ML20059G241
| ML20059G241 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/06/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059G227 | List: |
| References | |
| NUDOCS 9009120208 | |
| Download: ML20059G241 (3) | |
Text
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UNITED STATES p,
NUCLEAR REGULATORY COMMISSION 7,
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j k......o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO 135 TO FACILITY OPERATING LICENSE NO.' DPR-3 YANKEE ATOMIC ELECTRIC COMPANY YANKEE' NUCLEAR POWER STATION DOCKET-N0. 50-029:
1 INTRODUCTION i
By letter dated April 19 1990, as supplemented on June 7, 1990, the' Yankee Atomic Electric Company YAEC or the licensee) requested an amendment to e
FacilityOperatingLicenseNo.DPR-3for.theYankeeNuclearPowerStation(YNPS-ortheplant). The proposed amendment would modify Technical Specification-Surveillance Requireinent 4.5.2a to change the ECCS pump surveillance frequency from monthly to quarterly and to remove the minimum required discharge pressures l
from the Technical. Specification.
EVALUATION l
The licensee is proposing to bring the High Pressure Safety I'njection (HPSI) and LPSI pump surveillance frequency requirements in line with the Standard Technical Specifications for Westinghouse Pressurized Water Reactors (PWRs):
contained in NUREG-0452, Revision.4, while providing for re-establishment of-ASME XI inservice testing reference values as provided.for in the code; j
NUREG-0452 requires surveillance of these pumps only when they are being tested to meet the in-service testing required by Section XI of the ASME Boiler l
and Pressure Vessel Code in effect for each specific plant, d
The code in effect for Yankee Nuclear Power Station (YNPS) is the 1977 edition through the 1978 summer addendum which requires monthly pump testing. However, editions and addenda to the code after this have changed pump testing to quarterly. Yankee's In-service Testing Program is being updated to a later edition of the code which will require quarterly pump testing.
By:1etter dated October 3 -1989 the licensee requested specific code relief to perform quarterly.pumpInservlcetestingonaninterimbasisuntiltheprogramis formally updated. This relief was granted on April 11.-1990, one week prior to the filing of the instant request for license amendment. This proposed change will bring the licensee's pump testing requirements in line with the Westinghouse Standard Technical Specifications of NUREG-0452, the intent of
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which is to link the Emergency Core Cooling System (ECCS) pump surveillance-to the ASME Section XI Program.
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. J The Inservice Training Program at YNPS will continue to ensure that pump operational readiness criteria are consistent with the requirements of ASME l
XI. System performance surveillance will continue to be conducted in accordance with plant Technical Specifications.
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The minimum discharge pressure requirement is being deleted from the surveillance ri.quirement in Technical Specification (TS) 4.5.2a because ECCS pump oprability is verified through implementation of the Inservice Testing (IST) Program n delineated in TS 4.0.5, which does not have a specific requirement and acceptance l
j criterion on minimum discharge pressure.
Safety Injection System performance surveillance including minimum discharge pressure is currently and will continue to be conducted in accordance with TS 4.5,2,f&G. These surveillance requirements verify that the system develops the required flows and pressures in response to the most limiting large and small break LOCA events analyzed'in the Final Safety Analysis Report.
Based on the above evaluation of the licensee's submittal, the staff finds-that there is reasonable assurance that operation of YNPS consistent with the TS will not endanger the health and safety of the public and that the change is acceptable.
P ENVIRONMENTAL CONSIDERATION This amendment involves a change in a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes to the surveillance requirements. The staff has deter-mined 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 that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously published a proposed finding that the amendment involves no significant hazards consideration and there has been no public coment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuantto10CFR51.22(b),noenvironmentalimpactstatementorenvironmental assessment need be prepared in connection with the issuance of this amendment.
CONCLUSION The Comission made a proposed determination that the amendment involves no significant hazards consideration which was published in the Federal Register (55 FR 26299) on June 27, 1990. No public comments were received and the State of Massachusetts did not have any coments.
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i The staff has 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 activities will be conducted in compliance with the Commission's regulations,fense and security or to the health and safety and(3)theissuanceofthisamendmentwillnotbe inimical to the common de of-the public.
Principal Contributor: Patrick Sears Dated: September 6.1990 J
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- .._s AMENDMENT.NO. 135 TODPR-3YANKEENUCLEARPOWERSTATION(ROWE) DATED 9/6/90 i
LA DISTRIBUTION:
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'S. Varga.
R. Wessman B. Clayton P. Sears V. Merses.
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