ML19345H634
| ML19345H634 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/14/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19345H633 | List: |
| References | |
| NUDOCS 8105210495 | |
| Download: ML19345H634 (3) | |
Text
'
l j.a aeg[c UNITED STATES y,
y e(,
g NUCLEAR REGULATORY COMMISSION
-s r
wAsHWGTON, D. C. 20555 s
'%f,'.'.,e,$'
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIGN SUPPORTING AMENDMENT NO. 28 ANO f;0. 9 TO FACILITY OPERATING LICENSE NOS. NPF 4 AND NPF-7 VIRGINIA ELECTRIC AND 00WER COMPANY NORTH ANNA POWER STATION, UNITS NO. 1 AND NO. 2 DOCKET NOS. 50-338 AND 50-339
==
Introduction:==
By letter dated July 30, 1980, the Virginia Electric and Power Company, (the licensee) requested an amenciment in the form of changes to the Technical Specifications for Facility Operating Licenses NPF-4 and NPF-1 for the North Anna Power Station, Unit Nos. 1 and 2 (NA-1&2).
The requested changes involve:
(1) channel functional testing for loss of power circuitry, (2) consistency in the Technical Specifications for the steam jet air ejector isolation valves, and (3) changes in the Technical Specifications regarding the licensee's management reorganization.
Secause of the many occuring changes in the licensee's management reorganiza-tion after the July 30, 1980 request, these changes were held in abeyance until all of the management reorganization change requests were received for our evaluation.
We have now reviewed and evaluated the licensee's management reorganization and these matters will be issued in a separate, forthcoming amendment addressing the Administrative Controls, Section 6 of the Technical Speci-fications for NA-l&2.
Therefore, this safety evaluation addresses only the licensee's requested changes regarding items 1 and 2 above.
Discussion:
(1.) Channel Functional Testina for Loss of Power Circuitry:
Technical Specification 4.3.2.1.1 for NA-l&2 requires that a channel functional test t,e performed on a monthly basis for the Loss of Power circuitry.
The Loss of Power Circuitry at NA-l&2 has been cesigned to detect a total loss of cffsite power or a degraded voltage condition. After initiation and a suitable time delay, emergency loads are separated from the offsite power source and loaded onto the onsite power system.
81052104D4
. The licensee has requested a change in Table 4.3-2, Items 7a and 7t; to revise the existing requirement which specifies the performance of a channel functional test every 31 days. The change would require the performance of a channel functional test for each logic channel on a bi-monthly basis.
(2.) Steam Jet Air Ejector Isolation Valves:
By letter dated November 28, 1978, the NRC identified a number of concerns with containment purging during normal plant operations. By letter dated October 29, 1978 the NRC requested an interim commitment from licensees to limit purging and venting during normal operation.
Our review and evaluation of these matters identified a conflict in the applicability of Technical Specification 3.6.1.1 and 3.6.5.1.
Technical Specification 3.6.1.1. requires that primary containment integrity be maintained when operating in Modes 4, 3, 2 and 1 (Hot Shutdown, Hot Standby, Startup and Power 0 ? ration, respectively). Technical Specification 3.6.5.1 requires that the st iam jet air ejector isolation valves be closed when operating in Modes 1, 2, and 3, thus conflicting with Technical Specification 3.6.1.1.
We identified our concern to the licensee, and by letter dated July 30, 1980, the licensee proposed a change to Technical Specification 3.6.5.1 which would require the steam jet air ejector valves be closed in Modes 1, 2, 3 and 4.
Evaluation:
(1) The licensee's requested change to perform a channel functional test on a bi-monthly basis for each logic channel for Items 7a and 7b is consistent with the frequency interval stipulated for other logic testing specified in Table 4.3.2, Engineered Safety Feature Activation System Instrumentation Requirements.
This change will-enable the licensee to incorporate the surveillance prc Ndures for the logic testing required in Table 4.3.2 and thus obtain a mo e complete evaluation of safety system logic operation on-a bi-monthly basis. On this basis, we find the proposed change to be acceptable.
(2) The licensee has reponded to our concern regarding containment purging and isolation during normal plant operations. The deletion of operation.
of the steam jet air ejector system during Mode 4 will remove a potential path of containment leakage in the unlikely event of a loss-of-coolant-accident (LOCA) in Mode 4 operation. On this basis we find the proposed change to be acceptable.
3-Environmental Consideration We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made' this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 51.5(d)(4), that an l
environmental impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of this amendment.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in corpliance 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.
Date: May 14, 1981 1
i
- - - -. + - -
,y-....