ML20057A158
| ML20057A158 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/30/1993 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057A159 | List: |
| References | |
| NFP-73-A-056, NFP-73-A-56, NUDOCS 9309130125 | |
| Download: ML20057A158 (10) | |
Text
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UNITED STATES if <
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NUCLEAR REGULATORY COMMISSION j
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DUQUESNE LIGHT COMPANY 1
OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 1
BEAVER VALLEY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment in.176 License No. DPR-66 j
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated December 30, 1992, as supplemented March 12 and June 8,1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; 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 i
51 of the Comission's regulations and all applicable requirements have been satisfied.
9309130125 930830 PDR ADOCK 05000334 P
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. l 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-66 is hereby amended to read as follows-(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.176, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the i
Technical Specifications.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
I FOR THE NUCLEAR REGULATORY COMMISSION i
Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i
Attachment:
l Changes to the Technical Specifications Date of Issuance:
August 30, 1993 j
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ATTACHMENT TO LICENSE AMENDMENT NO.176 l
FACILITY OPERATING LICENSE NO. DPR-6E DOCKET NO. 50-334 Replace the following pages of Appendix A Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment i
number and contain vertical lines indicating the areas of change.
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Remove Insert 3/4 4-10a 3/4 4-10a 3/4 4-10b 3/4 4-10b l
4*
5 DPR-66 REACTOR COOLANT SYSTEM i
j SURVEILLANCE REQUIREMENTS (Continued)
I l
3.
A loss-of-coolant accident requiring actuation of the i
engineered safeguards, or
)
4.
A main steam line or feedwater line break.
4.4.5.4 Acceotance Criteria i
j a.
As used in this Specification:
i j
1.
Imoerfection means an exception to the dimensions, finish or contour of a tube or sleeve from that I
required by fabrication drawings or specifications.
Eddy-current testing indications below 20 percent of the nominal tube wall thickness, if detectable, may be considered as imperfections.
2.
Dearadation means a service-induced cracking,
wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve.
3.
Deoraded Tube means a tube or sleeve containing imperfections greater than or equal to 20 percent of the nominal wall thickness caused by degradation.
4.
Percent Deoradation means the percentage of the tube or sleeve wall thickness affected or removed by degradation.
5.
Defect means an imperfection of such severity that it exceeds the plugging or repair limit.
A tube containing a defect is defective. Any tube which does not permit the passage of the eddy-current inspection probe shall be deemed a defective tube.
6.
Pluccina or Recair Limit means the imperfection depth at or beyond which the tube shall be removed from service by plugging or repaired by sleeving in the affected area because it may become unserviceable prior to the next inspection.
The plugging or repair limit imperfection depths are specified in percentage j
of nominal wall thickness as follows:
i a.
Original tube wall 40%
b.
Babcock & Wilcox kinetic welded sleeve wall 40%
c.
Westinghouse laser welded sleeve wall 25%i BEAVER VALLEY - UNIT 1 3/4 4-10a Amendment No.176
l i
l DPR-66 REACTOR COOLANT SYSTEM i
SURVEILLANCE REQUIREMENTS (Continued) 7.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.
8.
Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support to the cold leg.
9.
Tube Recair refers to sleeving which is used to j
maintain a tube in-service or return a tube to service. This includes the removal of plugs that were installed as a corrective or preventive measure.
The following sleeve designs have been found acceptable:
a)
Babcock Wilcox kinetic welded
" tooling" and installation process parameter changes.
b)
Westinghouse laser welded sleeves, WCAP-13483, Revision 1.
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the plugging or repair limit) required by Table 4.4-2.
l 4.4.5.5 Reoorts 1
a.
Within 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged or repaired in each steam generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2.
j b.
The complete results of the steam generator tube and sleeve inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection. This Special Report shall include:
1.
Number and extent of tubes and sleeves inspected.
2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
3.
Identification of tubes plugged or repaired.
BEAVER VALLEY - UNIT 1 3/4 4-10b Amendment No.176
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D C. 20555-0001 i
DOOVESNE LIGHT COMPANY OHIO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY 3
DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 56 License No. NPF-73 l
1.
The Nuclear P,egulatory Comission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated December 30, 1992, as supplemented March 12 and June 8, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
j
. 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. NPF-73 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as ievised through Amendment No. 56, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLCO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 30, 1993
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ATTACHMENT TO LICENSE AMENDMENT NO.56 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amer.dment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 4-14 3/4 4-14 3/4 4-14a 3/4 4-14a i
l i
)
4 NPF-73 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) i 3.
A loss-of-coolant accident requiring actuation of the engineered safeguards, or 1
4.
A main steam line or feedwater line break.
4.4.5.4 Acceotance Criteria a.
As used in this Specification:
1.
Imperfection means an exception to the dimensions, finish or contour of a tube or sleeve from that required by fabrication drawings or specifications.
F.ddy-current testing indications below 20 percent of the nominal tube wall thickness, if detectable, may be considered as imperfections.
2.
Decradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve.
3.
Decraded Tube means a
tube or sleeve containing imperfections greater than or equal to 20 percent of the nominal wall thickness caused by degradation.
4.
Percent Decradation means the percentage of the tube or sleeve wall thickness affected or removed by degradation.
5.
Defect means an imperfection of such severity that it exceeds the plugging or repair limit.
A tube containing a defect is defective.
Any tube which does not permit the passage of the eddy-current inspection probe shall be deemed a defective tube.
6.
Pluccina or Repair Limit means the imperfection depth at or beyond which the tube shall be removed from service by plugging or repaired by sleeving in the affected area because it may become unserviceable prior to the next inspection.
The plugging or repair limit imperfection depths are specified in percentage of nominal vall thickness as follows:
a.
Original tube wall 40%
b.
Babcock & Wilcox kinetic welded sleeve wall 40%
c.
Westinghouse laser welded sleeve wall 25% l BEAVER VALLEY - UNIT 2 3/4 4-14 Amendment No.56
e NPF-73 REACTOR COOLANT SYSTEM j
SURVEILLANCE REQUIREMENTS (Continued) 7.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis e
Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.
8.
Tube Insoection means an inspection of the steam 4
generator tube from the point of entry (hot leg side) completely around the U-bend to the top support to the cold leg.
S.
Tube Renair refers to sleeving which is used to maintain a tube in-service or return a tube to service.
This includes the removal of plugs that were installed as a corrective or preventive measure.
The following sleeve designs have been found acceptable:
a)
Babcock Wilcox kinetic welded
" tooling" and installation process parameter changes.
b)
Westinghouse laser welded sleeves, WCAP-13483, Revision 1.
]
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the plugging or repair limit) required by Table 4.4-2.
4.4.5.5 Reoorts a
Within 15 days following the completion of each inservice a.
inspection of steam generator tubes, the number of tubes plugged or repaired in each steam generator shall be report d to the Commission in a Special Report pursuant to Specification 6.9.2.
b.
The complete results of the steam generator tube and sleeve inservice inspection shall be submitted to the Commis.sion in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection.
This Special Report shall include:
1.
Number and extent of tubes and sleeves inspectec'.
2.
Location and percent of vall-thickness penetration for each indication of an imperfection.
3.
Identification of tubes plugged or repaired.
BEAVER VALLEY - UNIT 2 3/4 4-14a Amendment NoS6
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