ML18009A540
| ML18009A540 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/09/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18009A539 | List: |
| References | |
| NUDOCS 9005170074 | |
| Download: ML18009A540 (3) | |
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+)i*<<qs UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIOH SUPPORTING AMENDMENT NO.
>7 TO FACILITY OPERATING LICENSE NO. NPF-63 CAROLINA POWER 5 LIGHT COMPANY et al.
SHEARON HARRIS NUCLEAR POWER PI.ANT UH!T I DOCKET NO. 50-400
1.0 INTRODUCTION
By letter dated May 5, 1989, as supplemented May 25, 1989, Carolina Power 5 Light Company submitted a request for changes to the Shearon Harris Nuclear Power Plant, Unit 1, Technical Specification (TS) Table 4.4-4 related to gross radioactivity analyses of reactor coolant samples.
The May 25, 1989, letter provided clarifying information that did not change the initial determination of no significant hazards consideration as published in the Federal Re ister -(54'FR 29400) dated July 12, 1989.
The amendment request~a ates t e ootnote in Table 4.4-4 related to the gross radioactivity determination.
The footnote stipulates that the determination of radioactivity should consist of quantitative measurements of both gaseous and degassed activities excluding specific activities with half-lives less than 15 minutes and all radioiodines.
The amendment request would replace the deleted footnote method with the gross count method described in the Bases for TS 3/4.4.8.
The gross count method of TS 3/4.4.8 is a gross beta/gamma proportional counter measurement of an evaporated reactor coolant sample.
2.0 EVALUATION Performing the radioactivity determination described in, the footnote to TS Table 4.4-4, Gross Radioactivity Determinations, requires collecting a
pressurized.reactor coolant sample; degassing and collecting the gaseous portion of the sample; performing separate isotopic measurements of the degassed liquid and stripped gaseous samples; and then summing these activities including the activities of pure beta emitters such as tritium, Fe-55, Sr-89 and Sr-90.
The intent of the gross radioactivity determina-tion required by TS Table 4.4-4, Item I is to verify that Reactor Coolant System (RCS) liquid specific activity is ma]ntained within the specific activity limits of TS 3.4.8.b.
The specific activity limits of TS 3.4.8.b ensure that the resulting doses at the site boundary will not exceed an appropr iately small fraction of 10 CFR Part 100 dose guideline values following a steam generator tube rupture.
The conditions imposed by note I of Table 4.4-4 are too restrictive since the gaseous activity does not 005f7007 Qg000400 900509 pDR
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contribute significantly to the doses at the site boundary for the steam generator tube rupture event.
In addition, degradation of fuel performance would be readily detectable by an increase in the sample's non"gaseous fission products.
- Further, the staff concludes that these changes are consistent with the Standard Technical Specifications (STS) for Westinghouse's Pressurized Mater Reactors, NUREG-0452, Rev.
4, 1981, Table 4.4-4, "Primary Coolant Specific Activity Sample and Analysis Program,"
and are, therefore, acceptable.
- 3. 0 ENVIRONMENTAL CONSIDERATION This amendment changes a surveillance requir ement of a facility component located within the restr icted area as defined in 10, CFR Part 20.
The 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 th'at there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration, and there has been no public comment on such finding.
Accordingly, this amendment'eets 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 environ-mental assessment need be prepared in connection with the issuance of this amendment.
- 4. 0 CONCLUSION The Commission made a proposed determination that this amendment involves no significant hazards consideration which was published in the Federal Receister (54 FR 29400) on July 12, 1989, and consulted with the State of North Carolina.
No public comments or requests for hearing were
- received, and the State of North Carolina did not have any comments, The staff has concluded, based on the considerations'iscussed
- 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 activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
J.
Minns R. Becker Oated:
May 9, 1990