: ( LEAK TEST REL-l LEAK TEST ALT: i EXER TEST REQ: 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 1 1 1 1 3 3 I I I 1 1 1 1 EXER TEST REL: X X X X X X l 4 EXER TEST ALT: 2 2 2 2 2 2 l F.S. TEST REQ: X X X X X XlX 8 POS IND TEST: X X X X I X X X X X X X X X X NOTES: 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 50 50 51 51 REMARKS: 4 Rev 1 4 y

New llampshire Yankee March it,1991 i EtifqkOStJRi? 3 TO NYN 91039 p I i- __l i 3 ol-

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New llampshire Yankee March 11,1991 Y d 1 i ENCL.OSURE 4 TO NYN.91039 . r i i }.. l. . 1 I l {' l.

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o i New llanipshire Yankee ~ March 11,1991 S t i ENCLOSURE 5 TO NYN 91039 k-I i -[ l' l r yr,, ...w., a

'~ TIGURE 5 3 YALVE TESTI E REQUIREMENTS SYSTEM: SAFETY INJECTION HIGH HEAD.PSID NO. 805010

• E Y P810 1-51-820447 j

I I i VALVE: S S S S S S S S S S I I I I I I I I I I -I-Y v v v v v v v v v I 1 1 1 1 1 I I 1 1 3 3 4 4 4 5 5 5 5 6 'l 8 9 0 4 8 2 6 7 8 0 C00RDiftATES: G5 G6 C3 04 D4 D4 C4 C3 D3 C3 FUNCTION: A A A A A A A A A A CODE CLASS: 2 2 1 1 1 1 1 2 2 2 AC AC AC AC B B B CATEGORY: B B. AC i SIZE (IM): 4 4 3 1.5 1.5 1.5 1.5 3/4 3/4 3/4 VALVE TYPE: G G C' C C C C GL GL GL <1 ACTUAT(R: ft M A A A S NORM POSITION: C C C C C C C C i ': C LEAK TEST REQ: 1 1 1 1 1 2 g LEAK TEST REL: X X X X X LEAK TEST ALT: 1 1 1 1 1 EXER TEST REQ: 'l 1 3 3 3 3 3 1 1 1 EXER. TEST REL: X X X X X X X EXER TEST ALT: 2 2 5 ~3 3 3 3 f F.S. TEST REQ: X X X q i POS IND TEST: X X X X X j ~ i NOTES: 64 64 10 10 10 10 10 20 20 20 20 20 1 t REMARKS: i I + Rev 1 4 s y 4 ' i 0 ~ _ - -

4 1 i New Hampshire Yankee March 11,1991 ENCLOSURl! 6 TO NYN.91039, ..,,.,-.n.. ~, -.,-.n,. ,,,m.,-

Relief Reauest: V-42 Valves: Group 1 (Safety injection Accumulator Check Valvesit V6, V21, V36, V51 Group 2(Combined $1/RHRCheckValves)1 VS, V20, V35, V50 Cateoory: AC Code Cicss: 1 (Active)CombinedSafety(forwardflow),ReactorCoolant functions injectionAccumulatorandRHR injection check valves PressureBoundaryIsolationValves(reverseflow). Tet,t Reuuirements IWV-3520(3 months) Basis for Relief: Group 1 valves cannot be full-stroked exercised with flow quarterly during power operation because the Matyinjectionaccumulatorshaveinsufficient .;sure to flow into the RCS. Additionally, Group 2 valves cannot be exe4cised quarterly during power operation because the RHR pumps have insufficient pressure to flow into the RCS. Group 1 valves cannot be f ull-stroked exercised with flow during cold shutdowns because of the restrictions placed on the ectumulator isolation valves (S! V3, SI-V17,SI-V32,andSI-V47). The accumulator isolatica valves (see CSJ-4) cannot be exercised in Mode 4, or inMode5whentheaccumulator(s)arepressurized above 100 psig, as they are required to be closed, withpowerremovedfromtheiractuator(s)bytheplant Technical Specifications. 51 flow from the accumulators could also risk low-temperature overpressurization of the RCS. Group 2 valves cannot be full-stroked exercised during cold shutdowns as there is not sufficient flow using the RHR pumps to full-stroke the valves. Group 'c valves will be partially stroked during cold shutdowns.

1 ( Alternate Testino These valves will be monitored with a non-intrusive test during certain flow condittors in order to determine if a forward full stroke exercise is achievable. Group 1 valves will be monitored during low pressure accumulator blows (all valves each refuelingoutage). Group 2 valves (allvalves6ach refueling outage) will be monitored either by using RHR or during the is pressure accumulator blows. In addition to the non-intrusive testing, reactor cc:' "' pressure isolation valve leakage testing will cora e to be .ed to verify reverse closure at the frega.:cies specified in the plant technical specifications. If non-intrusive testing is inconclusive in demonstrating a forward full stroke exercise, then a partial disassembly, inspection and examination by sampling program will be used. One valve from each group s1all be partially disassembled, inspected, and manually exercisci on a staggered basis each refueling outage. At disassembly, it shall be verified that the disassembled valve is capable of full stroking and that its internals are structurally sound (no loose or corrodedparts). In the event that the disassembled valve's full stroke capability is in question, all valves in this group will be disassembled.

New llampshire Yankee 3 March 11,1991 ENCLOSURE 7 TO NYN 91039 P 4 9 ,..,,wr

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l. 49. These valves are not provided with power operators, therefore, the measuring of stroke time is not measured for these valves. 50. During quarterly pump testing of the EFW turbine pump, there it insufficient flow to full-stroke exercise these valves in accordance with the requirements of the Code. These valves are partially stroked during the quarterly pump test. These valves shall be full-stroke exercised during plant cooldown to cold shutdown or heatup from cold shutdown when there is sufficient steam available to full-stroke exercise these valves. (Relief Request V-il.) 51. These valves shall additionally be tested to closed position because they are required to close in the event of a main steam line break. 52. These valves cannot be full-stroke exercised quarterly during power operation, or during cold shutdowns. Forward full stroke exercise will be demonstrated each refueling by either monitoring)the valve with non-intrusive test ins +rumentation (acoustic monitoring during certain flow conditions or by oisawembly and examination on a staggered sampling basis. Reverse closure demonstration will be satisfied by pressure isolation valve seat leakage testing. (ReliefRequestV42.) 53. These valves shall be partially stroked during cold shutdowns. 54. N/A 55, it is impractical to measure the limiting value of full-stroke time of these valves. The safety function of these valves is to open to support the startup of its respective diesel to provide rated frequency and voltage in less than 10 seconds. Successful startup of each emergency diesel generator within the above s)ecified conditions is dependent upon the proper operation and speed of t1ese valves. Additional Code required full-stroke time measurement of these valves will not increase the assurance that the diesel generators will start as required. Upon failure of the diesel generators to start as required, corrective action shall be taken to assure proper diesel startup condition. (Relief Request V-44.) 56. Exercising these valves at any periodic frequency is impractical. The primary function of these valves is to modulate to control the temperature and pressure of the cooling water nf each emergency diesel generator. Code required full-stroke exercising of these valves would not verify the operability of these valves. Periodic operation of the diesels verifies operability of these valves. These valves are included in the inservice test program because of their fail-safe function. These valves shall be verified on a quarterly basis that they fail to maximum rooling position upon loss of actuator power. (ReliefRequest V-45.) 57. These valves shall additionally be full-stroke exercise tested open. (* - Relief Requests refer to relief requested in IST submittal to the NRC.)

a 1 New item), shire Yankee March 11,1991 ~; 1 ENCL,OSURE 8 TO NYN.91039 b P 1 T

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