ML20245C259
| ML20245C259 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/14/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245C257 | List: |
| References | |
| NUDOCS 8906260108 | |
| Download: ML20245C259 (4) | |
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SAFETY EVALUATION BYJ HE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDPENT NO.
23 TO FACILITY OPEPATING LICENSE NO. NPF-39 PHILADELPHIA ELECTRIC COMPANY LIHERICK GENERATING STATION, UNIT 1 DOCKET NO. 50-352 1
1 1:0 INTRODUCTION By letter dated' January 27, 1989, Philadelphia Electric Company (the licensee) requested an amendmer,t to Facility Operating License No. NPF-39 for the Limerick Generating Station, Unit 1.
The proposed amendment.would change the Unit 1 Technical Specifications (TSs) to reflect the.
completion and tie-in of the Unit 2 Standby Gas Treatment System (SGTS)-
and the Unit 2 Refueling Area Heating, Ventilating and Air Conditioning (HVAC) Sys;.em.. The changes to the TSs allow the inclusion.of Unit 2 equipment that will be relied upon or required to se operable to support the operation of Unit I when Unit 2 is issued an Operating License.
'2.0 DISCUSSION The SGTS.is a redundant safety-related system that is designed to reduce radioactive halogen and particulate concentrations in (1) gases that may be present' in the secondary containment after a Loss-of-Cooling-Accident
-(LC0A), and (2) gases present after a. postulated Fuel Handling Accident in the refueling floor area before the gases are discharged to the environment. The SGTS is a common system that serves both the Unit I and the Unit 2 Reactor Enclosure and the Connon Refueling Area. The SGTS is designed'to draw down and maintain a negative pressure in these areas during a secondary containment isolation. The SGTS also functions to reduce halogen and particulate concentrations purged tiom the primary containment through the drywell' or suppression pool exhaust lines.
The SGTS is designed as a shared system for filtration and treatment of both the Unit I and the Unit 2 Reactor Enclosure atmospheres and the refueling area. When the tie-in of the Unit 2 Reactor Enclosure to the SGTS is complete, that portion of the Unit 2 ductwork will form a part of the secondary containment isolation boundary for the Unit 1 Reactor Enclosure. The Unit 2 Refueling Area HVAC system, as well as the exicting Unit 1 Refueling Area HVAC system, has exhaust duct radiation monitors which provide input to the Refueling Area Secondary Containment Isolation System. An isolation signal from either unit's exhaust duct radiation monitors will cause both the Unit 1 and Unit 2 Refueling Area HVAC systems to isolate. The Unit 2 radiation monitors located in the 1
Refuelirg Area HVAC exhaust duct are not presently connected to the Unit 1 itolation logic. Completion of the tie-in would require the Unit 2 HYAC n
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isolation activation instrumentation, isolation valves, and the exhaust duct radiation monitors to be operable for the appropriate Operational conditions.
I Specifically, the proposed changes are as follows:
a.
Technical Specification Table 3.3.2-1, Table 3.3.2-2, Table 3.3.2-3, and 4.3.2.1-1 would be revised to include the
" Refueling Area Unit 2 Ventilation Exhaust Duct Radiation -
High" radiaticn monitors. The Limiting Conditions for Operation, setpoints, and Surveillance Requirements for these monitors are the same as those for the existing Unit i radiation monitors contained in the Unit 1 Technical l
Specifications. Since the Refueling Area is common to both l
units, operation of either Unit 1 or 2 Refueling Area Ventilation i
System represents a potential exhaust pathway and the associated radiation monitors should be operable. Therefore the Applicability is revised to include the condition "During the operation of the i
associated ventilation exhaust system."
b.
Technical Specification Table 3.6.5.2.2-1 Footnote ** is being deleted and the associated lines will now be required to have operable isolation capability as Unit 2 construction is being completed.
(The footnote now states that the lines are blanked off during Unit 2 construction),
c.
Technical Specification Table 3.6.5.2.1-1 would be revised to include the Unit 2 drywell purge exhaust valves (HV-57-214 and HV-57-215) and suppression purge exhaust valves (HV-57-204 and i
HV-57-212). These valves are required to be operable in order to maintain the Unit 1 Reactor Enclosura secondary containment isolation boundary. Any breech of this isolation boundary to an area outside of the Unit 1 Reactor Enclosure affects the ability of the SGTS to perform its design functions; therefore, these valves are added to the list of Reactor Enclosure Secondary Containment Ventilation System Automatic Isolation Valves, Table 3.6.5.2.1-1.
In addition, since these drywell and suppression pool purge exhaust valves also provide a primary containment function, their dual function, as Reactor Enclosure isolation valves for the other unit will be reflected in Table Notation 33 to Table 3.6.3-1, d.
Technical Specification Table 3.6.5.2.1, Action C, is being revised to include a reference to slide gate dampers. These slide gate dampers can be used to isolate the drywell and/or suppression pool exhaust lines in he event that the exhaust valves are not operable. The incle Mn of the slide gate dampers into Specification 3.6.5.2.
provides manual isolation capability in these lines.
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Minor administrative changes were made to. clarify that the requirements applied to either Unit 1 or Unit 2, and to clarify the title of the ventilation exhaust system. These changes provide no change in technical content of the specifications proposed by the licensee and no reduction in the margin of safety.
3.0 EVALUATION The proposed changes to the TSs add various Unit 2 SGTS and Refueling i
Area llVAC equipment operability requirements and clarifications to reflect the completion and tie-in of Unit 2.
The proposed changes reflect the original two unit design as described in the Final Safety Analysis Report 1
which was previously reviewed and approved by the Nuclear Regulatory Commission in NUREG-0991, " Safety Evaluation Report Related to the Operation of Limerick Generating Station, Unit I and 2" dated August,1983 and supplements thereto.
The proposed changes ensure that the Unit 2 systems and equipment which i
are relied upon or required to be operable to support the operation of 1
Unit I are accounted for in the Unit 1 Limiting Conditions for Operation and Surveillance Requirements. This ensures that the Unit 2 systems and i
equipment required for the operation of Unit 1 perform their intended safety functions as required in the design basis for the Limerick Generating Station. Additionally, the proposed revisions will not affect nor change any plant hardware, plant design or plant system operation from that already described in the Final Safety Analysis Report. For this reason, the SGTS continues to meet the requirements of 10 CFR Part 50, Appendix A General Design Criteria 41, 42, 43, 61 and 64.
Based on our evaluation, the staff has detennined that the proposed changes to the TSs are acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes to surveillance requirements. The stiff 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 coment on such finding. Accordingly, this amendment meets the elig(ibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement nor environmental assessment need be prepared in connection with the issuance of this amendment.
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5.0 CONCLUSION
~ The Commission made a proposed determination that the amendment. involves no significant hazards consideration which was published in the Federal
_ Register (54 FR 9924)lon March 8,.1989 and consulted with the State
'of Pennsylvania. No public comments were received and the State of Pennsylvania did not have any comments.
.The staff has concluded, based on the considerations discussed above, that:
(1) there.is reasonable assurance that the health and safety of the ublic will not be endangered by operation in the proposed manner, and p(2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and.the security nor to the health and safety of the paalic.
Principal Contributor: Dick Clark Dated:
June 14, 1989 I
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