ML19345B175
| ML19345B175 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/17/1980 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19345B170 | List: |
| References | |
| NUDOCS 8011260257 | |
| Download: ML19345B175 (3) | |
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NOV 171980 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION IN SUPPORT OF CHANGE TO TECHNICAL SPECIFICATION 4.4.6.2.2 FOR NORTH ANNA POWER STATION, UNIT 2 l
I INTRODUCTION In a letter, dated November 4,1980, the Virginia Electric and Power Company (VEPCO) requested a change to the North Anna Power Station Unit 2 Technical scecification 4.4.6.2.2.
The Technical Specification now requires all pressure isolation I
valves to be leak tested prior to entering hot shutdown (Mode 4) on a periodic testing interval or each time the valve is disturbed.
VEPCO has requested that the Technical Specification be changed to permit leak testing prior to entering j
startup (Mode 2) for all pressure isolation valves identifed in Table 3.4-1 of the Techn % 1 Specifications.
EVALUA7 ION j
The basis for requesting this change is as follows. Leak testing the pressure isoltion valves prior to entering Mode 2 will (1) allow high pressure testing at actual functional pressure, (?) allow testing in lower operational modes, and (3) gives more accurate data because correction factors applied to measured leak races will not be used.
Wo have concluded that leak testing at a higher pressure with a larger differential pressure across the valve will produce a more accurate 8011260 86b
. NOV 171980 calculation of leak rate and more closely simulate actual operating conditions since extrapolation methods are not required. Also, high pressure testing will ensure proper seating of check valves used as pressure isolation valves allowing a more meaningful leak test at operating cor.ditions. We also conclude that reasonable assurance will be provided that the design pressure of low pressure systems which interface with the reactor coolant system will not be exceeded. Thus, the probability of an intersystem LOCA will not be increased.
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 Section 51.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment, i
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 or a significant decrease in any safety margin, it 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 l
. NOV 171980 operation in the proposed manner; and (3) such activities will be conducted in compliance with the Commission's regulations.
Thus, the issuance of this amendment to change the North Anna Power Station, Unit 2 Technical Specification 4.4.6.2.2 to permit leak testing prior to entering startup (Mode 2) for all pressure isolation valves. identified in Table 3.4-1 of the Technical Specifications, will not be inimical to the common defense and security or to the health and safety of the public.
Also, we reaffirm our conclusions as otherwise stated in our Safety Evaluation Report and its Supplements.
Dated NOV 1 7 1500 a
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