ML20135C559
| ML20135C559 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 02/28/1997 |
| From: | Dawn Powell Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18102A887 | List: |
| References | |
| LR-N97105, NUDOCS 9703040123 | |
| Download: ML20135C559 (3) | |
Text
O PSEG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit EEB 2 81997 LR-N97105 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 TECHNICAL SPECIFICATION 6.9.1.5 ANNUAL REPORTS SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 Gentlemen:
Public Service Electric and Gas Company (PSE&G) hereby submits the enclosed Annual Reports for the Salem and Hope Creek Generating Stations, in accordance with Technical Specifications 6.9.1.5.a and 6.9.1.5.b of Appendix A to Facility Operating License Nos. DPR-70, DPR-75 and NPF-57.
Pursuant to Technical Specification 6.9.1.5.a, Enclosures 1, 2
and 3 are submitted for Salem Unit 1, Salem Unit 2 and Hope Creek, respectively.
These enclosures contain estimations on an annual basis of the number of station, utility and other personnel receiving exposures greater than 100 mrem / year and the collective exposures according to work and job function for each unit. provides information pu::suant to the requirements of Technical Specification 6.9.1.5.b of Appendix A to Facility Operating Licenses DPR-70 and DPR-75.
This information pertains to the Salem Unit 1 and Unit 2 steam generator tube inspections completed in 1996.
Pursuant to the requirements of Technical Specification 6.9.1.5.b of Appendix A to Facility Operating License No. NPF-57, the following information is being provided concerning the Hope Creek Safety / Relief Valves (SRVs).
During 1996, the SRVs were not challenged by any overpressurization events or transients that would have required the valves to respond.
No SRV testing was
]
performed on installed SRVs during 1996 and no SRV setpoint drift concerns were identified.
hI 9703040123 970228 PDR ADOCK 05000272 R
PDR l
The pwverisin Suurhands.
Nw Document Control Desk LR-N97105 Should you have any questions or comments regarding this submittal, please contact us.
Sincerely, 42A. --!
D.
R. Powell Manager -
)
Licensing and Regulation Enclosures (4)
C Mr. T. T. Martin, Administrator - Region I U.
S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager - Salem U.
S. Nuclear Regulatory Commission One White Flint North i
11555 Rockville Pike i
Rockville, MD 20852 Mr.
D.
Jaffe (WITHOUT ENCLO9URE 4)
Licensing Project Manager - Hope Creek U.
S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. R.
Summers (X24) (WITHOUT ENCLOSURE 4)
USNRC Senior Resident Inspector - Hope Creek Mr. C.
S. Marschall (X24)
USNRC Senior Resident Inspector - Salem Mr. K.
Tosch, Manager, IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625
l' Document Control Desk LR-N97105 I
JPP BC Sr Vice President - Nuclear Engineering (N19) (W/O ENCL. 4)
General Manager - Salem Operations (SOS) (W/O ENCL. 4)
)
General Manager - Hope Creek Operations (H07) (W/O ENCL. 4) i Director - QA/NSR' (X01) (W/O ENCL. 4)
Manager - Technical Services Manager (N17) (W/O ENCL. 4)
Manager - Specialty Engineering (XO7) (W/O ENCL. 4)
Manager - Project Manager - Steam Generators (N16) i Manager - Nuclear Safety Review (N38) (W/O ENCL. 4) l Manager - Joint Cwners/ External Affairs (N28) (W/O ENCL. 4)
{
Onsite Safety Review Engineer - HC (H11) (W/O ENCL. 4)
Onsite Safety Review Engineer - Salem (X01) (W/O ENCL. 4)
Supervisor - HC Licensing (XO9) (cover letter only)
Supervisor - Salem Licensing (XO9) (cover letter only)
Station Licensing Engineer - Salem (XO9) (cover letter only)
Station Licensing Engineer - HC (X09) (cover letter only)
General Solicitor, R. Selover (Newark, SG)
Perry Robinson, Esq.
Microfilm Copy File 1.2.1 and 3.9.2 l
l 4
l