ML20072P849
| ML20072P849 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 11/21/1990 |
| From: | Drawbridge B PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-90202, NUDOCS 9011280187 | |
| Download: ML20072P849 (8) | |
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New Hampshire Yankee NYN 90202 November 21, 1990 United States Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Document Control Desk I
)
References:
(a)
Facility Operating License No. NPF 86, Docket No. 50 443 (b)
Telephone Conversation on November 21, 1990 from T. L. liarpster (NiiY) to E. Leeds (NRC)
Subject:
Justification for Continued Operation of Scabrook Station in MODE 3 Gentleman:
)
Enclosed please find a Justification for Continued Operation (JCO) of Scabrook j
Station in MODE 3, llot Standby, while repairs are made to Valve MS V 127.
This justification documents a telephone conversation between T. L. liarpster of New Hampshire Yankee, N. Dudley, NRC Senior Resident inspector, and E. Leeds of the NRC on November 21,1990 at 3:15 pm from the Senior Resident inspector's office (Reference b).
Should you have any questions regarding this matter please contact Mr. Terry L.
llarpster, INrector of Licensing Services, at (603) 474 9521, extension 2765.
j i
l Very t ly,,'yours, l
Yg&
L Ilruce
. Drawbridge i
Executive Director -
l Nuclear Production Enclosures 1
DLD:JMP/ tad l
t ec:
Mr. Thomas T. Martin 1
b Regional Administrator
)
'd United States Nuclear Regulatory Commission
-h Region 1 85 475 Allendale Road "O
King of Prussia, PA 19406
' tw ON' Mr. Noel Dudley
!.Oh NRC Senior Resident inspector 3
P.O. Box 1149 g
f L -g[j Seabrook, Nil 03874 l
M o.
New Hampshire Yonkee Division of Public Service Company of New Hampshire t
P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474 9521 1
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New Hampshi'e Yankee November 21, 1990 j
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ENCL,OSURE 1 TO NYN.90202 i
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e New Hampshire Yankee November 21, 1990 ENCLOSURE 1 TO NYN 90202 Valve MS.V 127 is a dual function valve which provides the steam supply to the steam turbine driven emergency feedwater pump and functions as a containment isolation valve.
This valve is in the main steam system, which is a closed system inside the containment and therefore requires only a single isolation valve pursuant to 10 CFR 50, Appendix A, Criterion j
- 57. This valve is currently inoperable in the open position. Seabrook Station Technical Specification 3.6.3, ' Containment Isolation Valves', states:
'With one or more of the Isolation valve (s) Inoperable, maintain at least one 1
(solation valve OPERABLE in each affected penetration that is open and:
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a.
Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or Isolate each affec'ted penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least c.
one closed manual valve or blind flange; or d.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the.following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />."
The Seabrook Station Final Safety Analysis Report, Seption 6.2.4.2, states that the piping and l
valves of the containment isolation system conform to the ASME Bollet and Pressure Vessel Code, Section 111, Code Class NC (le Safety Class 2). Valve MS.V 127 erves as the class boundary in this system; the piping downstream of this valve is designated as Safety Class
- 3. -Therefore, no Class 2 valve exists to provide the isolation function as required by this
. Technical Specification until MS.V 127 is repaired.
l To provide the containment isolation function, valves MS.V 393, MS.V.396, MS.V.397, and MS.V.398 will be closed during the period that MS.V.127 is being repaired. Valve MS.V.
393 is located approximately 25 feet downstream of MS.V.127, MS V.396 is a bypass valve around MS.V.393, and MS.V.397 and MS.V.398 are drain valves located between MS.V-127 and MS.V 393. These valves are shown in Enclosure 2.
All of the intermediate piping and the valves are designated as Safety Class 3.
The Class 3 piping downstream of MS.
V.127 has the same design pressure and temperature limits as the Class 2, upstream piping and was hydrostatically tested to the same requirements.
The closure of MS.V.393 will render one train of the auxillary feedwater system inoperable.
Therefore, closure of this valve will place the unit in Action 'a.' of Technical Specification l
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l New llampshire Yankee November 21, 1990 3.7.1.2, ' Auxiliary Feedwater System *, which states:
'a. With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least IIOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in llOT SIIUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.'
As stated above, the containment isolation provision for the main steam system is designed to the requirements of General Design Criterion (ODC) 57. Valve MS V 127 functions as one of the two required barriers to fission product release.
The second barrier is the closed system inside the containment, speelfically the steam generator and main steam piping.
The required second barrier is fully functional.
Operation in Mode 3 in this configuration is functionally equivalent to the remedial actions specified in Technical Specification 3.6.3 for an inoperable containment isolation velve. Therefore, operation in Mode 3 for the maximum period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> will not represent any undue risk to the health and safety of the public nor will it provide a pathway for release of radioactive material to the environs.
Valve MS V 127 is a normally open, fall open air operated valve.
Safety related air accumulators are provided to effect valve closure. By securing the downstream valves in the closed position, assurance of the containment isolation function is provided even though the piping and valves are not designed as Safety C%ss 2. Therefore, the safety related function of the containment isolation system will continue to be fulfilled. Ensuring the containment isolation function will ensure that any offslte releases, however unlikely, remain within the guidelines of 10 CFR 100. As stated previously, this configuration will be limited by the action requirements of Technical Specification 3.7.1.2, which allow the steam turbine driven auxillery feedwater pump to be inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Although this pump will be inoperable during this period, an additional steam supply to the turbine exists through valves MS V 128 and MS V 394. Therefore, all applicable regulatory criteria will continue to be
- met, At this time, the only available alternative action would be to place the unit in Mode 5.
Because the containment isolation function is fulfilled by placing the unit in the above stated configuration, this would result in an additional heatup/cooldown cycle for the unit without yleiding any additional safety benefit.
The corrective action for this condition will be completed by repairing Valve M'hV 127.
The valve actuator piston is flawed and will be replaced. It is estimated that this repair will be completed by November 23, 1990.
Additional corrective action will be pursued with the NRC Staff to resolve the discrepancy between the plant design basis as documented in the FSAR and the Technical Specifications.
Technical Specification 3.6.3 la based upon the Westinghouse Standard Technical Specifications and provides appropriate remedial actions for systems utilizing two containment isolation valves. These action requirements are not appropriate for systems designed to GDC 57 which have only one isolation valve and which utilize the closed system inside containment as one of the two required fission product barriers. This action will be 2
New llampshire Yankee November 21, 1990 pursued expediently. Based upon the above New 1-lampshire Yankee has determined that these actions meet the original design criteria and will not jeopardize the health and safety of the public. New llampshire Yankee will operate Seabrook Station in MODE 3 in this configuration for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> as described in Technical Specification 3.7.1.2.a.
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New llampshire Yankee November 21, 1990 ENCLOSURE 2 TO NYN 90202 M AIN STEAM SYSTEM EMERGENCY FEEDWATER PUMP SUPPL,Y DETAIL i
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