ML17304A323
| ML17304A323 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/29/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17304A322 | List: |
| References | |
| NUDOCS 8808090153 | |
| Download: ML17304A323 (6) | |
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UNITEDSTATES NUCL'EAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMEHDMEHT NO. 35 TO FACILITY OPERATING LICENSE NO.
NPF-41 AMENDMENT NO. 22 TO FACILITY OPERATING LICENSE NO. NPF-51 AND AMENDMENT NO.
11 TO.FACILITY OPERATING LICENSE NO. NPF-74 ARIZONA PUBLIC SERVICE COMPANY ET AL.
PALO VERDE NUCLEAR GENERATING STATION UNIT NOS.
1 2 AND 3 DOCKET NOS.
STH 50-528 STN 50-529 AHD STN 50-530 1.0
2.0 INTRODUCTION
By letter dated May 9, 1988, the Arizona Public Service Company (APS) on behalf of itself, the Salt River Project Agricultural Improvement and Power District, Southern California Edison
- Company, El Paso Electric
- Company, Pub'Iic Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority (licensees),
requested a change to the Technical Specifications for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Appendix A to Facility Operating License Hos.
NPF-41, NPF-51 and NPF-74, respectively).
The proposed change would revise Technical Specification Table 3.6-1 to reduce the maximum actuation time of the containment isolation valves which isolate the containment air radioactivity monitor from 12 seconds to 1
second.
EVALUATION Technical Specification Table 3.6-1 lists containment isolation valves and their maximum actuation times.
The operability of the containment automatic isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.
Containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
The valves affected by this change, the isolation valves for the containment air radioactivity monitor, have actual actuation times of less than 1 second.
By allowing 12 seconds for valve closure the containment air radioactivity monitor could possibly be subjected to pressures in excess of its 10 psi design limit.
FSAR Figure 6.2.1-2, displays containment pressure and temperature response to a double-ended discharge leg slot break, and shows that pressures in excess of 40 psig are possible within 12 seconds of such an event.
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The proposed amendments would reduce the allowable actuation times for these valves to I second, thereby preserving containment integrity by reducing the possibility of damage to the radiation monitor.
This will ensure that the release of radioactive material from the containment atmosphere during accident conditions will be restricted to those leakage paths and associated leak rates assumed in the safety analyses, thereby limiting the site boundary radiation doses to within the 10 CFR Part 100 limits.
3.0 On the basis of the above evaluation, the staff concludes that the proposed change to Technical Specification Table 3.6-1 is acceptable.
CONTACT WITH STATE OFFICIAL 4.0 The Arizona Radiation Regulatory Agency was advised of the proposed determination of no significant hazards consideration with regard to this change.
No comments were received.
ENVIRONMENTAL CONSIDERATIONS 5.0 The amendments involve changes in the use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendments involve 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 Conmission has previously issued a proposed finding that the amendments involve no significant hazards consideration and there has been no public comment on such finding.
Accordingly, the amendments meet 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 to be prepared in connection with the issuance of these amendments.
CONCLUSION The staff has concluded, based on the considerations discussed
- above, that (I) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manneI, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of these amendments will not be inimical to the co@non defense and security or to the health and safety of the public.
We therefore, conclude that the proposed change is acceptable.
Principal Contributor:
M. Davis Dated:
July 29<
1988
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FIGURE 3.1-1 ALL(NABLEHZC HODES 1 ND 2 PALO VERDE UNIT 2 CYCLE 2 ALLO@ABLE MTC iIOO%.0.0) m CD m
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20 40 60 CORE POWER LEVEL,X OF RATED THERNL POWER Ioo
MINIMUMTEMPERATURE FOR CRITICALITY LIMITING CONDITION FOR OPERATION 3.1.1.4 The Reactor Coolant Systew lowest operating loop teaperature (T
ld) shall be greater'han; or equal to 5524F.
APPLICABILITY:
MODES 1 and 28~.
ACTION:
Nth a Reactor Coolant Systew operatfng loop temperature (T
ld) less than 552 F, restore T
ld to within fts If@it within 15 afnutes or be fn HOT STANDBY within the next 15 efnutes.
SURVEILLANCE RE UIREMENTS 4.1.1.4 The Reactor Coolant Systea tewperature (T
ld) shall be deterafned to be greater than or equal to 5524F:
a.
Nthfn 15 efnutes prior to achfevfng reactor crftfcalfty, and b.
At least once per 30 minutes when the reactor fs critical and the Reactor Coolant Systea T
ld fs less than 557 F.
Arith K << greater than ot equal to 1.0.
eff "See Special Test Exceptfon 3.10.5.
PALO VERDE - UNIT 2 3/4 1-6