ML20033C630
| ML20033C630 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/13/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033C629 | List: |
| References | |
| NUDOCS 8112030519 | |
| Download: ML20033C630 (3) | |
Text
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a wAsmuoTow, p. c.2oses SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 51 TO FACILITY OPERATING LICENSE NO. DPR-42 AND AMEN 0 MENT NO. 45 T0' FACILITY OPERATING LICENSE'NO. DPR '
00RTHERA. STATES POWER COMPANY
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NOS.1 AND 2
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. DOCKET'N S.'50-282 AND 50-306
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~By' letter dated November 22, 1978 Northern States Power Company (NSP)
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requested amendments to Facility Operating Licenses No. DPR-42 and DPR-60 for Prairie Island Nuclear Generating Plant, Unit Nos. 1 and 2.
The proposed amendments would incorporate the monitoring program for -..
Secondary Water Chemistry in the Appendix A Technical Specifications (TS).
Discussion and Evaluation:
In August 1976, we sent letters to the majority of licensees who operate Pressurized Water Reactors (PWRs) regarding the control of.st.condary water chemistry to inhibit corrosion of steam generator tubes. The letters reque,sted the licensees to propose Technical Specification changes to incorporate limiting conditions for operation and surveillance require-aents f.or secondary water chemistry parameters. Since the Prairie Island operating lie.ense hearing was being held open during this period (August 1976) to consider the steam generator tube irservice inspection requirements which could have an impact on the secondary water chemistry Technical
, Specifications, the letter was not sent to NSP.
Many licer. sees objected to the Model Technical Specifications principally
'on the basis that they could unnecessarily restrict plant operation. The majority of these licensees submitted alternative approaches that were directed more toward monitoring and record keeping rather than specific limits on chemistry parameters. At the time of our request, we recognized
'that a major disadvantage of the Technical Specifications was a potential decrease in operational flexibility, but our request was motivated.by an overriding concern for steam generator tube integrity.- Our:cbjective was to provide added assurance that licensees would properly monitor and control secondary water chemistry to limit corrosion of steam generator tubes.
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2-However, based on the exper..1ce and knowledge gained since 1976, we I
4 concluded in mid-1978'that Technical ~ Specification limits would not be-the most effective way of~ accomplishing this obje:tive. Due to the I
complexity of the corrosion phenomena involved, and the state-of-the-art as it exists today,.we believe that a more effective approach woulf be to L
institute a licensing i:hn'dition thaUequires the implementation oCa
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seconildy waterihimistry monitoring and a control program. The required
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procedures for the program would be developed by the licensees, With any needed input from their' reactor vendors or other consultants, and thus could l
- r. ore readily account for site and plant specific factors that affect t
. chemistry conditions in the steam generators.
In our view, plant operation following_such procedures would provide assurance that licensees would
- devote proper attention to' controlling secondary water chemistry while also providing the needed flexibility to allow them to more effectively
' deal with any off-normal conditions that-might arise.
Conseque'ntly, by letter dated September 7,1978, we requested the licensee to propose a license amendment incorporating an interim secondary water chemistry monitoring program Technical Specification appropriate.for the Prairie Island Generating Plants. The licensee responded to our request by letter dated November 22, 1978 by proposing to incorporate seconda~y water r
chemistry monitoring rcmairements appropriate for the Prairie Island Generating Plant Units 1.and 2.
The proposed amendments comply.with the-guidance,we provided to the licensee in our September 7, 1978 request.
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Additional assurance that steam generator tube integrity-is not reduced below an acceptable margin of safety is provided by the requirements in the plant Technical Specifications for (a) limits in the primary to secondary leakage rates, (b) steam generator tube surveillance and (c) plugging criteria for-degradation.
Based on our review, we have' concluded that the proposed sampling program in the proposed amendments are acceptable.
Environmental Consideration We have deterndned that the amendments do not' authorize a change.in effluent types or total amounts nor an increase in power level and Will not result in any signif~icant environmental impact. Having made-4 i.
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 551.5(d)(4), that an environmental impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of these amendments.
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3-Conclusion
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We have concluded, based on the considerations discussed above, that.
(1) because the ' amendments do not involve a significant increase.
in the probability or consequenccs of accidents creviously considered and do not involve a significant decrease in a safety margin, the amendments do not involve a significant. hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance, of these amendments will not be inimical j
to the common defense and security or to the health and safety of the public.
I Date: November 13, 1981 I
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