ML20149M575
| ML20149M575 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 02/17/1988 |
| From: | Colburn T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149M578 | List: |
| References | |
| NUDOCS 8802260133 | |
| Download: ML20149M575 (6) | |
Text
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7590-01 UNITED STATES NUCLEAR REGULATORY COMISSION CLEVELAND ELECTRIC ILLUMINATING COMPANY, ET AL.
DOCKET NO. 50-440 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENOMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION The U. S. Nuclear Regulatory Comission (the Comission) is considering issuance of an amendment to Facility Operating License No. NPF-58 issue 8 to the Cleveland Electric Illuminating Company (CEI), the Duquesne Light i
Company, the Ohio Edison Company, the Pennsylvania Power Company, and the Toledo Edison Company (the licensees) for operation of the Perry Nuclear Power Plant, Unit No.1, located in Lake County, Ohio.
The licensee's application for amendment was dated February 12, 1988, i
The amendment would modify Technical Specification (TS) 3.4.3.1 to I
delete the requirement that the upper drywell air coolers condensate flow rate monitoring system be operable so long as the drywell floor drein j
monitoring system remains operable.
Current TS's require three combinations of reactor coolant system (RCS) leakage detection systems to be operable. These are:
1.
Drywell atmosphere particulate or gaseous radioactivity monitoring system;
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2.
Drywell floor drain sump and equipment drain sump flow monitoring system; and 3.
Upper drywell air coolers condcnsate flow rate monitoring system.
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. With only two of the above systems operable, operation may continue for 30 days, provided certain conditions are met, otherwise the plant will be in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The upper drywell cooler condensate flow monitoring system became inoperable on February 6, 1988. Without the reouested change, the plant will be required to be shut down on March 7, 1988. As there is not sufficient time to allow for a full 30 days notice of this proposed amendment in the FEDERAL REGISTER, the licensees have requested that the amendment be processed under exigent circumstances in accordance with 10 CFR 50.91(a)(6).
L The NRC staff has reviewed the circumstances resulting in the submittal of the proposed TS changes.
Failure to act would result in shutdown of the Perry Nuclear Power Plant on March 7, 1988.
Further, the licensees could not have anticipated the need for the proposed change prior to the upper drywell air coolers condensate flow monitoring system becoming inoperable on February 6, 1988. Accordingly, the NRC staff has determined that sufficient justification exists for consideration of these amendments on an emergency l
basis.
Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act o' 1954, as amended (the Act), and the Commission's regulations.
The Conmission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission's
. regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
The NRC staff has reviewed the licensee's proposed change and has proposed to determine that the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed change would permit continued plant operation with the upper drywell air cooler condensate flow rate rnonitoring system inoperable, as long as the drywell floor drain flow monitoring system was operable.
The drytell floor drain flow monitoring system is class 1E powered, designed to withstand OBE loads, and has a sensitivity of detection of one (1) gpm within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The licensees have stated that the total flow ccming from the upper drywell coolers drain system is collected in the dry 9eil floor drain suinp and will be monitored by the drywell floor drain sump flow monitoring system whether the upper drywell cooler condensate flow monitoring system is operable or not. Therefore, any flow from the upper drywell coolers, which j
would be indicative of a possible steam leak, would still be rnonitored and j
quantified. Thus, there is no increase in the probability of an accident previously evaluated.
Since these systems are used to detect minor drywell
. leakages, but not used to mitigate the results of any accidents this proposed change will not increase the consequences of any previously evaluated accident.
The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
j The proposed change involves the reactor coolant system leakage detection systems, a group of systems used to monitor for reactor coolant leaks within the drywell.
Since these systems are used for monitoring only, the change cannot create a new or different kind of accident from any previously etaluated.
The proposed change does not involve a significant reduction in a margin of safety.
The proposed change does not change allowable leakage rates or how those leakage rates will be classified.
It attempts to take credit for a redundancy the licensees claim exists between the upper drywell cooler condensate drain flow monitoring system and the drywell floor drain sump flow monitoring system. As such, the proposed change does not involve a reduction in the margin of safety.
Therefore, based on these considerations and the three criteria given above, the Comission proposes to determine that the amendment request involves no significant hazards consideration.
The Comission has determined that failure to act in a timely way would result in an untimely and unnecessary shutdown of Unit 1 on March 7, 1988, with no enhancement of safety. Therefore, the Comission has insuffi-cient time to issue its usual 30-day notice of the proposed action for public coment.
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. If the proposed determination becomes final, an opportunity for a hearing will be published in the FEDERAL REGISTER at a later cate and any hearing request will not delay the effective date of the amendment.
If the Commission decides in its final determination that the amendment does involve a significant hazards consideration, a notice of opportunity for a prior hearing will be published in the FEDERAL REGISTER and, if a hearing is granted, it will be held before any amendment is issued.
The Commission is seeking public comments on this proposed determination 1
of no significant hazards consideration. Any comments received by March 7, 1988 will be considered in making any final determination. Comments on the proposed determination may be submitted in writing to the Rules and Procedures Branch, Division of Rules and Records, Office of Administration, U. S.
Nuclear Regulatory Commission, Washington, D. C.
20555, and should cite the publication date and page number of this FEDERAL REGISTER notice. Written 1
comments may also be delivered to Room 4000, Maryland National Bank Building, 7735 Old Georgetown Road, Bethesda, Maryland, from 8:15 A.M. 5:00 P.M.
4 Copies of written concents received nuy be examined at the NRC Public Document Room 1717 H Street, N. W., Washington, D. C.
For further details with respect to this action, see the application for amendment dated February 12, 1988 which is available for public
. inspection at the Comission's Public Document Room,1717 H Street, N.W.,
Washington, D.C., and at the Perry Public Library, 3753 Main Street, Perry, Ohio 44081.
Dated at Rockville, Maryland this 17th day of February,1988.
FOR THE NUCLEAR REGULATORY C0f9tISSION b
'M 4-O//be%
Timothy G. Co burn, Project Manager Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects t
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