ML20203B523
| ML20203B523 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/29/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20203B516 | List: |
| References | |
| NUDOCS 9802240311 | |
| Download: ML20203B523 (3) | |
Text
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UNITED STATES g
,j NUCLEAR REGULATORY COMMISSION s
WASHINGTON, D.c. 30666 4 001 V...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 206 TO FACILITY OPERATING LICENSE NO. DPR-70 PUBLIC SERVICE ELECTRIC & GAS COMPANY E. IILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY SALEM NUCLEAR GENERATING STATION. UNIT NO.1 DOCKET NO. 50-272
1.0 INTRODUCTION
l By letter dated December 11,1997, the Public Service Electric & Gas Company (the licensee) submitted a request for changes to the Salem Nuclear Generating Station, Unit No.1, Technical Specifications (TSs). The requested changes would provide a one-time change to the TSs to allow purging of the containment during Modes 3 (Hot Standy) and 4 (Hot Shu'.dowr) upon the retum to power from the current refuehng outage (1R13). The one-time amendment expires with initial entry into Mode 2 following outage 1R13. The purpose of the request is to provide for the safety of the workers that require access to the containment following start up with the new steam generators. Hazardous gasses are likely to be produced during heat-up of the newly installed steam generators. Purging of the containment is planned to reduce the concentration of these gasses.
2.0 EVALUATION The licensee provided calculations of the expected radiation doses that would be received by individuals off-site and in the control room if a loss of coolant accident (LOCA) were to occur with the purge valves open. The results of these calculations indicate the requirements of Part 100 of Title 10 of the Code of Federal Reaulations (10 CFR Part 100) and General Design Criterion (GDC) 19 in Appendix A to 10 CFR Part 50 would be met during this postulated accident. For these calculations, it was assumed that two thirds of the reactor core had been operated at power then decayed for a minimum of 2.5 years (912 days) due to the extended shutdown. The other one third would be new un-irradiated fuel, contributing no fission products to the source term. Due to the uncertainty of how well the purge isolation valves would seal against the containment pressure expected during a LOCA, no credit was taken for containment isolation.
Therefore, the release was modeled as a puff release from an open containment. No credit was taken in the analysis for fission product removal by the containment spray system. However, credit was taken for plate-out of 50% of the lodines released into containment, consistent with the guidance in Regulatory Guide 1.4," Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors,"
dated June 1974.
9902240311 980129 PDR ADOCK 05000272 i
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2 The NRC staff review ed the licensee's models and assumptions and performed an independent analysis of the expect 3d off-site and control room doses resulting from the postulated LOCA.
Using the assumptions stated above and input parameters taken from the current licensing basis, whole body and thyroid doses for the maximum exposed individuals at the Exclusion Area Boundary (EAB) and the Low Population Zone (LPZ) wori calculated using the HABIT computer code. The whole body, thyroid and skin doses for operators in the control room were also calculated using the HABIT code. Current design basis parameters used in the stars analysis were taken from Table 1 of the stafs Safety Evaluation supporting the February 6, igg 7, amendment to the Salem Control Room Ventilation Specifications. No credit was assumed for the operation of any of the control room habitability systems.
f Table 1 lists the results of the stars analysis of the off site and control room doses resulting from the postulated LOCA along with the applicable acceptance r.iteria from NUREG 0800;
" Standard Review Plan"(SRP).
Table 1 i
Radiological Consequences of LOCA While Purging Following a Steam Generator Replacement Outage For Salem Unit 1 Dose (Rem)
Acceptance Criteria Exclusion Area Boundarv(2 Hourk Whole Body
.088 25 Thyroid
.006 300 t
Low Population Zone (30 Davn);
Whole Body
.008 25 Thyroid
.005 300 Control Room (30 Dtyst Whole Body
.63 5
Thyroid
<.001 30 Skin 70 30(75*)
- 75 rem applicable with eye protection provided.
The licensee has committed to provide glasses to the control room operators to shield their eyes from beta radiation in the unlikely event of a LOCA occurring with the purge valves open. The staff concludes that the licensee has demonstrated that the design, as modified, meets the SRP acceptance criteria for the maximum radiation dose to control room operator and members of the public during a LOCA. Therefore, the Technical Specification relaxation as proposed is acceptable.
i
s.
3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the New Jersey 8 tate official was notified of the proposed lasuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The omsodment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupationw radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards maideration, and there has been no public comment we such finding (62 FR 663g7) Accordingly, the amendment meets t
l the eligibility critetta for categorical exclusion set forth in 10 CFR 51.22(c)(g). Pursuant to 10 i
CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in conr.ection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Roger L Pederson Date: January 29, 1998
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