ML20217K811
| ML20217K811 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/19/1998 |
| 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 | |
| ML20217K816 | List: |
| References | |
| DPR-75-A-190 NUDOCS 9805040144 | |
| Download: ML20217K811 (5) | |
Text
."
- p.i rngk p
UNITED STATES j
NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 308564m01
%,...../
PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.190 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found 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 October 29,1997, as suppicmented on January 27,1998, 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 ChapterI; B.
The facility will operate in conformity with the application, the provisions of the Act, snd 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 forth in 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 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 satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications 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:
9805040144 900319 PDR AT 1 05000311 P
- (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.190, 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 80 days of the date ofissuance.
FOR THE NUCLEAR REGULATORY COMMISSION J n F. Stolz, Director roject Directorate 1-2 Division of Reactor Projects - t/Il Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: March 19, 1998 P
l ATTACHMENT TO LICENSE AMENDMENT NO.1on FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 l
Revise Appendix A as follows:
Remove Paoes insert Paoes l
l 3/4 4-11 3/4 4-11 l
3/4 4-15a 3/4 4-15a j
4 l
l e
R REACTOR co0LANT SYSTEM SURVEII.!ANCE REQUIRIMENTS (Continued) 4.4.5.3 Inspection Frequencies - The above required inservice inspections of steam generator tubes shall be perfonned at the following frequencies; The first inservice inspection shall be performed after 5 a.
Effective Full Power Months but within 24 calendar amonths of initial criticality. Subsequent inservloe inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection. For Fuel cycle 10 only, the inspection interval shall begin at criticality.
If two consecutive inspections following service under AVT conditions, not including the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a==4==
of once per 40 months.
b.
If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40 month intervals fall in Category c-3, the inspection frequency shall be increased to at least once per 20 months.
The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 4.4.5.3.a; the interval may then be extended to a
w4=
of once per 40 months.
Additional, unscheduled inservice inspections shall be c.
performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:
1.
Primary-to-secondary tubes leaks (not including leaks originating from tube-to-tube sheet welds) in emoess of the limits of Specification 3.4.7.2.
2.
A seismic occurrence greater than the operating Basis Earthquake.
3.
A loss-of-coolant accident requiring actuation of the engineered safeguards.
4.
A main steam line or feedwater line break.
SALEN - UNIT 2 3/4 4-11 Amendment No.190
~
o STEAM GENERATOR SURVEILIANCE PERIOD LMNNNT FOR BALEM NUCLEAR GENERATING STATION UNIT 2 FUEL CYCLE 2R10 i
Salesa Unit 2 was removed fresa seavice in June of 1995 for a ocaprehensive review of plant methods and policies.
In May of 1996, a 1009 bobbin coil and additional specialty examinations inspection of the salem Unit 2 steam generators was ocapleted. Permission'to restart Unit 2 was given by the NRC in June of 1997 and Mode 2 first achieved on August 17, 1997. After the May 1996 inspection, Unit 2 steam generators were placed in lay-up, using EPRI guidelines, to protect the steam generators from deterioration. PSE&G has a high level of confidence that corrosion growth and new corrosion initiation during the time of lay-up were essentially halted, and the condition of the i
steam generators has not changed since the May 1996 inspection.
Thus, in order to avoid an unnecessary mid-cycle steam generator inspection forced outage, Technical specification 3/4.4.6 is hereby amended such that the next steam generator inspection will be required to be performed within 24 months of Mode 2(this would be by August 17, 1999), or during the next scheduled refueling outage, whichever is first for Unit 2 fuel cycle 10.
Subsequent steam generator inspections will be scheduled accordingly.
SALEM - UNIT 2 3/4 4-15a Ar.mndswent Fo. 63,190
~