ML20067A485
| ML20067A485 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 02/14/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20067A484 | List: |
| References | |
| NUDOCS 9402180057 | |
| Download: ML20067A485 (2) | |
Text
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WASHINGTON. D C. 20555 0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
55 TO FACILITY OPERATING LICENSE NO. NPF-58 THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.
PERRY NUCLEAR POWER PLANT. UNIT NO. 1 DOCKET NO. 50-440
1.0 INTRODUCTION
By letter dated September 23, 1991, Cleveland Electric Illuminatir.g Company (the licensee) requested a revision to the Technical Specifications (TS) for the Perry Nuclear Power Plant, Unit No.1.
The proposed amendment would revise TS 3.1.3.3 " Control Rod Scram Accumulators," to allow an alternate method for verifying that a control rod drive (CRD) pump is operating.
Such verification is required with more than one control rod scram accumulator inoperable.
The existing Perry TS requires that at least one control rod be j
inserted at letst one notch as a verification that a CRD pump is operating.
The proposed change would allow alternate verification that a CRD pump is running by direct indication of the control rod charging water header pressure.
l 2.0 EVALUATION The CRD pumps supply water to the hydraulic control units (HCUs) for insertion i
l and withdrawal of control rods, charging of the scram accumulators, and the i
cooling of the control rod drive mechanisms.
There is one HCU per control i
rod.
The control rod scram accumulators are located on the HCUs and ensure that the control rods scram at any reactor pressure within the required scram insertion times of TS 3.1.3.2.
The operating CRD pump provides water at approximately 1720 psig to the charging water header.
A check valve in each accumulator charging line prevents the loss of pressure for a limited time, when supply pressure from the CRD pump is lost.
Check valve integrity is verified each refueling outage.
l Perry has had an occurrence where power was lost to the Rod Control and Information System. Upon this loss of power, control rods cannot be moved (except by scram) and accumulator status indication is lost. Under current TS, operators would have an inappropriately short time to fix'the problem because of the inability to insert a control rod one notch to verify an operating CRD pump.
The proposed alternate CRD pump operating verification method would avoid the above TS problem and result in a more appropriate amount of time to fix the plant problem. Charging water header pressure in excess of 1520 psig is acceptable as an alternate verification method, because if a CRD pump is not operating, CRD system pressure decreases rapidly due to cooling water flow discharging to the reactor vessel.
However, the primary and preferred verification method is by inserting a control rod one notch.
9402180057 940214 PDR ADOCK 05000440 PDR p
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. The NRC staff has reviewed the licensee's proposed alternate method to verify an operating CRD pump, and based on the above, finds it to be acceptable.
3.0 STATE CONSULTATION
In accordance with_ the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment.
The State official had i
no comments.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment changes a requirement with respect to the installation or use i
of a facility component located within the restricted area as defined in 10 CFR Part 20. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there. is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public l
comment on such finding (56 FR 57705). Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR l
51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
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5.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner,.(2) such activities will be conducted in compliance with the Commission's regulations, i
and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
1 Principal Contributor: J. Hopkins Date:
February 14, 1994 l
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