ML18094B364
| ML18094B364 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 03/20/1990 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-A-47, REF-GTECI-SY, TASK-A-47, TASK-OR GL-89-19, NLR-N90057, NUDOCS 9004090045 | |
| Download: ML18094B364 (5) | |
Text
Public Service Electric and Gas Company
... e Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038. 609-339-1200 Vice President - Nuclear Operations
- MAR 2 o 1990
. NLR-N90057 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
GENERIC-L~TTER-89=i9*~~~~~-~~
RESOLUTION OF UNRESOLVED SAFETY ISSUE A-47 SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 On September 20, 1989, the Nuclear Regulatory Commission.(NRC) issued Generic Letter 89-19, concerning overfill protection for steam generators in PWRs and reactors in BWRs.
Public Service Electric and Gas Company (PSE&G) hereby provides its response to Generic Letter 89-19 for Salem Units 1 and 2.
Salem Units 1 and 2 meet the requirements for a satisfactory steam generator overfill protection system as stated in generic letter 89-19.
The justification for PSE&G's assessment is included in Attachment 1.
Hope Creek is a member of the BWR Owners' Group (BWROG).
The BWROG has requested and received an extension to May 4, 1990.
The BWROG generic response and the Hope Creek specific response will be submitted on or before this date *.
Should you have any questions regarding this transmittal, please feel free to contact us.
Sincerely, Attachment
Document Control Desk NLR-N90057 c
Mr. J. c. Stone Licensing Project Mr. c. Y. Shiraki Licensing Project Mr. T. P. Johnson Manager Manager Senior Resident Inspector 2
,.., 2 0 1990
~i'f:i i Mr w. T. Russell, Administrator Region I
::-::-----:::----:-----=-~--=----;-. ----:.:-----------------~
Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Envirqnmental Quality Bureau of Nuclear.Engineeri11g CN 415 Trenton, NJ 08625
REF: NLR-N90057 STATE OF NEW JERSEY
)
SS.
COUNTY OF SALEM
)
S. LaBruna, being duly sworn according to law deposes and says:
I am Vice President - Nuclear Operations o~-PuoTlc SerV"ice Electric and Gas Compa~y, and as such, I find the matters set forth in OUr letter d:~ed 2 o' 199()'
f COnCerning the Salem Unit Nos. 1 and 2 and Hope Creek Generating Stations, are true to the best of my knowledge, information and belief.
Subscribed and Sworn to before me
_'}A.,d_.
/)_,
/
av day of
/~, 1990 Jersey My Commission expires on LARAINE Y. BEARD Notary Public of New Jersey My Commission Expires May 1, 1991
NLR-N90057 ATTACHMENT 1 JUSTIFICATION FOR FOR SALEM UNITS 1 AND 2 RESPONSE TO GENERIC LETTER 89-19 of Generic Letter 89-19 stated that existing designs would be acceptable if the criteria listed for the specific design are met.
Salem Units 1 and 2 are Westinghouse four loop PWR's with 2 out of 3 initiating logic for overfill protection.
The criteria and Salem's response are listed below:
Criterion
-Aut.ematie-steam-gene-.r-ato~-over-f-il-1-protection--is-pro'ilided_to ______,
mitigate main feedwater overfeed events.
The overfill protection system is sufficiently separate from the control system, such that, it is not powered from the same power source, not located in the same cabinet, and not routed so that a fire is likely to affect both systems.
Response
Steam generator overfill protection is provided by the Turbine Trip and Feedwater Isolation function of the Engineered Safety Features Actuation system, Technical Specification 3.3.2, Table 3.3-3, Functional Unit 5.
This function will isolate the main feedwater system by closing the main feedwater isolation valves, tripping the main feedwater pumps and tripping the main turbine.
The overfill protection control circuits are powered from vital buses 11c 11 and "D" and the protection circuits are powered from vital buses "A" and "B".
The overfill protection control circuits are located in cabinets R18 and R19 and the protection circuits are located in cabinets R4 and RS.
The control signal is separated from the protection signal by a Class lE isolator located in the protection cabinet.
A Fire Protection engineering review was conducted to ensure components and cabling are not routed so that a fire is likely to affect the control and protection circuits.
The review determined, either, 1) physical separation exists for both functions, 2) protection is already planned via the Fire Protection Improvement Program (wrap of penetration 1-59, 2-59), or 3) in areas where physical separation is not possible, (Upper 460V Switchgear Room, Relay Room and Control Room Complex Room), NRC approved alternate shutdown methodology which includes steam generator overfill protection will be implemented.
Criterion The plant procedures and Technical Specifications include requirements to periodically verify operability of the main
- Eeedwa-t;er-0ver-f-i-l-l--pr0test-i0n-and--ensu-!:'e-the---aut0matiG------ _____,
overfill protection is operable during reactor power operation.
Response
Technical Specification 4.3.2.1.1, Table 4.3-2, for both Salem Units 1 and 2 require periodic surveillance testing 'Of the Turbine Trip and Feedwater Isolation function to assure operability of the system.
The following Maintenance Department procedures are used to periodically verify operability of the trips:
Channel Calibration Procedures PD-2.3.033, 034, 035 PD-2.3.043, 044, 045 PD-2.3.053, 054, 055 PD-2.3.063, 064, 065 Channel Functional Procedures PD-2.6.033, 034, 035 PD-2.6.043, 044, 045 PD-2.6.053, 054, 055 PD-2.6.063, 064, 065