ML20248C062

Safety Evaluation Supporting Amend 97 to License DPR-6

ML20248C062
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	05/31/1989
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20248C054	List: ML20248C050 ML20248C057 ML20248C062
References
NUDOCS 8906090251
Download: ML20248C062 (3)

Text

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SAFETY EVALUATION'BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 97 TO FACILITY OPERATING LICENSE NO. DPR-6 CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET NO. 50-155

1.0 INTRODUCTION

By letter dated April 21, 1986, Consumers Power Company (the licensee) pr.oposed -

several changes to the Technical Specifications pertaining to its alternate shutdown system. The licensee revised its proposed changes by letter dated February 6,1987, which superseded preceding submittals dated September 30, 1985, March 4, April 21, and December 17, 1986, and the additional information provided on' August 27, 1986. The subsequent submittals after the original proposed changes, dated September 30, 1985, provide clarifications based upon reviews by the licensee and the NRC. .

2.0 DISCUSSION The licensee on September 30, 1985 submitted its initial request to add operability and surveillance requirements for the alternate shutdown system installed in accordance with Appendix R to 10 CFR Part 50. The subsequent submittals provided technical specifications for the active fire barriers and the fire detection instrumentation for the Auxiliary Shutdown Building and addressed concerns raised during subsequent reviews by licensee and the NRC staff's preliminary reviews. The alternate shutdown system design was approved by an NRC Safety Evaluation dated March 8,1983 with added requirements based on applicable portions of draft standard Technical Speci-fications.

The following changes to the plant's Technical Specifications (TS) were proposed by the licensee:

2.1 Table of Contents The Table of Centents is revised to reflect changes made to the Fire Detection and Fire Suppression Systems, Penetration Fire Barriers, Alternate Shutdown Systems and Bases.

2.2 Alternate Shutdown Battery System The Alternate Shutdown Battery System has been added to Sections 11.3.5.3 and i 11.4.5.3, Emergency Power Source.

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2.3 Bases for Sections 11.3.5.3 and 11.4.5.3 A paragraph has been added to the Bases for Sections 11.3.5.3 and 11.4.5.3 pertaining to the size of the Alternate Shutdown Battery System discussed in Section 2.2 above.

2.4 Addition'to Table 3.3-8 Add Item 13. Alternate Shutdown Building to Table 3.3-8 in Section 3.3.3.8.

2.5 Section 3/4.7.12 '!

The Limiting Condition for Operation concerning operability of fire barriers is revised to include fire doors and fire dampers.

'2.6 Alternate Shutdown System - Sections 3/4.7.13 Additions have been made to the Limiting Conditions for Operation in Sections 3/4.7.13 and Tables 3.3-9 and 4.3-9 to include equipment in the Alternate Shutdown System.

3.0 EVALUATION We have reviewed the technical support furnished by ths licensee for each of its proposed changes. Our evaluation for each of them follows in the same order in which they are listed in Section 2.0, Discussion above.

3.1 Revisions to Section 12.0 of the Table of Contents are required because of the other proposed changes to the body of the TS. These changes to Section 12.0 shown on Page ii of the TS, are acceptable.

3.2 The addition of the " Alternate Shutdown Battery System" to Sections 11.3.5.3 and 11.4.5.3, Emergency Power Sources, providbs all of the equipment necessary to assure that hot shutdown of the reactor can be achieved and maintained indefinitely. We agree with the technical support provided by the licensee and find acceptable the changes as shown on Pages 11-17 through 11-19a of the TS.

3.3 The " Alternate Shutdown Battery" supplies power to the main steam isolation valve, the emergency condenser outlet valves, and other alternate shutdown equipment. This proposed change to' the Bases states that the battery will be sized so as to remain operational for at least six or nine days (depending on minimum temperature of 25 F or 40 F, respectively) even if the battery charger fails. We agree with the technical support furnished by the licensee and find acceptable the change as shown on Page 11-20 of the TS.

3.4 Table 3.3-8 lists Fire Detection Instrument requirements for various areas and buildings of the plant. " Item 13. Alternate Shutdown Building" was added to Table 3.3-8 to reflect the protection provided for this new facility. We agree with the technical support provided by the licensee and find acceptable the change as shown in revised Page 12-2 of the TS.

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3.5. The addition of active fire barriers (fire doors and fire dampers) to the existing requirements in Section 3/4.7.12 establishes surveillance and operability requirements which will verify that such active barriers are capable of performing their intended safety functions. We find acceptable the addition to the Specifications as shown on Page 12-7 and'the accompanying expanded Bases as shown in the addition to Page 12-11 of the TS.

3.6 The new Limiting Conditions for Operation contained in Sections 3/4.7.13 i and Tables 3.3-9 and 4.3-9 establish surveillance and operability requirements '

for components of the new Alternate Shutdown System. We note one error, however, on Page 157a in the February 6,1987 submittal. Item 1 under TRANSFER SWITCHES / POWER SUPPLIES / CONTROL CIRCUITS indicates with an asterick (*) that "Section 3.7.13(a) applies only if the alternate i shutdown controls for both emergency condenser outlet valves, M0-7053 and 1 M0-7063, are inoperable at the same time." In the February 6,1987 revision (a)and [b) have been combined into a single unlettered paragraph.Sect Therefore, the reference on Page 157a should be to Section 3.7.13. With this change, we find acceptable this addition to the Specification as i shown on Pages 12-8,12-9 and 12-10 and the accompanying expanded Bases as shown in the addition of Page 12-12 of the TS.

Based upon the above evaluation, we conclude that the six changes to the Technical Specifications for the Big Rock Plant as proposed and described by the licensee in its April 21, 1986 submittal, and later revised in their letters of December 17, 1986 and February 6,1987, should be approved.

4.0 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 a change in a surveillance requirement.

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 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 meets the eligibility criteria for categorical exclusion set forthin10CFR51.22(c)(9). Pursuantto10CFR51.22{b),noenvironmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

5.0 CONCLUSION

We have concluded, based on the considerations discussed above, that (1) there is reasonable assurance thm, 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 the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Dated: May 31, 1989 Principal Contributor: D. Notley

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