ML20207R684

Safety Evaluation Supporting Amend 90 to License DPR-61

ML20207R684
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/11/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20207R670	List: ML20207R669 ML20207R680 ML20207R684 ML20207R689
References
NUDOCS 8703180021
Download: ML20207R684 (4)

Text

. .

[aurg' IS UNITED STATES

{ J,;g;yf,7gf[ g NUCLEAR REGULATORY COMMISSION 5 M'

[ 'VASHINGTON, D. C. 20555

%,[R:Of f

+....

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. go TO FACILITY OPERATING LICENSE NO. DPR-61 CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213

1.0 INTRODUCTION

By letter dated December 24, 1986,~the Connecticut Yankee Atomic Power Company (CYAPC0) submitted a request for changes to the Haddam Neck Plant technical specifications.

The amendment revises the second note of clarification to the definition of Containment Integrity, Technical Specification Section 1.8.2.b, by including two additional valves (CC-V-884 and SS-V-999V). Also, this note has been revised to: (1) allow these manual containment isolation valves to be opened to perform periodic surveillance, (2) ensure that technical specifications limits are maintained, or (3) ensure that system operability is maintained. The previous version of this note allowed SA-V-413 to be openeo in support of maintenance activities. This was deleted in response to the NPC's SER on Amend.nent 86.

A Notice of Consideration of Issuance of Amendment to License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested ~ action was published in the Federal Register on January 28,1987(52FR2078). No comments or requests for hearing were received.

2.0 EVALUATION By letter dated December 24, 1986, CYAPC0 requested revisions to the Haddam Neck. Plant technical specifications to include two additional N>[

P D ,

2-manual containment isolation valves in the second note of clarification to Technical Specification 1.8, " Containment Integrity."

This amendment will allow periodic opening of the neutron shield tank fill valve and neutron shield tank sample line valve (CC-V-884 and SS-V-999A respectively). Opening of these valves is important to plant opera-tion. Valve CC-V-884 is opened once approximately every two months for a few minutes to top off the neutron shield tank surge tank to compensate for evaporation and sampling losses. Because neutron shield tank level in-strumentation monito'rs the surge tank level, operation of this valve ensures that the tank level can be monitored in the control room. Main-taining a filled neutron shield tank is required to maintain low neutron dose levels in containment and acceptable temperature levels for certain nuclear instrumentation and snubbers. Valve SS-V-999A is opened approxi-mately once a month for 30 minutes so that a sample can be drawn. The sample is analyzed to determine water chemistry to ensure that tank inte-

'grity is maintained.

The staff has reviewed the information presented by the licensee concerning operation of valves CC-V-884 and SS-V-999A. Both valves require local mani-pulation by an operator during the required surveillance activities. Each valve is opened and closed independently so that during the surveillance operation only one isolation valve is open at any time. Further, the li-censee has stated that the operator performing the valve manipulation is in constant communication with the control room. In the event of a containment isolation actuation signal (CIAS), the operator manipulating the subject valve will be promptly notified and the valve can be isolated within 60 seconds.

If CC-V-884 should fail to close on a CIAS, water pressure in the component cooling water system would prevent any leakage of containment atmosphere through this penetration. If component cooling water pressure is lost, a check valve upstream of CC-V-884 will isolate this penetration.

. u

~

If SS-V-999A should fail to close or be delayed following a CIAS, the entire contents of the neutron shield surge tank would have to drain through the 3/8 inch valve before containment leakage could occur.

Due to elevation differences, the neutron shield tank cannot drain entirely through this line. In addition, if the operator is unable to close valve SS-V-999A, another manual valve (SS-V-999) is readily accessible to isolate the sampling line.

We therefore, cpnclude that the proposed license amendment is acceptable given the licensee's comitment that (1) the valves (CC-V-884 and SS-V-999A) are opes'ated individually, (2) the operators manipulating the i

subject valves are in constant communication with the control room and (3) that upon a containment isolation signal, these operators are immediately available to isolate the subject valves within 60 seconds.

3.0 ENVIRONMENTAL CONSIDERATION

t This amendment involves a change to a requirement with respect to the

[

installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes to the surveillance requirements. The staff has determined that the amendment involves

[.

no significant increase in the amounts, and no significant change in the types, of any effluent 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 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 this amendment.

l

4.0 CONCLUSION

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 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.

5.0 ACKNOWLEDGEMENT l

l This Safety Evaluation has been prepared by F. Akstulewicz, PBIA, DPWRL-B.

l Dated: March 11, 1987

~

l

__ _,,_________.-______m__..__ _