ML20071K874
| ML20071K874 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/25/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071K864 | List: |
| References | |
| NUDOCS 9408020064 | |
| Download: ML20071K874 (3) | |
Text
,M.are UNITED STATES yw 5
E NUCLEAR R5GULATORY COMMISSION E
f WASHINGTON, D.C. 206two001
,o SAFETY EVALUATION BY THE OFFICE OF NUCLEA9_ REACTOR REGULATION RELATED TO AMENDMENT NO.190 TO FACILITY OPERATING LICENSE NO. OPR-50 METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION THREE MILE ISLAND NUCLEAR STATION. UNIT NO. I DOCKET NO. 50-289
1.0 INTRODUCTION
The amendment revises the TMI-1 Technical Specifications (TS) to specify an allowable outage time for the Emergency Feedwater (EFW) Pumps during surveillance activities.
It also changes the requirement to test redundant components for operability to a requirement to ensure operability based on verification of completion of appropriate surveillance activities. According I
to the licensee, these changes, in conjunction with TSCRs 228 and 230, are being made to permit full implementation of the guidance provided to licensees regarding OPERABILITY determinations in Generic Letter (GL) 91-18.
Guidance from NUREG-1366, " Improvements to Technical Specification Surveillance Requirements," and NUREG-1430, " Standard Technical Specifications for Babcock
& Wilcox Plants," was used by the licensee to develop these proposed changes.
2.0 EVALUATION (1) Page 3-22 TS 3.3.1.3.b is modified to correct a typing error made in previous TSCR No.
i 222. The "i" sign between 8 ft. and 6 inches is added.
This change is considered to be administrative and is acceptable.
TS 3.3.~2 is modified to clarify that maintenance "or testing" shall be allowed during reactor operation on the components associated with emergency core cooling, reactor building emergency core cooling, and the reactor building spray systems.
Since the associated components of a train are inoperable during maintenance or surveillance testing and the redundant trains have no change in its safety function in either case, the change is considered acceptable.
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9400020064 940725 PDR ADOCK 05000289 P
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, (2) Page 3-25 TS 3.4.1.1(2) is modified to provide a specified allowable outage time for the EFW pumps during surveillance testing.
The 8 extra hours are requested to perform required surveillance testing.
During a quarterly Heat Sink Protection System (HSPS) Train Actuation Logic Testing, one HSPS train is tested at a time. An HSPS train involves one EFW flow path and one motor-driven EFW pump (EF-P-2A or EF-P-28) and the turbine-driven 1:FW pump (EF-P-1),
which is common to both trains. During the testing, one flow path is made i
inoperable and both EFW pumps associated with that train are made inoperable.
Since the licensee provides a required local operator action to return the turbine-driven EFW pump to service in a prompt manner and the motor-driven EFW pumps can be started very quickly using the control switches, the NOTE that allows the EFW pumps to be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when performing surveillance testing is considered reasonable. Therefore, the staff finds the change to be acceptable.
(3) Page 3-26b The last paragraph of the bases for TS 3.4 on this page was inadvertent 1y' i
changed during the processing of Amendment 133. The first sentence of the paragraph is being added to restore its original wording made in Amendment 124.
This change is considered to be administrative and is acceptable, j
(4) Page 3-41 TS 3.6.6 is modified to change the requirement to test a redundant reactor i
building (RB) isolation valve for OPERABILITY following a determination that the other valve in the line is inoperable.
Instead of testing the redundant i
valve to verify 0PERABILITY, it is verified to be OPERABLE by ensuring the appropriate surveillance is current.
The staff agrees that verification of operability of the redundant valve by verifyina that the required surveillance testing is current is an acceptable, and perhaps even preferable, alternative to testina the valve.
GL 93-05 allowed several line item improvements to TSs as justified in NUREG-1366.
Section 10.1 to GL 93-05, Enclosure.1 approved removal of TSs requiring operation of redundant systems or components in the i
case of an inoperable system or component on a generic basis.
This concept was also approved in NUREG-1430 (September 1992). Therefore, the staff finds i
this change to be acceptable.
(5)_Page 3-61 TS 3.15.1.3 is modified to change the requirement to test the redundant control room air treatment system when the other system is made or found to be inoperable.
Instead of testing the redundant valve to verify OPERABILITY, it is verified to be OPERABLE by ensuring the appropriate surveillance is current. GL 93-05 allowed several line item improvements to TSs as justified in NUREG-1366.
Section 10.1 to GL 93-05,. Enclosure 1 approved removal of TSs requiring operation of redundant systems or components in the case of an inoperable system or component on a generic basis.
This concept was also
,.I
j o approved in NUREG-1430 (September 1992). Therefore, the staff finds this change to be acceptable.
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3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts or types of 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 the amendment involves no significant hazards consideration, and there has been no public comment on such finding (59 FR 17601). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 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 the amendment.
5.0 ONCLUSION The Commission 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, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
C. Chung, R. Hernan Date: July 25, 1994 t
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