ML18102A470
| ML18102A470 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/17/1996 |
| From: | Storz L Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18102A471 | List: |
| References | |
| LR-N96318, NUDOCS 9610250074 | |
| Download: ML18102A470 (4) | |
Text
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Public Service Electric and Gas Company Louis F. Storz Public SeNice Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 Senior Vice President - Nuclear Operations OCT 1 7 1996 LR-N96318 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUPPLEMENTAL INFORMATION RADIOLOGICAL DOSE ASSESSMENT METHODOLOGY SALEM GENERATING STATION NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Gentlemen:
This letter is being sent to provide updated information to the Staff pertaining to the radiological dose assessment that was performed in support of a requested change to the Technical Specifications on Control Room Emergency Air Conditioning System, (ref. LR-N96154, dated June 10, 1996).
The attached information revises previously supplied information of June 24, 1996, (ref.
LR-N96178), and July 1, 1996, (ref. LR-N96191) to reflect changed input assumptions and the resulting Control Room calculated doses.
The enclosed pages provide revised input assumptions, data and results pertaining to a postulated LOCA, fuel handling accident inside the Fuel Handling Building and Reactor Coolant Pump locked rotor accidents.
The revised LOCA calculations include changes to the specified Control Room makeup flow from 2500 cfm to 2200 cfm as a result of including 10% margin and to the alignment time of the Auxiliary Building Ventilation System from thirty minutes to two hours.
These were discussed in Public Service Electric & Gas Company's September 20, 1996 letter, (ref. LR-N96284).
The revised calculations for fuel handling and locked rotor include these changes as well as Salem specific intake radiation monitor response data and a three second monitor response delay time due to the noise reject algorithm inherent to the monitor design.
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The attached includes information pertaining to the calculation of Exclusion Area Boundary and Low Population Zone doses.
This
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Document Control Desk LR-N96318 2
information, however, is not relevant to the Control Room dose analyses and should be disregarded.
PSE&G is not requesting approval of the revised offsite doses since it does not include the application of the ARCON95 methodology for determining dispersion factors.
Please note that the attached 29 pages are not sequentially numbered and represent complete updates of Table 5 attached to LR-N96178 and all attachments to LR-N96191.
References listed on the included pages are to the internal documents from which the calculational information was obtained.
If any further information pertaining to this supplement is needed, please call.
Sincerely, Attachments (2)
C Mr. H. J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. Olshan, Licensing Project Manager -
Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C. Marschall (X24)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 95-4933
REF: LR-N96318 STATE OF NEW JERSEY SS.
COUNTY OF SALEM L.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 Salem Generating Station, Unit 1 and Unit 2, is true to the best of my knowledge, information and belief.
L.F. Storz, nio V ce President Nuclear Operations Subscribed and Sworl}ito before me this /?fh day of (1!_(!_,i-obUL 1996
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illA~tMnU/10 NQ:ari Public NewJersey My Commission expires on KIMaEnLV JO SROWN NOTARY PUBLIC OF NEW JERSEY My Commission Expires April 21, 1998
Document Control D.k Atta,chment to LR-N96321 SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 SUPPLEMENTAL INFORMATION RADIOLOGICAL DOSE ASSESSMENT METHODOLOGY ATTACHED ERRATA PAGES The following calculation pages are enclosed:
Loss of Coolant Accident (Replaces Table 5 of LR-N96178)
Objective Page 6 of 53 Assumptions Page 15 of 53 Data Pages 16 - 21 of 53 Results and Conclusions Pages 52 & 53 of 53 Fuel Handling Accident in the Fuel Handling Building (Replaces all previously submitted pages attached to LR-N96191)
Objective Page 5
Assumptions Page 8
Data Pages 9 - 11 Results/Conclusions Page 21 Appendix A Pages App-A(l & 2 of 2)
Reactor Coolant Pump Locked Rotor Accident (Replaces all previously submitted pages attached to LR-N96191)
Objective Page 5
Assumptions Page 9
Data Pages 10 - 14 Control Room Intake Monitor Pages 19 & 20 Response Time Results and Conclusions Pages 40 & 41