ML20149K792
| ML20149K792 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 02/14/1996 |
| From: | Storz L Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LCR-H96-03, LCR-H96-3, LR-N96043, NUDOCS 9602220176 | |
| Download: ML20149K792 (4) | |
Text
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s Pubhc Serwce Electric and Gas Cornpany Louis F. Storz Pubhc Service Electnc and Gas Cornpany P.O. Box 236, Hancocks Bndge, NJ 08038 609-339-5700 s-u. er
.. ne.a operai on.
FEB 141996 LR-N96043 LCR H96-03 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
SUPPLEMENT TO EXIGENT LICENSE AMENDMENT APPLICATION SUPPRESSION POOL COOLING E SPRAY SURVEILLANCES HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 Public Service Electric and Gas Company (PSE&G) submits the following supplemental information to the license amendment 4
request transmitted to the NRC via letter LR-N96009, dated
]
February 5, 1996.
The amendment request involved revising J
Surveillance Requirements 4.6.2.2.b and 4.6.2.3.b of the Hope Creek Technical Specifications, to include flow through the Residual Heat Removal (RHR) heat exchanger bypass line (in addition to the RHR heat exchanger) in the Suppression Pool Cooling and Suppression Pool Spray flow path used during RHR pump testing.
The subject amendment stated that periodic testing would be conducted to ensure that a flow rate of at least 8985 gpm through the RHR heat exchanger can be achieved during the Suppression Pool Cooling mode of operation with the bypass valve closed.
Results of the initial test, description of the testing, and testing periodicity were requested by the NRC staff on February 9, 1996.
The following provides the requested information.
A)
Results of Initial Test The initial tests have been conducted on the A and RHR heat exchangers.
The test results indicate that 9,968 gpm is passing through the A RHR heat exchanger and 9,648 gpm is passing through the B RHR heat exchanger.
Each of these flow rates exceed the required minimum flow rate through the heat exchanger for the Suppression Pool Cooling mode of operation.
9602220176 960214 DR ADOCK 05000354 PDR wwv.
(3) Pnntedon l
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o FEB 141996 Document Control Desk LR-N96043 B)
Testing Description and Periodicity Testing to verify adequate flow through the RHR heat exchanger, with the bypass valve closed, during the Suppression Pool Cooling mode of operation will be performed using ultrasonic measurement equipment.
The testing will be conducted once per operating cycle, either during operation or refueling, on a frequency not to exceed 24 months.
The RHR heat exchanger bypass valve will be stroke tested on a quarterly basis as part of the Inservice Testing Program.
The acceptance criteria for this test requires meeting a prescribed stroke time for valve opening and closing.
The bypass valve can exceed its design leakage rate and still not deprive the heat exchanger of its required flow rate or its heat transfer capability.
Actual determination of leakage through the bypass valve is not necessary provided that the flow rate through the heat exchanger and the total flow rate are known for the Suppression Pool Cooling mode of operation.
Therefore, it is not necessary to impose a leakage acceptance criteria on the bypass valve as part of the Inservice Testing Program.
This supplement to the amendment request formally documents and commits that the RHR heat exchanger and bypass valve testing described above for the Suppression Pool Cooling mode of operation, will be conducted at the test frequencies stated.
Should there be any questions with regard to this submittal, please do not hesitate to contact us.
Sincerely,
,f.
r' c0 L.
F.
Storz Sr. Vice President -
Nuclear Operations i
FEB 141996 Document Control Desk LR-N96043 C
Mr. T. T. Martin, Administrator - Region I U.
S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr.
D. Jaffe, Licensing Project Manager - Hope Creek U.
S.
Nuclear Regulatory Commission One White Flint North j
11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. R. Summers (X24)
USNRC Senior Resident Inspector Mr.
K. Tosch, Manager, IV Bureau of Nuclear Engineering 33 Arctic Parkway 4
CN 415 Trenton, NJ 08625 l
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Ref:
LR-N96043 STATE OF NEW JERSEY )) ss COUNTY OF SALEM
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F. Storz, being duly sworn according to law, deposes and says:
I am Senior Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Hope Creek Generating Station, are true to the best of my knowledge, information and belief.
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Subscribed and Sworn before me this /k day ofd 6bMM dLLA,1996.
IA m l0JL MM e
Ncy ary Public' of gew 'JWsey t
KlMBERlY JO BROWN My Commission expires on vem,i,7,br'.[7,Ef.f.fRpEJ
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