ML20076B017
| ML20076B017 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/01/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076B012 | List: |
| References | |
| NUDOCS 9107090192 | |
| Download: ML20076B017 (4) | |
Text
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- y UNITED STATES j
i' NUCLEAR REGULATORY COMMISSION 3-o WASHINoToN. o.C. 20M6 g..v
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j SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION t
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At:0 AMENDMENT NO., j 35,Tp, FA,C),LJ,TY,p,PER,A,TJNG LICENSE NO. DPR-69 BALTIt10REGASANDEL,EERJ,C.,CpMPANY CALVERTCLIFFSNUCLEA,R,Pp!!E,R, PLANT, UNI,T,!1pS.1AND2 DOCKET NOS,.,,50-317 AND;5;0,,3)8,
1.0 INTRODUCTION
- By letter dated April 2,1991, the Baltimore ~ Gas and Electric Company (the licensee) submitted a_ request for changes to the-Calvert Cliffs Nuclear Power Plant, Unit.Nos. 1 and 2, Technical Specifications (TS). The requestea changes would modify the Definitions,- Section 1.8, and the.TS Surveillance Requirements, Section 4.6.1.1.b.
Section 1.8 defines.when containment integrity exists, Item 1.8.3 defines the conditions the containment. air locks must meet to assure containment integrity, and Section 4.6.1.1.b ' specifies-the required surveillances of-the air locks-to assure containment-integrity. The proposed changes will remove the existing requirement that the air locks be
= operable, in both the TS definitions.and surveillance sections, and replace it with the requirement that the. air locks be in compliance with the requirements-of:TS Section 3.6.1.3.- 3ection 3.6.1.3 provides.the limiting conditions of operation (LCO), applicable modes, and actions to be taken.(including the allowed out-of service times-for repairs) when the'airlocks are inoperable prior'to requiring a unit'to shutdown.
i 2.0 EVALUATION
- As noted
- in'the 11censee's submittal, the Calvert Cliffs Unit 2. Technical
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Specifications, as originallyLissued, and the subsequent: conversion offUnit 1-to the Standardized Technical Specification format, were written such that the definition.and the surveillance sections both require operable containment air locks to.show containment integrity.
However, TS Se;. tion 3.6.1.3 provides.the LCO,-applicable modes, and the actions to be taken when the airLlocks are inoperable. The design of the air locks and the_ impact of their being?
inoperable in relation to overall primary containment integrity was-taken into:
" consideration in establishing-the LCOs'and the action-statements of-TS Section 3.6.1.3.
The proposed change will allow >the use'of the current TS.specified-
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out-of-service times to repair air lock problems prior to requiring a unit to shutdown. ~The current TS requires shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> with no provision
=to allow for--the intended out-of-service times specified. This resulted in
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unintended and unnecessary re~strictions.
9107090192 910701
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2 Overall containment integrity is required to limit offsite doses from postulated Designs Basis Accidents (DEA) described in the Calvert Cliffs tiuclear Power Plant, linits 1 and 2. Updated Final Safety Analysis Report (UFSAR). The DBAs identified in Chapter 14 of the UFSAR which could occur at power and result in a release of radioactive material within the affected unit include a loss of coolant accident, riain steam line break, and a control eleotent asser.bly ejection accident. The containment design, safety function, and the related TS provide reasonable assurance that the releak of fission products to tre environment is limited to a small fraction of the total containment volume.
The licensee's safety evaluation indicated that the containment design provides for an allcwable lealage rate (L ) of 0.20% of the containment air s
weight per day.
Thisleakageratewasus8dintheoffsiteradiologicaldose calculations for Calvert Cliffs tiuclear power Plant, Units 1 and 2, and is the basis for TS 3.6.1.2.a.
An additional restriction irposed by 10 CFR Part 50, Appendix J, and TS 3.6.1.2.b, is t hat no ntore than 60% of this L be through Type, B and C penetrations. The cir locks are Type B penetrations.
E$ch containment air lock is further limited, by TS 3.6.1.3.b, to an overall leakage rate of 5% L
- a Both of the containoent air locks are designed with a door on each end.
Both doors are required to be closed during operation unless the air lack is being used for transit entry or exit through the containoent. Then, at least one door is required to be closed.
Each door contains a double seal.
The area between the double seal on a door is maintained pressurized to provide the leakage barrier.
In accordance with TS Surveillance Requirement 4.6.1.3.a.
the seal leakage of each containment air lock is routinely verified following its use to be no greater than 0.02' of the L
- a The operable seal of either door is sufficient to maintain the required containment barrier since each is designed to withstand the peak containment
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pressure calculated to occur following a DBA; however, both doors are kept closed when not in use to provide an additional barrier.
TS 3.6.1.3 was written to recognize this capability of a single door to serve as a leakage barrier and provided an allowed out-of-service time for one door in order to attempt repairs prior to requiring a shutdown.
However, due to the existing TS wording by which the containment integrity requirements reference the air lock doors (stating that the doors must be operable), the intent to govern airlock doors with the action statements of TS 3.6.1.3 is not allowed.
The staff has reviewed and agrees with the licensee's findings as detailed above and therefore; find the proposed changes acceptable.
The staff's finding was based on: 1) the design of the air lock doors 2) the surveillance requirements of TS 4.6.1.3 imposed on the air locks, 3) the LCOs and actions required by TS 3.6.1.3 when an air loci is determined to be inoperable and 4) the restrictions imposed by TS 3.6.1.2a and 3.6.1.2b relating to the overall allowed containment leakage, including any air lock door leakage.
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3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the Maryland State of ficial was notified of the proposed issuance of the amendments. The State official
- had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located withir, the restricted area as defined in 10 CFR Part 20 and changes to the surveillance requirements.
The NRC staff has determined that the amendments involve 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 issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public concent on such finding (56 FR 24205). Accordingly, the amendments meet 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 environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 CONCLUSION
' The Commission 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, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
D. Mcdonald Date: July 1, 1991
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July 1,1991 A copy of the related Safety Evaluation is enclosed.
A Notice of Issuance will be included in the Commission's next regular biweekly Federal Reaister notice.
Sincerely, C*1GINAL SIGNto BY Daniel G. Mcdonald, Senior Project Manager Project Directorate 1 1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
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1.
Amendment No.156 to DPR-53 2.
Amendment No.136 to DPR-69 3.
Safety Evaluation cc w/ enclosures:
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_ Distribution:
Docket File NRC & Local PDRs PDI.1 Reading SVarga JCalvo CVogan DMcDonald 0GC DHagan GHill (6)
Wanda Jones CGrimes ACRS (10)
GPA/PA OC/LFMB RACapra Plant File JLinville CMcCracken OFC
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