ML20041D137
| ML20041D137 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/08/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20041D129 | List: |
| References | |
| NUDOCS 8203040345 | |
| Download: ML20041D137 (3) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION 3
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NOS. 67 AND 49 TO FACILITY OPERATING LICENSE NOS. OPR-53 AND DPR-69 BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318 Introduction By application dated December 21, 1981, the Baltimore Gas and Electric Company (BG&E) requested changes to the Technical Specifications (TS) for Calvert Cliffs Units 1 and 2.
The proposed changes to TS 3.7.1.2 and 4.7.1.2 would require operability and verification of the auxiliary feedwater system throtti valves. The application of December 21, 1981 was submitted in response to our letter of May 29, 1981.
Discussion and Evaluaticn License Amendment 54 and'37 for Calvert Cliffs Units 1 and 2 provided augmented TS for operability and surveillance for the Calvert Cliffs Units 1 and 2 auxiliary feedwater (AFW) systems. Subsequent review of TS 3.7.1.2 and 4.7.1.2 indicated that no requirements existed for the operability, setting, and verification of the AFW throttle valves. By letter dated May 29, 1981, we requested that BG&E propose TS that would assure operability and proper setting of the AFW throttle valves. The BG&E application dated December 21, 1981 meets our requirements, in this regard.
As indicated in the December 21, 1981 BG&E application, an automatic AFW flow of between 88 gpm (plus 12 gpm for instrument error) and 142 i
gpm (minus 12 gpm for instrument error) provides an acceptable range of initial AFW flow to each steam generator at 900 psia. The lower-i limit of acceptable, automatic, AFW operation, 88 gpm, allows 20 minutes for the reactor operator'to manually increase AFW flow to the desired l
value to maintain an adequate primary system heat sink, should AFW operation be required. The upper limit of acceptabie, automatic, AFW operation,142 gpm, allows 20 minutes fer the reactor operator to terminate AFW operation thould main feedwater be avail ble; failure to terminate AFW operation, in this case, could lead to primary system overcooling i
and subsequent safety injection actuation.
Based upon the above, it is appropriate to set the AFW throttle valves to deliver between 100 l
and 130 gpm per steam generator, at 900 psia and this requirement should j
be incorporated in the TS.
i 8203040345 820208 PDR ADOCK 05000317 i
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, At the present time, TS 3.7.1.2 requires the operability of the AFW system and associated flow pathes. The BG&E application proposed that the automatic flow initiation feature, with throttle valves set between 100 and 130 gpm at 900 psia, also be required to be operable. Operability of this feature in Mode 3 (hot standby) is not proposed since under non-power conditions, the AFW need not be automatically initiated to maintain an adequate primary system heat sink.
The Bases for TS 3.7.1.2 have been proposed for modification to relect the rationalefor selection of AFW throttle valve settings.
In addition to the surveillance requirements of TS 4.7.1.2, BG&E has proposed two additional requirements. The 18 month AFW surveillance described in TS 4.7.1.2c would be augmented by adding proposed TS 4.7.1.2c.3 which requires verification of automatically initiated AFW flow to be between 100 and 130 gpm, per steam generator, at a steam pressure of 900 psia.
In addition, TS 4.7.1.2d would be added to require verification of proper realignment of AFW throttle valve settings should these throttle valves be repositioned.
The requirements of TS 4.7.1.2d would not be applicable during MODE 3 since the automatic initiation features of the AFW is not required to be operable in MODE 3.
I.t is our intent however, that the licensee realign the AFW throttle valves as soon as practicable following entry into MODE 2 (operation up to 5% power) if necessary.
Based upon our evaluation, we find that the proposed changes to the TS, and associated. Bases, are acceptable. The TS, as amended, assure that the AFW throttle valves will be properly set such that sufficient time is permitted for the reactor operator to terminate AFW operation, or increase AFW flow, as required.
In additicn, the augmented surveillance requirements provide sufficient confidence that the AFW throttle valves will be properly adjusted and readjusted should their setting be altered.
Accordingly, we conclude that the consequences of transients and accidents for which AFW operation is required, and for those transients and accidents for which AFW operation is not desirable, have not increased.
Environmental Consideration We have determined that the amendments do 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 deteraination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and, pursuant to 10_CFR $51,5(d)(4), that an environmental impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection with the
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issuance of these amenda..nts, f
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t 3-Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendments do not involve a significant increase in tne probability or consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendments do 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) i such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Date: /ebruary 8, 1982 Principal Contributor:
Dave Jaffe 1
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