ML20198K093
| ML20198K093 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/15/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198K091 | List: |
| References | |
| NUDOCS 9710230055 | |
| Download: ML20198K093 (2) | |
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4 UNITED STATES g
,j NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D.C. 30666 0001 os...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 20s TO FACILITY OPERATING LICENSE NO. DPR-50 METROPOLITAN EDISON COMPANY E RSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 1 DOCKET NO. 50-289
1.0 INTRODUCTION
By letter dated July 30, 1997, and supplemented by letters dated September 19.
and September 24, 1997. GPU Nuclear, Inc requested changes to the Technical S)ecifications (Ap)endix A to Facility Operatinj License No. DPR-50) for the T1ree Mile Island luclear Station, Unit 1. (THI-1/TS) and revisions to the Three Mile Island Unit 1 Updated Final Safety Analysis Report (TMI-1/UFSAR).
The requested changes are related to (1) the maximum allowable total leakage from the accident recirculation portions of the Decay Heat Building Spray, and Makeup systems, and (2) revision of a postulated design basis loss-of-coolant accident (LOCA) analysis in the THI-1/UFSAR.
The September 19. and September 24, 1997, submittals did not affect the initial no significant hazards consideration determinat10n.
2.0 EVALUATION The requested maximum allowable total leakage limit would decrease the current leakage limit of 6.0 gallons per hour'(gph) from the Decay Heat Removal System components in the THI-1/TS Section 4.5.4 to 0.6 g)h.
The proposed change also adds a footnote to TS Section 4.5.4 that limits tie combined total leakage from the accident recirculation portions of the Decay Heat. Building Spray, and Makeup systems to 0.6 gph. This requested change of allovable total leakage to 0.6 gph would conform with that used in the current licensing basis accident analyses in the THI-1 Updated Final Safety Analysis. The accident recirculation systems would include the accident recirculaton portions of the Decay Heat. Building Spray, and Make-up systems outside of the containment.
The requested change is a more restrictive limitation for leakage from systems recirculating contaminated fluids outside of containment during a LOCA than the current TS. Also, the requested change makes the TS consistent with the design basis analyses in UFSAR Section 14.2.2.5.
The change will provide 971023o055 971015 l
PDR ADOCK 05000289 P
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assurance that the dose reference values given in 10 CFR 100 of 300 rem to the thyroid and 25 rea to the whole body are met.
Therefore the proposed change-in the TS is acceptable.-
The review of the requested revision of a postulated design basis LOCA analysis in the THI-1/UFSAR is deferred until the licensee provides a complete evaluation of THI-1 control room habitability for the staff's review.
In an NRC letter to the licensee dated September 24, 1997, the staff requested that' the licensee provide an analysis of the-control room operator thyroid dose that addresses the full spectrum of design basis accidents, including the.
large break LOCA and main steam line break: accident within 6 months from the date of the letter.
3.0-
SUMMARY
CONCLUSION Based on our review, the staff finds that the licensee's proposal to reduce
- the maximum allowable total leakage from the Decay Heat Removal System to
- 0.6 gph is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
This amendment 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 1
significant increase in the i. mounts, 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 occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (62 FR 45458). Accordingly, this amendment
- meets the eligibility-criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or i
- environmerital assessment need be prepared in connection with the issuance of the amendment.
1 6.0 -CONCLUSION The Commission has concluded, based on the considerations discussed above.
- that:
(1) there is reasonable assurance that the health and safety of-the s
. public will not be endangered by operation in the proposed manner (2) such activitiee will be conducted in compliance with the Commission's regulations.
= and (3) 1he issuance of the amendment will not be inimical to the common-defense and security or to the health and safety of the public.
Principal Contributors: - Jay Lee-Bart Buckley Date: October 15, 1997
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