ML20088A255
| ML20088A255 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/27/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20088A254 | List: |
| References | |
| TASK-2.B.1, TASK-TM GL-83-37, TAC-53458, TAC-53459, NUDOCS 8404110279 | |
| Download: ML20088A255 (2) | |
Text
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/psa no
'o UNITED STATES
",h NUCLEAR REGULATORY COMMISSION 3
.E WASHINGTON, D. C. 20555
- o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NOS. 69 AND 63 TO FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-60 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-282 AND 50-306 Introduction By letter dated January 13, 1984, Northern States Power Company (NSP) (the licensee) requested technical specification (TS) changes for Prairie Island Nuclear Generating Plant Unit Nos. I and 2 concerned with operability and surveillance requirement of the reactor coolant system vents.
In response to NUREG-0737 (Item II.B.1) the licensee installed reactor coolant system vents which consist of vent paths from the reactor vessel head and the pres-surizer.
The proposed TS change submitted by the licensee is in response to the NRC's request in Generic Letter 83-37.
Discussion and Evaluation By letter dated January 13, 1984, the licensee requested a TS change that is in conformance with our request in Generic L'etter 83-37 to specify the limiting conditions for operation and surveillance reouirements for the reactor coolant system vents. The licensee installed reactor coolant system vents at the Prairie Island Nuclear Generating Plant Unit Nos.1 and 2 in rt.sponse to NUREG-0737 Item II.B.1.
The vents provide a pathway to exhaust noncondensible gases from the reactor coolant system that could inhibit circulation through the reactor core.
This vent system consists of vent paths from the reactor vessel head and the pressurizer. Each path contains two independently emer-gency powered, fail safe valves in parallel which connect a common header that discharges to either the containment atmosphere or the pressurizer relief tank.
By letter dated September 19, 1983 the staff informed the licensee that, based i
on submittals dated December 3,1979, July 1,1981 and April 26, 1982, it was found that the design of the reactor coolant system vents at the Prairie Island Nuclear Generatin ments of 10 CFR 50.44(c)g Plant Unit Nos. I and 2 conforms with the require-(3)(iii), the guidelines of NUREG-0737 Item II.B.1, and NUREG-0800 Section 5.4.12 and therefore are acceptable. The licensee's January 13, 1984 submittal also provided a response to four open items in the staff's safety evaluation dated September 19, 1983.
The staff reviewed the licensee's response and concluded that the licensee adequately responded l
to our concerns and these matters are considered complete.
A post implementation review to erure compliance with 10 CFR 50.44(c)(3)(iii) was performed by Region III and the findings are reported in the I&E report l
8404110279 840327 PDR ADOCK 05000282 i
P pop
,. Nos. 50-282/8324 and 50-306/8324 covering the period from December 1,1983 to February 10, 1984.
This post-implementation review indicates that the installation of the reactor coolant system vents meets the NRC requirements.
The plant procedures are subject to an NRC audit which will be performed by the resident inspector after the procedures are in place (after April 1, 1984). The NRC audit will be completed prior to the effective date of these amendments which is after the first cold shutdown occurring after April 1, 1984 or after the next refueling outage, whichever occurs first, for each unit. Justification for this delay is to allow the licensee to block and tag the valves in the vicinity of the reactor vessel head which are inacces-sible during power operation.
The licensee used the staff's model standard technical specifications (STS) as guidance in preparing the proposed TS for the reactor coolant vent system.
The staff's review of the licensee's proposed limiting conditions for opera-tion indicates that, except for minor modifications, the proposed change meets the model STS requirements. The proposed surveillance requirements related to system flow testing at least once every five years was modified to every refueling period. These modifications to the limiting conditions for operations and the surveillance requirements were discussed with and agreed to by the licensee. On this basis, the proposed TS related to the limiting con-dition for operation and the surveillance requirements (as modified) for the reactor coolant system vents (NUREG-0737 Item II.B.1) are found acceptable.
Environmental Consideration We have determined that the amendments do not authorize a change in effluent types or total amounts nor an increase in power level and will not result i
in any significant environmental impact.
Having made this determination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 951.5(d)(4), that an environmental impact statement or negative declara-tion and environmental impact appraisal need not be prepared in connection with the issuance of the amendments.
Conclusion We have 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, and (2) such.
j activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Date:
March 27, 1984 Principal Contributor:
D. C. Dilanni