ML17278A259
| ML17278A259 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/25/1985 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17278A257 | List: |
| References | |
| TAC-57260, NUDOCS 8507030048 | |
| Download: ML17278A259 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION AMENDMENT NO. 12 TO NPF-21 WPPSS NUCLEAR PROJECT NO.
2 DOCKET NO. 50-397 INTRODUCTION By letter dated March 13, 1985, the licensee requested an amendment to the Technical Specifications, Isolation Actuation Instrumentation, Section 3/4 3.2 of the WNP-2 license NPF-21.
EVALUATION Prior to full power operation, analyses were performed by the Supply System to determine a best estimate for the trip setpoint values for-isolation actuation of several systems in both the primary and secondary containments.
Similarly best estimates for allowable values of these parameters were also obtained.
Specifically these systems are:
the main steam line tunnel in the primary containment the exhaust plenum of the reactor building vent the reactor water coolant system the reactor core isolation cooling (RCIC) system the residual heat removal (RHR) system When the Technical Specifications were written it was recognized by the staff that these values were preliminary arid that they should be changed to reflect actual plant operating conditions.
These measurements o
these parameters are used primarily to detect leaks and line breaks in various rooms and areas of the containments.
An increase in air temperature is signaled in the control room and used as an initial indication that a high energy line leak has occurred.
If this initial indication is not severe it is used as a basis for an inspection, evaluation and manual intervention as appropriate.
If the measured signal exceeds the trip setpoint value, the signal automatically causes an isolation of the systems associated with the local area or room.
Initially, conservative values of the leak detection setpoints were deliberately chosen to permit early warning and isolation for local leaks and pipe breaks.
When the Operating License was issued, the Technical Specifications included trip setpoints and allowable values that were based on these conservative engineering estimates with the expectation that these values would be adjusted following plant startup tests when actual ambient conditions >>ere established.
These values were so noted in the Technical Specifications themselves and more appropriate values were to be determined and submitted to the Comission.
(See "TABLE NOTATIONS," page 3/4 3-18 of the Technical 6070~
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Specifications).
The Supply System has completed the necessary
- testing, measurements and analyses and has submitted the required values as a request for amendment to the Technical Specifications.
In addition, the amendment will change the delta temperature
- high signal to a temperature
- high signal for isolation actuation from the RHR Heat Exchanger Area and correct an inconsistency in the quality assurance record retention requirements.."
The substitution of a temperature measurement for a temperature difference measurement reflects aii operational preference and is equally valid as an indication of a significant leak.
The quality assurance record retention change is purely administrative and without safety implications.
The licensee has determined that no unresolved safety questions will result from these changes.
The staff has reviewed this determination and the proposed changes to the Technical Specifications and conclude that they are acceptable.
FINAL NO SIGNIFICANT HAZARDS CONSIDERATION DETERt~iINATION A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an acc'ident previously evaluated; (2) create the possibility of a new or different kind of accident from an accident previously evaluated; or (3) irvolve a significant reduction ir a margin of safety.
The licensee has determined and the NRC staff agrees that the requested amendment per 10 CFR 50.92 aoes not:
1) involve a significant increase in the probability or consequences of an accident previously evaluated because the updated temperature setpoints use the same leakage criteria as previously arid du riot alter the valve closure times, so accident 'probabilities and consequences are not affected;,or 2) create the possibility of a new or di'fferent kind of accident than previously evaluated because this change introduces no new accident types nor changes any criteria; or 3) involve a significant reduction it> a margin of safety because the same criteria for allowable leakage prior to high temperature trip have been
- used, so the miargin of safety has been maintained.
Accordingly, the Commission has determined that this amendment involves no significant hazards consideration.
On June 18, 1985 the Commission published in local newspapers notice of its proposal to amend the Supply System's license.
No public comment was received relative to this amendment.
In addition, the State of Washington has been notified of the request for amendment by the Supply System and they indicated their concurrence by telephone on June 17, 1985.
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-3 ENV1Roia>Er,TAL C0NS1OERAT10N This amendment involves a change to the requirement with respect xo installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant chanoe in the types or significant increase in the amounts of any effluents that may be released offsite, and that there is no signific'ant increase in individual or cumulative occupational radiation exposures.
The Commission has determined that this amendment involves no significant hazards consideration.
.Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section 51.22(c)(9).
Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessmenx need be prepared in connection with the issuance of this amendment.
COllCLUS10N He 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 activi-ties 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.
Dated Principal Contributor:
J. Bradfute
3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY GOMMISSION WM~signed bye Walter R. Butler, Chief Licensing Branch No.
2 Division of Licensing
Enclosure:
Changes to Technical Specifications Date of Issuance:
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