JPN-89-024, Proposed Tech Specs 3.11.A.1 & 3.11.A.3 & Bases 3.11.A, Placing More Restrictive Limiting Conditions for Operations on Main Control Room Emergency Ventilation Sys (JPTS-89-024)
| ML20247H468 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/18/1989 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20247H456 | List: |
| References | |
| JPN-89-024, JPN-89-24, JPTS-89-012, JPTS-89-12, NUDOCS 8905310246 | |
| Download: ML20247H468 (7) | |
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1; ATTACHMENT I TO JPN-89-024 PROPOSED TECilNICAL SPECIFICATION CHANGES REGARDING MAIN CONTROL ROOM EMERGENCY VENTILATION SYSTEM (JPTS-89-012)
.s l-1 New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 8905310246 890518 PDR ADOCK 05000333 P
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L ATTACHMENT II TO JPN-89-024 SAFETY EVALUATION FOR p
PROPOSED TECliNICAL SPECIFICATION CHANGES REGARDING MAIN CONTROL ROOM EMERGENCY VENTILATION SYSTEM i-(JI'I's-89-012)
New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59
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- Attachment II to JPN-89-024 SAFETY EVALUATION -
.f Page 1 of 3 r
1.
DESCRIPTION OF THE PROPOSED CHANGES The proposed change to the James A. FitzPatrick Technical Specifications revises Specifications 3.11.A.1 and 3.11.A.3 on page 238 and the associated Bases on page 243.
Specification 3.11.A.1 - Replace "1 month" with "14 days."
Specification 3.11.A.3 - In two places, replace "7 days" with "3 days."
Bases for 3.11.A -
Replace "the allowable repair time of 1 month is justified, based on the 3 month test interval" with "a repair time of 14 days is allowed because during that time, a redundant 100% capacity train is required to be operable."
IL PURPOSE OF Tile PROPOSED CHANGES in issuing Amendment 114 to the FitzPatrick Technical Specifications (Reference 3), the NRC requested that the Authority propose more restrictive limiting conditions for operations (LCO's) for the Main Control Room Emergency Ventilation System (MCREVS) to be consistent with the LCO's contained in the Standard Technical Specifications. The Authority reviewed the existing specifications in light of their safety significance (Reference 4) and determined that the specifications were appropriate witnout revision.
I The availabi!ity of the MCREVS over the last three calendar years has been 100 percent (i.e. at no time during this period were both trains unavailable). The worst case unavailability of a single train was 0.25 percent due solely to planned maintenance and surveillance testing. These figures demonstrate the high degree of reliability the MCREVS has maintained despite relatively long duration LCO's. Despite this, the Authority offered to sobmit revised LCO's (Reference 5) to reduce the MCREVS allowable outage times to fourteen days with one filter train inoperable, and three days with both trains inoperable.
I' IH.~
IMPACT OF THE PROPOSED CHANGES The impact of reduced allowed outage times (AOT) would be to reduce the length of time the plant can operate with MCREVS equipment out of service. Shorter AOT's generally correlate with greater availability since the equipment must be returned to service in less time. The operating history of the MCREVS demonstrates a high availability with the current AOT's. MCREVS reliability is expected to remain high under the reduced AOT's. If one train of the MCREVS should become inoperable,14 days provides a sufficient time to repair, retest, and restore the equipment to
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operable status. During this time, the redundant 100% capacity train will provide the required
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safety function ifit is needed.
In the highly unlikely event that both trains of MCREVS become inoperable simultaneously, a shorter three day period is allowed to restore at least one train to operability. This time is appropriate considering that the safety function of the MCREVS does not involve accident l
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Attachment II to JPN-89-024
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SAFETY EVALUATION
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Page 2 of 3 prevention or core damage mitigation. Therefore, the allowed out-of-service times for one train and for both trains of MCREVS inoperable are justified.
The NRC has performed a preliminary review of the revised allowable outage times (Reference 6) and has found the concept to be acceptable pending the results of the formal amendment review process. In addition, the NRC has made a proposed determination that this change involves no significant hazards consideration (Reference 7).
IV.
EVALUATION OF SIGNIFICANT IIAZARDS CONSIDERATION Operation of the James A. FitzPatrick Nuclear Power Plant in accordance with the proposed amendment would not involve a significant hazards consideration as stated in 10 CFR 50.92, since it would not:
1.
involve significant increase in the probability or consequences of an accident previously evaluated. The proposed amendment is an administrative change which does not involve changes to plant hardware or procedures. The change merely reduces the length of time the plant is allowed to operate with certain safety related equipment out of service. This change has no impact on plant operations. The change will have no impact on previously evaluated accidents.
2.
create the possibility of a new or different kind of accident from those previously evaluated. The proposed change does not involve plant hardware or procedures, and therefore, cannot initiate an accident of any kind. The change cannot create the possibility of a new or different kind of accident.
i 3.
involve a significant reduction in the margin of safety. The changa reduces the length of time the plant is allowed to operate with certain safety related equipment out of service.
This cannot reduce any margins of safety and instead increases existing safety margins by imposing more restrictive operability requirements.
In the April 6,1983 Federal Register (48FR14870), NRC published examples of license amendments that are not likely to involve a significant hazards consideration. Example (ii) from this Federal Register notice is applicable to these changes and states:
"A change that constitutes an additional limitation, restriction, or control not presently included in the technical specifications: for example, a more stringent surveillance requirement."
V.
IMPLEMENTATION OF TIIE PROPOSED CIIANGE Implementation of the proposed changes will not impact the ALARA or Fire Protection Prop.uns at FitzPatrick, nor will the changes impact the environment.
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' Attachment II to JPN-89-024
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SAFETY EVALUATION Page 3 of 3 b
L VI.
CONCLUSION The change, as proposed, does not constitute an unreviewed safety question as defined in 10 CFR 50.59. That is, it:
a.
will not change the probability nor the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the Safety Analysis Report; b.
will not increase the possibility of an accident or malfunction of a different type from any previously evaluated in the Safety Analysis Report;.
will not reduce the margin of safety as defined in the basis for any technical specification; c.
d.
involves no significant hazards consideration, as defined in 10 CFR 50.92.
Vll.
REFERENCES 1.
James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report, Section 9.9.3.11 and Figure 9.9-5.
2.
James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report (SER), dated November 20,1972 and Supplements.
3.
NRC letter, H. Abelson to J. C. Brons dated February 17, 1988, Amendment 114 to Technical Specifications.
4.
NYPA letter, J. C. Brons to NRC dated December 19,1986 (JPN-86-59), NUREG-0737 Item III.D.3.4 " Control Room Habitability Requirements."
k 5.
NYPA letter, J. C. Brons to NRC dated May 13,1988 (JPN-88-019), Main Control i
Room Emergency Ventilation System Technical Specifications.
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6.
NRC letter, D. E. LaBarge to J. C. Brons dated March 30, 1989, Control Room Habitability - Proposed LCO.
7.
NRC letter, D. E. LaBarge to J. C. Brons dated April 25,1989, Notice of Consideration ofIssuance of Amendment.
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