ML20246A104
| ML20246A104 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 05/01/1989 |
| From: | George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-89052, NUDOCS 8905080172 | |
| Download: ML20246A104 (13) | |
Text
{{#Wiki_filter:_ - _ - _ _ - i gPgg George S. Thomas vice r,.,io.ni.wuci.o, eroe,c, ion Yankee i NYN-89052-May 1, 1989 United States Nuclear Regulatory Ccmnission 3 Washington, DC 20555 . Attention: Document Control Desk
References:
(a) Facility Operating License NPF-56, Docket No. 50-443 H l (b) NHY Istter NYN-89032, dated March 30, 1989, " Licensing I Itms Status Sumary"', G. S. '1homas to USNRC l J (c) USNRC Istter, dated October 1987, " Safety Evaluation Report Related to the Operation of Seabrook Station Unit 1 and 2 Supplement 7", NUREG-0896
Subject:
Residual Heat Reoval/ Containment Building Spray Systen Interface Gentlenen: In Reference (b), New Hanpshire Yankee (NHY) ccumitted to subnit by. April 30, 1989, a description of the Residual Heat Removal (RHR)/ ~ Containment Building Spray (CBS) Systems interface design tyyada. h design upgrade, which is sumarized in the enclosure, s.vyoses to add four additional check valves in series with each of the four existing check valves which provide isolation at the RHR/CBS systen interface. N I addition of redundant check valves will provide effective pressure isolation between the RHR and CBS systes as required by the current guidelines of the Boiler and Pressure Vessel Code of the American Society of Mechanical Engineers and will have minimal impact on system performance and operation. '1his design upgrad9 description is being subnitted for.NRC - Staff review and approval, prior to implementation, per our previous ccanitment..'1he design upgrade does not introduce an unreviewed' safety-question as defined by 10CFR50.59 requiring pre-implementation review. In the Seabrook Station Safety Evaluation Report Supplanent'7, the NRC j. Staff reflected NHY's ccanitnant to cnrplete long term actions to address this item prior to startup frm the first refueling outage. Upon receipt-of NRC approval of its proposed design upgrade, NHY intends to expedite its i 8905080172 890501 R P PDC [)(/ PDR-ADOCK 05000443 v New Hampshire Yankee Division of Public Service Company of New Hampshire I P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474-9521
]
- ___==_---__
0
-a a United States Nuclear Regulatory Comission May 1, 1989 Attention: Document Control Desk Page 2 implementation and will endeavor to improve upon the accepted implemen-tation schedule (prior to startup fran the first refueling outage). In support of an expedited implanantation schedule, NHY requests that the NRC l Staff review and approve the enclosed information by May 31, 1989. Should you require further. information regarding this matter, please contact Mr. Robert E. Sweeney in our Bethesda Licensing Office at (301) 656-6100. Very truly yours, .4'yb MrkO George S. Thanas Enclosure cc: Mr. William T. Russell Regional Administrator l United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Victor Nerses, Project Manager Project Directorate I-3 United States Nuclear Regulatory Ccmnission Division of Reactor Projects Washington, DC 20555 Mr. David G. Ruscitto NRC Senior Resident Inspector P. O. Box 1149 Seabrook, NH 03874 l l .\\ l i i
j ENCOSURE 'IO NYN-89052 ENIADMENP BUIIDDG SPRAY / RESIDUAL HFAT REKNAL SYSTEMS INPERFACE BTCKGROUND: Isakage frm the Residual Heat Raoval (RHR) System into the Containment Building Spray (CBS) Syst s was observed in Nov mber-December 1986. In letters to the NRC on May 20, 1987 (NYN-87069) and July 1, 1987 (NYN-87085), NHY provided an evaluation of the systs interface and cmmittec to both short term and long term design enhanc m ents. References to both the short and long tem enhancements have been included in the Seabrook Station Safety Evaluation Report, Supplment 7. In 1987, NHY analyzed the effects of check valve leakage on the CBS System and implemented the short tem enhancements which included upgrading the CBS suction pressure to 350 PSIG and installing a leak detection /nonitoring systs in the CBS Systs. In addition, NHY cmmitted to implementation of one of the following alternative long term actions prior to startup frm the first refueling outage - Upgrade the CBS design pressure and tmperature to RHR suction 0 conditions (470 PSIG/350 F), or Add redundant valves in series with the existing check valves separating the RHR and CBS Syst a s. 'Ihe above two alternative long term actions ccmply with the current ASME Section III Code requirements which apply to connected piping systems operating at different pressures (NC-3612.4). These alternatives represent an enhancement over the requirements of the original code of design. In evaluating the alternatives, an important consideration was that leakage frm the RHR System (suction side of the RHR pump) into the CBS Systs across the interfacing check valves is a concern only during plant hot shutdown operation (Mode 4) when the RHR System is aligned to the Reactor 0 F Coolant Syst s (RCS) and the RCS taperature ir between 200 F and 3500, which occurs infrequently and for a short duradan. During operational modes (i.e., Modes 1 and 2) and during hot stas q conditions (Mode 3), the RHR System is isolated frm the RCS, depressurned and at ambient tmperature. DESIGN CHANGE
SUMMARY
DESCRIPI' ION: New Hampshire Yankee has determined that the addition of redundant check valves is the preferred alternative. This configuration meets current ASME Code requirements, provides effective system isolation, and has minimal impact on syste performnce. The piping thermal nonitoring system (PIMS) installed as one of the short term actions will be retained as an operator aide.
As shown on the attached NHY P&ID l-CBS-B20233 and drawing 1-NHY-804979, each train of the RHR and CBS Systes interface in two locations. One interface location is in the ccnnon suction line frm the Refueling Water Storage Tank (RWST) and the second interface location is in the ccnnon suction line frm the containment recirculation sump. We present syst s configuration utilizes a 12-inch 300# and 16-inch 600#, ASME III, Class 2, 316 stainless steel swing check valve in the cuanan suction lines frm the RWST and containment recirculation sump, respectively, for system isolation. %e design change will install four duplicate valves in series with four existing valves and extend the RHR design conditions through the new valves. %e four additional valves, which were originally supplied for Unit 2, are identical to those installed and cmply with all the original design requirements. In addition, a pressure relief valve will be installed within two feet of each new check valve in the CBS System. All design and installation work will cmply with the original design and construction code requirements. The redundant check valves will provide effective pressure isolation between the RHR and CBS Systems with minimal impact on system perfomance, as discussed below, and do not require additional electrical or mechanical controls. Operability of the added valves will be verified utilizing the same testing requirements which apply to the adjacent existing valves. %e inservice testing requirements for the installed valves are reflected in Safety Evaluation Report Supplement 6 including Appendix S which explained the bases for the testing. Annotated pages frm FSAR Table 3.9(B)-23 are attached to identify the proposed specific inspections for the check valves. The additional relief valves are ASME III, Class 2, with a set pressure of 350 PSIG, the design pressure of the CBS System. %e capacity of the relief valves is 30 GPM which exceeds the anticipated maximum upset or e ergency leak rate through the two check valves in series. Se CBS Syst s relief valves CBS-V94/V96 are also available, thereby doubling the relieving capacity. In addition, the piping themal nonitoring system (PIMS) is available to alert the operator to isolate the affected RHR train upon receipt of a high temperature alarm. his alarm would have followed the CBS high pressure alarm, which is set at 300 PSIG, to enable corrective action prior to discharge frm the relief valves. All relief valves in the CBS Systs clischarge to the RHR vault sumps, from which the fluid is pumped to the Waste Liquid Drain (WLD) Syst s for processing. %e RHR sump design includes level sensors which generate a high level alarm at the Main Control Board. IMPACT ON SYSTEM OPERATIONS: Since the additional check valves have no actuators and are in series with existing check valves with no intervening cmponents or branch connections, no operational procedures are affected by the redundant check valves. If check valve leakage were observed to occur, the same corrective actions for leakage across a single check valve would be app.vg.iate and effective for two check valves in series and is provided in existing procedural guidance. 2
RHR NPSH CONSIDERATIONS: 'Ihe addition of another check valve in the suction line fran the RWST and the containment recirculation sump to each RHR pump marginally reduces the available NPSH to the RHR pump. Applying the criteria frcm USNRC Regulatory Guide 1.1 (Net Positive Suction Head for Dnergency Core Cooling and Containment Heat RaToval Systen Pumps), the design basis case for evaluating the NPSH available for the RHR pump is during recirculation when the suction is taken from the containnunt recirculation sump. In view of the many conservative factors included in the original bases for detennining the available NPSH, we have found that even with the additional check valve, the NPSH available is consistent with the values shown in FSAR Table 6.3-1. 3
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mcs u n n pp p p i r eq o o o e o e e net e m m m t m t n y m m/ m i x r o o gr a ay a ME F 3 3 3 N 3 N i o s s s 3 l t 2 an d d S d 0 e e e e rg r 5 e ev r 0 e r 0 0 0 0 0 0 b n e ec e 8 s u 1 1 1 2 1 2 i g g g g/m g i t d 4 4 4 5 4 5 o g c s e 3 3 3 3 3 3 t n a a a r ec o t t t a e eTo V V V V V V s r s s s c x r W W W W W W no aG a n E P I I I I I I ob a e i r t S n n n e cC o o/ o f t y uR v e ms c s s s s s d d d R u en r r r r n e e - e sS mT e A A a a a a pi s s g i u / / e e e e m i i i cB n nk q N N y y y y ue c c i i ae ps r r r eC e w M er 2 2 2 2 a e a LF ge x x x r nr e e e D icgn y y) y ri l l 6 l J J J J a l l 2 l h n a aV a t e p p p p c e u u - u s r p p p p d n nS n e u A A A A ed a aB a Td A A h u m mC m e / / 0 0 0 0 t s k c N N 5 5 5 5 d d d. d ao R R R R ea n n n n e r F F F F r a a a a LP C C C C i e. 0 0 0 0 us s d d5 d 3 )4 1 1 1 1 q u n e e2 e 2 eaw t t V t 6 r co c c - c ) y0 d e eS e) f B r0 dd t p pB p8 o ( o2 l l u s) sC s1 95 g2 uuh n7 n nV 5 B B B C B C e - oo s i V i, i - 3 t V ww 5 S aW d ,S ,1 ,B t E CI nsl dB d V dC e L ) oio eC e - e e B d i h c l l S l d h A e t T bd bB b n T (S u n0 a g mn mC ma n o0 r n e a e e i i1 e e e e e e e.i s s, s2 t t 2 v v v v v v pk r s3 s9 s1 n c - i i i i i i on u aV aV aV o nV c uW _ t t t t t t ad s - s - s - c c c c c c rt i S i S i S ( FI A A A A A A e d dB dB dB we e C C C s ogs y( y( y( e pai l l l i r c l l l l go r a. a. a. p nt e i e i e ie p i s x t g t g t g s u r e r a r a r a e S l l u r at at at J i i d ee p u p u p u d a a t k o o o Va f i e F F e a o e e e u p v wr b g b g b g l y l t n n n K F T n n ags l i l i l i e o o k k vn - l l l l l l c4 S t e t e c c i l a e a e a e e C sf sf V e V e sl l h u h u h u hC / i a i a O h O h i e u sf sf sf S PS PS M C M C h uf e e e C C t f s r s r s r C e e e e e n E grb vh vh vh s e n l c l c l c L eJ s i el a a a a a a A d a 2 2 2 2 2 2 shl ve v e ve Hs m o l C i t a RD e C c h es es e s t rh s si si si s et es e s e s / y xit h a h a h a s S E wI Tb Tb Tb B C 2 3 l 2 7 8 e 3 3 l 1 1 1 1 2 3 4 v V V V V V V l D e e e e aI S S S S S S t t t t V B B B B B B o o o o C C C C C C N N N N j}}