ML19323B177
| ML19323B177 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 04/14/1980 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19323B168 | List: |
| References | |
| NUDOCS 8005120044 | |
| Download: ML19323B177 (3) | |
Text
_ -__
+-...
- sa rreg
' 80 0512 OdW
[.o
'O UNITED STATES '
[ 'i.
.[. i
' NUCLE AR REGULATORY COMMISSIGN -
j i
s WASHING T O N. D. C. 205L
-q.g j
}, b 4
5
, SAFETY EVALUATION BY THE 0FFICE OF NUCLEAR REACTOR REGULATION SUPPORTING A!1ENDMENT N0. 34 TO FACILITY OPERATING LICENSE NO. DPR-61 CONNECTICUT YANKEE ATOMIC POWER COMPANY
'S HADDAM NECK' PLANT DOCKET N0. 50-213 1.0 Introduction I&E Bulletin 79-06A, Revision 1, listed several areas of concern to be evaluated by licensees as a result of the Three Mile Island-2 accident including improvement of the reliability of auxiliary feedwater systems.
By letter dated June 1,1979, the Connecticut Yankee Atomic Power Company (the licensee) proposed changes to Sections 3.8 and 4.8 of the Technical.
Specifications appended to Facility Operating Lichnse No. DPR-61 for the Haddam Neck Plant which would revise the limiting conditions for operation and the surveillance requirements for the auxiliary feedwater system, including pumps, piping, and water sources.
The proposed changes-are designed to further ensure the availability of tne auxiliary feedwater system by providing more comprehensive and complete limiting conditions for operation and surveilla'nce requirements.
2.0 Discussion and Evaluation 2.1 Section 3.8 - Turbine Cycle
.The changes proposed for this section include provisions which would require that:
(a) Both steam-driven auxiliary feedwater pumps'be operable during
. power operation and capable.of providing an adequate supply of feedwater to the steam generators to remove ' decay heat following reactor shutdown. 'The1 proposed. change would also: improve the
. probability thatiat least one pump would be available at all times.
(b). If;one : auxiliary feedwater _ pump becomes inoperable, it-must be restored to an operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or thel plant must ~
- befplaced in at_least hot standby-condition within the:next 6
. hours and in hot shutdownLwithin the following-: 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />._ By requiring
- Lthat:an inoperable auxiliary feedwater, pump be restoredito service
'quickly,--the probability is increased that at leastoone pump would
~
1
' be available when ~ needed.
E-l'
- ~ R -
..m__
. (c)
If the level of water in the demineralized water storage tant, (DWST) falls below 50,000 gallons, or if the DUST becones otherwise inoperable, the DWST level must be restored and the DWST must be operable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or else the plant must be placed in the hot standby condition within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in the hot shut-down condition within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. This requirement is intended to further ensure that an adequate supply of feedwater is available to remove reactor decay heat following a reactor shutdown.
(d)
If the level of water in the primary water storage tank (PUST) falls below 80,000 gallons, or if the PWST becomes otherwise inoperable, the PWST level must be restored and the PWST must '>e operable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or an equivalent supply of water must be tade available from an alternate source or else the plant must be placed in the hot standby condition within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in the hot standby condition within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The PWST is a backup water supply for the DWST, and this requirement is intended to ensure that an adequate backup supply of feedwater is available to remove reactor decay heat following a reactor shutdown.
2.2 Section 4.8 - Auxiliary Steam Generator Feedwater Pumps The changes pravided for this section would provide more detailed require-ments to verify the operability of the auxiliary steam generator feedwater pumps and their ability to respond properly when required. The additional requirements include position checks of all non-automatic valves in the flow path and detailed minimum performance standards for the auxiliary feedwater pumps which must be tested monthly.
The greater detail required by these checks improves the capability to detect inoperable equipment and, therefore, improves the reliability of the auxiliary feedwater system.
All of the proposed changes are consistent with current licensing require-ments set forth in the Standard Technical Specifications for Westinghouse reactors.
Based on this and the above considerations, we find these changes acceptable for inclusion in the Haddam Neck Technical Specifications.
3.0 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 sig~nificant 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 tn 10 CFR 551.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisai need not be prepared in connection with the issuance of this amendment.
. 4.0 _ Conclusion We have concluded, based upon the considerations discussed above, that:
(1) because the amendner.t does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve significant decrease in a safety margin, the amendrent 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 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.
Date: April 14, 1980 e
d
.