ML20112J566
| ML20112J566 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/11/1996 |
| From: | Rinaldi F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20112J559 | List: |
| References | |
| NUDOCS 9606200290 | |
| Download: ML20112J566 (2) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NCS. 117 AND 79 TO FACILITY OPERATING LICENSE NOS. NPF-39 AND NPF-85 PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION. UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353
1.0 INTRODUCTION
By letter dated April 25, 1996, the Philadelphia Electric Company (the licensee) submitted a request for changes to the Limerick Generating Station (LGS), Units 1 and 2, Technical Specifications (TSs).
The requested changes would relocate the TS Traversing In-Core Probe (TIP) System Limiting Condition for Operation (LCO) 3/4.3.7.7 and its Bases 3/4.3.7.7, to the LGS Technical Requirements Manual (TRM), and modify Note (f) of TS Table 4.3.1.1-1, " Reactor Protection System Instrumentation Surveillance Requirements" to remove its reference to the TIP system, in accordance with the guidelines contained in i
the Improved Standard Technical Specifications, General Electric Plants BWR/4 (NUREG-1433), issued September 28, 1992.
2.0 EVALUATION The licensee has requested to delete the TIP system requirements, and LCO for TS Sections 3/4.3.7.7 and related Bases, and relocate them in their entirety l
to the LGS's TRM in accordance with NUREG-1433.
In addition, the licensee has requested to modify Note (f) to TS Table 4.3.1.1-1 to delete reference to the TIP system.
The licensee has indicated that future changes of these requirements will be evaluated in accordance with the provisions of 10 CFR 50.59.
Further, the licensee has indicated that, as stated in the Updated Final Safety Analysis Report (UFSAR) Section 7.7.1.6.3, the TIP system is an operational system which has no safety function. The TIP system allows i
calibration of the Local Power Range Monitor, but has no safety setpoints.
Other TIP TS requirements would be unaffected by these changes.
The staff has issued guidance in NUREG-1433 for relocating TS requirements.
NRC's letter to the BWR Owners Group, dated May 9, 1988, stated that the TIP LC0 may be relocated.
Further, NUREG-1433 allows for line item improvements, and states the criteria for the removal of LCOs from the TS when they are to be relocated to a licensee's controlled document like the TRM.
9606200290 960611 DR ADOCK 050003 2
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The licensee has addressed the criteria contained in 10 CFR 50.36 for removal i
j and relocation of TS requirements to a licensee's controlled document, Specifically, the LGS's TIP. system is not:
- 1) used to prevent degradation of tie reactor coolant boundary, 2)'part of a Design Basis Accident or a j
transient analysis that is based on the integrity of the fission product l
barrier, 3) a portion of the primary success path of a safety sequence.
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analysis, or 4) significant to public health and safety.
i The staff concurs with the licensee's determinations, and finds the proposed deletion and relocation of the above stated requirements 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 amendments.
The State official'had no comments.
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4.0 ENVIRONMENTAL CONSIDERATION
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The amendments change a requirement with respect to installation or use of a i
facility component located within the restricted area as defined in 10 CFR Part 20 and change the surveillance requirements.
The NRC staff has 1
determined that the amendments involve no significant increase in the amounts, i
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 the amendments involve no significant hazards e-i-
consideration, and there has been no public comment on such finding (61 FR 20840). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR i
51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 CONCll5103 l
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the j-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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributo'r:
F. Rinaldi t.
'Date:
June 11, 1996 l
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