PY-CEI-NRR-0592, Application to Amend License NPF-58,revising Tech Spec Table 3.6.4-1 to Change Max Isolation Time of RCIC Sys Inboard Containment Isolation Valve 1E51-F063 to 20 S.Fee Paid

Application to Amend License NPF-58,revising Tech Spec Table 3.6.4-1 to Change Max Isolation Time of RCIC Sys Inboard Containment Isolation Valve 1E51-F063 to 20 S.Fee Paid

ML20212J898
Person / Time
Site:	Perry
Issue date:	03/04/1987
From:	Edelman M CLEVELAND ELECTRIC ILLUMINATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20212J902	List: ML20212J926 PY-CEI-NRR-0592, Application to Amend License NPF-58,revising Tech Spec Table 3.6.4-1 to Change Max Isolation Time of RCIC Sys Inboard Containment Isolation Valve 1E51-F063 to 20 S.Fee Paid
References
PY-CEI-NRR-0592, PY-CEI-NRR-592, NUDOCS 8703090167
Download: ML20212J898 (3)

Text

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f THE CLEVELAND ELECTR P.O BOX 5000 - CLEVELAND. oHlo 44101 - TELEPHONE (216) 622-9800 - (LLUMINATING BLDG. - 55 PUBLICSoVARE Serving The Best Location in the Nation MURRAY R. EDELMAN SR. VICE PRESIDENT NUCWR March 4, 1987 PY-CEI/NRR-0592 L U.S. Nuclear Regulatory Commission Document Control Desk Washington D. C. 20555 Perry Nuclear Power Plant Docket No. 50-440 Exigent Technical Specification Change Request

Dear Sir:

Pursuant to 10 CFR 50.59, the Cleveland Electric Illuminating Company hereby requests amendment of Appendix A to the Perry Nuclear Power Plant ouerating license (NPF-58).

Summary The Reactor Core Isolation Cooling (RCIC) system inboard containment isolation valve (IE51-F063) is operated by a DC powered motor operator and is normally closed. During operation of the RCIC system, this valve must open to allow steam to pass to the RCIC turbine. CEI proposes to modify the position of this valve to normally open, and to replace the motor operator and supply it with Class IE AC power. Technical Specification (TS) Table 3.6.4-1 presently lists the maximum isolation time for this valve as 50 seconds. In order to allow this valve to remain normally open, and to remain consistent with the resulting environmental qualification and accident analyses, CEI proposes to change the maximum isolation time of tha IE51-F063 valve to 20 seconds. In addition, CEI is proposing changes to the respective DC power systems specifications, as this valve will no longer be powered from DC batteries.

l This modification in valve position (and the attendant TS changes) will provide an improvement in system reliability and availability. In that the modification will improve the reliability of the system, it is in the best interest of the company and the health and safety of the public to permit operation with this change as soon as possible.

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USNRC March 4, 1987 PY-CEI/NRR-0592 L Significant Hazards Analysis The standards used to arrive at a determination that a request for amendment requires no significant hazards consideration are included in the Commission's regulations, 10 CFR 50.92, which state that the 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, (2) create the possibility of a new or different kind of accident f rom any accident previously evaluated, or (3) involve a significant reduction in a margin of safety. CEI has reviewed the proposed change with respect to these three factors.

An analysis was performed to determine the possibility of an increase in offsite dose resulting from a pipe break in the RCIC steam supply line with the inboard containment isolation valve normally open. This analysis determined that a 20 second closing time for the IE51-F063 valve was bounded by the existing mainsteam line break analysis. For environmental qualification, CEI analyzed the RCIC pipe break event downstream of the outboard isolation valve.

This analysis demonstrated that line isolation with the 20 second closure time will not jeopardize equipment required for safe shutdown in the environmental zones related to the postulated pipe break.

The conversion of the 1E51-F063 valve from DC to AC will not significantly affect either the AC or DC power systems. The removal of the valve from Division II DC will reduce the one minute load and have a positive effect. The addition of the IE51-F063 valve motor operator will be insignificant to the Division II AC tystem compared to the other valve motor operators and other safety related motor J a vda, The supply will be from MCC EF-1-D-07, which is presently in the TS, This MCC is loaded considerably below capacity and remains so with the addition of the IE51-F063 motor operator.

The basic operation of the RCIC system will not change as a result af this proposea change. For its containment isolation function, the 1E51-F063 valve will maintain all of its previous isolation signals, will be capable of operating against the maximum calculated system pressure, and will continue to meet all applicable General Design Criteria of Appendix A to 10 CFR 50. The electrical supply for the AC motor operator will be designed in accordance with FSAR requirements with regard to cable routing and protection. The reliability of the controls and power supply will be similar to other AC powered operators.

The proposed change to allow the IE51-F063 valve to align in the normally open position increases the availability of the RCIC system as it will eliminate the active operating requirement of this valve for the RCIC systen initiation.

Converting the motor operator from DC to AC will reduce the battery load to 395 Amps for the first 60 seconds, which will not have any effect on any margins of safety in the TS. The Perry TS presently require MCC ED-1-B-09 to be energized. This will no longer be necessary since the IE51-F063 valva motor operator was the only load connected to this MCC.

l For these reasons, CEI has concluded that the proposed amendment involves no significant hazards considecetions.

l

USNRC March 4,'1987 PY-CEI/NRR-0592 L Statement of Exigent Circumstances In cur letter of February 24, 1987 (Pl-CEI/NRR-0597L), CEI comm'tted to make proposed changes tn the IE51-F063 velve by the completion of Startup Test Condition 1. By letter dated February 24, 1987, the NRC granted CEI interim relief on RCIC system operability which will expire on March 26, 1987. CEI will.need the changes to the TS proposed in this letter to allow operation to

-continue after March 26, 1987. Since the relief granted by the NRC was only for a 30 day period, there is insufficient time to process this amendment in a normal manner. Therefore, CEI requests that this amendment be processed under exigent circumstances in accordance with 10 CFR 50.91(a)(6).

Until this change is granted, CSI will continue to perform the required surveillances on the DC batteries and power distribution systems, and will perform surveillances to encure the maximum isolation time of the 1E51-F063 valve does not exceed 20 seconds. Thus, the attendant TS changes, to follow, 4

will be consistent with the conservative approach CEI is taking.

Environmental Impact CEI has reviewed the proposed TS changes against the criteria of 10 CFR 51.22 for environmental considerations. As shown above, the proposed change does not involve a significant hazards consideration, nor increase the types and amounts of effluents that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, CEI concludes that the proposed TS changes meet the criteria given in 10 CFR 51.22(c)(9) for a categorical exclusion from the requirement for an Environmental Impact Statement.

Administration

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Pursuant to 10 CFR 170.12, the application fee of $150.00 is enclosed.

l A marked up copy of the TS pages are enclosed. We request this amendment be processed under. exigent circumstances, as described in 10 CFR 50.91(a)(6), and be issued no later than March 26, 1987. Should you have any questions, please feel free to call me.

j Very truly y .rs, f

Murray R. Edelm n l

Senior Vice President Nuclear Group MRE:nje Enclosures

! cc: Jay Silberg, Esq.

Paul Leech K. A. Connaughton USNRC, Region III

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