ML20028H400
| ML20028H400 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/26/1990 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20028H401 | List: |
| References | |
| NUDOCS 9101020340 | |
| Download: ML20028H400 (4) | |
Text
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UNITED STATES
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SAFCTY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 132 TO FACILITY OPERATlHG LICENSE NO. OPR-72 FLORIDA POWER _ CORPORATION,_ET AL.
CRYSTAL _RIVERUNIT_N0_.3 NUCLEAR _GENERATINGPLAE 00CKET NO._50-302
_ INTRODUCTION By letter dated September 28, 1990, florida Power Co% miion (FPC or the licensee) reouested an amendirent to the Technical Spee.!: cations (TS) appended i
to Facility Operating License ho. ORP-72 for the Crystal liver Unit No. 3 Huclear Generating Plant (CR-3). The repesed amendment 'vould change the TS by adding a f ootnote to Table 4.7-4, lydraulic Snubber Inspection Schedule, which would extend th next required inspection iriterval of 6 months (ending January. 30, 1991) until the end of the mid-cycle outage currenib planned for the f all of 1991, a total interval of approximately 15 months.
A visual inspection of all snubbers was performed during the refueling outage completed in June 1990, in accordance with TS 4.7.9.1.a.
Two snubbers were found to be inoperable. Therefore, TS Table 4.7-4 required a decreased inspection interval of 6 months until the next inspection, which would necessitate an otherwise unnecessary plant shutdown by January 30, 1991.
The licensee notes that inspections performed in the three previous inspection intervals have shown no visual inspection failures.
In addition, there is no apparent relationship between the two rectnt snubber failures, which have since been repaired, y:
EVAL'UATION
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Based on past and recant inspection results, the steff concludes that there is no apparent trend in snubber failures and that there is no apparent common-mode failure mechanism in the two recent failures.
The current requirements do not take the snubber population at a plant into consideration in deterir.ining the next inspection interval. A revision Ms been proposed to the American Society of Mechanical Engineers (ASME) Standard on Snubber Testing, OM-D, to relate inspection interval to snubber population and nunter of failures. Analytical evaluations by the staff confirm the validity of this approach.
Staff evaluation based on this approach indicates that for the number of failures (2)-and total snubber population of CR-3, the same confidence level can be maintained regarding the operability of snubbers within specified limits.for an increased inspection interval of at least that requested by the licensee.
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1 Therefore, based on the past inspection results of the hydraulic snubbers at CR-3 and our evaluation, we find the proposed one-time TS change for CR-3 acceptable.
_ ENVIRONMENTAL CONSIDERATION This amendment involves a change to a requirement with respect to installation or use of a facility component located withil the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. We have 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 that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously issued a proposed fincing that this amendment involves no significant tazards consideration and there has been no public coment on such finding. Accurdingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuantto10CFR51.22(b),noenvironmentalimpactstatementorenvironmental assetssment need be prepared in connection with the issuance of this amendment.
_CONCLU_SION We have concluded, based on the considerations discussed abort, 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 Comission's regulations and the issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public.
Dated: December 26, 1990 PrincipalContrjbutor:
H. Silver
C December 20, 1990 J
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DISTRIBUTION [
Docket No. 50-255 DOCKET FILE i NRC & LOCAL PDRs PD31 R/F Mr. Gerald B. Slade-JZWOLINSKI Plant General Manager SMEADOR Palisades Plant BH0LIAN 27780 Blue Star Memorial Highway OGC Covert, Michigan A3043 DHAGAN GPA/PA
Dear Mr. Slade:
SUBJECT:
PALISADES PLANT - NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMEiD (TAC NO. 77111)
The Commission has requested the Office of the Federal Register to publish the enclosed " Notice of Consideration of Issuance of Amendment to Provisional Operating License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing." This notice relates to your application for dmendment dated June 12, 1990, and subsequently revised by letters dated Hovember 9 and December 7, 1990. This application for amendment proposes to revise Technical Specification (TS) 3.3.1.b, " Emergency Core Cooling System", to reduce the required minimum boron solution level in the Safety Injection Tanks (SIT) from 186 ' inches to 174 inches, and to raise the maximum allowed tank level from 198 to 200 inches, This change effectively broadens the operating band at which S1T level must be maintained from 12 to 26 inches.
Two related Technical Specification changes were also submitted.
First, a new surveillance requirement to check the SIT high and low level alarms was proposed to be included in TS table 4.1.2.
Secondly, the Basis section for TS 3.3.1 has been updated and two TS references have been added.
The proposed changes provide increased flexibility-to the control room operators in maintaining SIT level within limits, while still providing assurance that adequate borated water is available for injection from the SITS.
Sincerely,
/s/
Brian 1;olian, Project Manager Project Directorate 111-1 9101020353 901220 PDR ADOCK 0D000255-Division of Reactor Projects III/IV/V P
PDR Of fice of Nuclear Reactcr Regulation
Enclosure:
~ Notice cc w/ enclosure:
See next page 4g LA/PD31:DRP3g!V PM/PD31:DRP3j5 D/PD31:DRP345
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December 20, 1990 4....
Docket No. 50-255 Mr. Gerald B. Slade Plant General Manager Palisades Plant 27780 Blue Star Memorial Highway Covert, Michigan 49043
Dear Mr. Slace:
SUBJECT:
PAllSADES PLANT - NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT (TAC N0. 77111)
The Commission has requested the Office of the Federal Register to publish the enclosed " Notice of Consideration of Issuance of Amendment to Provisional Operating License and Proposed No Significant Hazards Consideration Determination and Opportunit'/ for Hearing." This notice relates to your application f or amendment dated June 12, 1990, and subsequently revised by letters dated November 9 and December 7 1990. This application for amendment proposes to revise Technical Specification (TS) 3.3.1.b, " Emergency Core Cooling System", to reduce the required minimum boron solution level in the Safety Injection Tanks (SIT) from 186 inches to 174 inches, and to raise the maximum allowed tank level from 198 to 200 inches.
This change effectively broadens the operating band at which SIT level must be maintained from 12 to 26 inches.
Two related Technical Specification changes were also submitted.
First, a new surveillance requirement to check the SIT high and low level alarms war proposed to be included in TS table 4.1.2.
Sacondly, the Basis section for TS 3.3.1 has been updated and two TS references have been added.
The proposed changes provide increased flexibility to the control room operators in maintaining SIT level within limits, while still providing assurance that adequate borated water is available for injection from the SITS.
Sincerely, S~
Brian Holian, Project Manager Project Directorate 111-1 Division of Reactor Projects I!!/IV/V Office of Nuclear Reactor Regulation
Enclosure:
l Notice cc w/ enclosure:
See next page
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