ML20091M777
| ML20091M777 | |
| Person / Time | |
|---|---|
| Site: | Salem, Diablo Canyon  |
| Issue date: | 08/24/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Philadelphia Electric Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20091M781 | List: |
| References | |
| DPR-70-A-174, DPR-75-A-155 NUDOCS 9508300294 | |
| Download: ML20091M777 (9) | |
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PUBLIC SERVICE' ELECTRIC & GAS COMPANY
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DOCKET NO. 50-212 j
-SALEM NUCLEAR GENERATING STATION.-UNIT NO. l' AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.174 License No. DrR-70 1.
The Nuclear Regulatory Commission (the. Commission or the NRC) has found that:
1 A.
The application for amendment filed by the Public Service. Electric &J
- l Gas Company, Philadelphia Electric Company, Delmarva Power and Light.
Company and Atlantic City Electric Company (the licensees) dated.
December 23, 1994, complies with the. standards'andLrequirements of the:
Atomic Energy Act of 1954,'as amended (the Act),7and the Commission's.
m rules and regulationsLset forth.in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions ofcthe Act,'and the rules and regulations of.the 4
i' Commission-C.
There is reasonable assurance:
(1) that.the activities' authorized by;
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this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in:10 CFR.
' Chapter I; D. tThe issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the:public;;and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of' the Commission's regulations and all applicable requirements have been.
i satisfied.
2.
Accordingly, the ' license is amended by changes 'to the Techn'ical Specifica-l tions as indicated in the attachment-to this license amendment, and-paragraph 2.C.(2) of Facility Operating License No. DPR-70 is.hereby e
amended to read.as follows:
b 9508300294 950824 "
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(2) Technical Specifications and Enyironmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.174, are hereby incorporated in the
' license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be s
implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMISSION f
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IJo F. Stolz, Directo l oject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 24, 1995
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- ATTACHMENT TO LICENSE ' AMENDMENT NO.174 FACILITY OPERATING LICENSE NO. OPR-70 DOCKET NO. '50- 272
. Revise Appendix A as follows:
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V EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) p c.
By a visual l inspection'which verifies that'no' loose debris (rags,.
trash, - clothing, etc.) is 'present in the containment which could be transported to.the containment sump and cause restriction of the pump-suctions during LOCA conditions. This' visual inspection.shall be performed:-
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For all accessible areas of the containment prior'to j
establishing CONTAINMENT INTEGRITY, and f
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At least once daily (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> consecutive period) the areas affected within containment by containment entry and during the final entry when CONTAINMENT INTEGRITY is established, d.
At least once per 18 months by:
1.
A visual inspection of the containment sump and verifying that' the subsystem suction inlets are not restricted by' debris and l
'that the sump components (trash racks, screens, etc.) show no l
evidence of structural distress or corrosion.
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At least once per 18 months, during shutdown, by:
E 1.
Verifying that each automatic valve in the flow path actuates to I
its correct position on a safe'ty injection test signal.
2.
Verifying that each of the following pumps start automatically upon receipt of a safety injection test signal:
a)
Centrifugal charging pump b)
Safety injection pump c)
Residual heat removal pump i>
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l SALEM - UNIT 1 3/4 5-5 Amendment No.174 l
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j-NUCLEAR REGULATORY COMMISSION N
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARYA.00WER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 4
SALEM NUCLEAR GENERATING STATION. UNIT NO. 2-AMENDMENT TO FACILITY OPERATING LICENSE Amendment _ No.155 License No. DPR-75 i
1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found
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1 that:
A.
The application for amendment filed by the Public Service Electric' &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company. (the licensees) dated December 23, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth.in 10 CFR Chapter I;.
8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized ~by:.
this amendment can be conducted without endangering the health and safety of the public, and (ii) that'such activities will be conducted in compliance with the Commission's regulations set forthin'10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and.
j E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been i
satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby-amended to read as follows:
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(2). Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.155., are hereby. incorporated in the license ~. The. licensee shall operate the facility in accordance with the Technical Specifications.
-3.
This license amendment is effective as of its date of. issuance, to be implemented within 60 days.
FOR THE NUCLEAR' REGULATORY COMISSION r
Jo i F. Stolz, Director P ject Directorate I-2 ivision of Reactor. Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of. Issuance: August 24, 1995 i
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ATTACHMENT TO LICENSE AMENDMENT NO.159 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 l
Revise Appendix A as follows:
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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
By a visual inspection which verifies that no loose debris (rags, tresh, clothing, etc.) is present-in the containment which could be L
. transported.to the containment sump and cause restriction of the pump
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suctions during LOCA conditions. This visual inspection shall be.
performed:-
b.-
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'For all accessible areas of the containment prior to 1.
establishing CONTAINMENT INTEGRITY, and l
2.
At 'least once daily '(24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> consecutive period) the areas affected within containment by containment entry and during the final entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
1.
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks,. screens, etc. ) 'show no i
evidence of structural distress or corrosion.
e.
At least once per 18 months, during shutdown, by:
1.
Verifying that each automatic valve in the flow path actuates to its correct position;on a safety injection test signal.
2.
Verifying that each of the following pumps start automatically-upon receipt of a safety injection test signal:
a)
Centrifugal charging pump-b)
Safety injection pump c)
Residual heat removal. pump' i
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i SALEM - UNIT 2 3/4 5-5 Amendment No. 155 l
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g WASHINGTON, D.C. 20006-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION J
RELATED TO AMENDMENT NOS.174~ - AND 155 TO FACILITY OPERATING LICENSE NOS. DPR-70'AND DPR-75.
PUBLIC SERVICE ELECTRIC & GAS COMPANY m
PHILADELPHIA ELECTRIC COMPANY.
DELMARVA POWER AND LIGHT COMPANY =
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.s ATLANTIC CITY ELECTRIC COMPANY-SALEM NUCLEAR GENERATING STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311
1.0 INTRODUCTION
By letter dated December 23, 1994, the Public Service Electric & Gas Company-
.(the licensee) submitted a request for changes to the Salen Nuclear Generating l
e Station, Unit Nos. I and 2, Technical Specifications (TS)..The. requested changes would revise the surveillance requirement to perform a visual
-inspection of containment areas affected by containment entry when containment integrity is established. The changes are consistent with Item 7.5 of.~ Generic Letter (GL) 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation."
2.0 EVALUATION The current Technical Specification 4.5.2.c.2 requires 'that ' containment areas affected by entry be visually inspected at the completion of each entry when containment integrity is established.
Item 7.5 of GL 93-05 recommends that visual inspection of the containment be performed once daily if the containment has been entered that day, and during the final entry to ensure that there is no loose debris that would clog the sump. This recommendation reduces the exposure to personnel performing the inspection when multiple entries are required into containment. The licensee maintains a record of containment areas visited and, in the event of multiple containment entries, this record would facilitate visual inspection during the final entry.
v The licensee has reviewed the Salem 1 and Salem 2 operating experience for the past two. years and there is no indication of any problems involving loose debris left inside containment when containment integrity is established.
The proposed changes are consistent with GL 93-05 and'are compatible with j
plant operating experience. The staff concludes that these changes do not adversely. affect plant safety and will result in a net benefit to the safe operation of the facility, and, therefore, are acceptable.
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3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New Jersey State official was notified of the proposed issuance of the amendments. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change surveillance requirements. The NRC 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 Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (60 FR 6308). 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 be prepared in connection with the issuance of the amendments.
5.0 CONCLUSION
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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
I.
01shan Date: August 24, 1995
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