ML20205D969
| ML20205D969 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/26/1999 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205D973 | List: |
| References | |
| NUDOCS 9904050018 | |
| Download: ML20205D969 (7) | |
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UNITED STATES g
j-NUCLEAR REGULATORY COMMISSION o
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- WASHINGTON, D.C. 20555-0001
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DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY THE' CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 98 License No. NPF-73 1.
The Nuclear Regulatory Commission (the Commission) has found that:
j A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated March 10,1997, as supplemented July 28,1997, September 17,1997,
. April 30,1998, January 29,1999, and February 26,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the I
Act), and the Commission'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 Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment q
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; 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 satisfied.
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9904050018 990326 PDR ADOCK 05000412 p
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.. '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 i
Operating License No. NPF-73 is hereby amended to read as follows:
(2) Technical Specifications -
The Technical Specifications contained in Appendix A, as revised through Amendment No. 98
, 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.
In addition, the license is amended by changes to paragraph 2.C.(11) to the Facility Operating License No. NPF-73 as follows:
-(11) Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No. 98, are hereby incorporated into this license. Duquesne Light Company shall operate the facility in accordance with the Additional Conditions.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Singh S. Bajwa, Director Project Directorate 1-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Att-hment: 1.
Page 1 of Appendix D of License
- 2. Changes to the Technical Specifications Date of issuance: March 26, 1999
- Page 1 of Appendix D is attached, for convenience, for the composite license to reflect this change.
r ATTACHMENTTO LICENSE AMENDMENT NO. 9B FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 1.
Revise Appendix D of the License as follows:
Remove Paae Insert Paae i
1 1
)
2.
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain verticallines indicating the areas of change.
Remove Insert 3/4 4-14 3/4 4-14 1
3/4 4-14a 3/4 4-14a i
8 3/4 4-3 B 3/4 4-3 j
APPENDIX D ADDITIONAL CONDITIONS OPERATING LICENSE NO. NPF-73 Duquesne Light Company, Ohio Edison Company, The Cleveland Electric illuminating Company,'and The Toledo Edison Company shall comply with the following conditions on the schedules noted below:
Amendment Additional Condition implementation Number Date 83 The licensee is authorized to relocate certain This amendment Technical Specification requirements to shall be licensee-controlled documents. lmplementation implemented of this amendment shallinclude the relocation within 60 days -
of these technical specification requirements from April 14, to the appropriate documents, as described in 1997 the licensee's application dated September 9, 1996, and evaluated in the staff's safety evaluation attached to this amendment.
87 The licensee is authorized to relocate certain The amendment Technical specification requirements to shall be licensee-controlled documents, implementation implemented within of this amendment shallinclude the relocation 60 days from of these technical specification requirements December 10, to the appropriate documents, as described in 1997 the licensee's application dated March 14, 1997, as supplemented July 29 and August 13, 1997, and evaluated in the staff's safety evaluation attached to this amendment.
88 The licensee is authorized to relocate certain The amendment i
Technical Specification requirements to shall be licensee-controlled documents. implementation implemented of this amendment shallinclude the relocation within 30 days of these technical specification requirements to from J
the appropriate documents, as described in the January 20,1998 1
licensee's application dated September 11, 1997, and evaluated in the staff's safety evaluation attached to this amendment.
98 The licensee commits to perform visual The amendment acceptance examinations of sleeve welds; post shall be weld heat treatment of sleeve welds; and the implemented within NRC-recommended inspections of repaired 60 days from i
tubes s described in the licensee's application thrch 26,1999 dated March 10,1997, as supplemented July 28,1997, September 17,1997, April 30,1998, and January 29,1999, and evaluated in the staff's safety evaluation attached to this 3
amendment.
NPF-73 i
l SURVEILLANCF REQUIREMENTS (Continued) 3.
A loss-of-coolant acci&.tt requiring actuation of the engineered safeguards, or 4.
A main cteamline or feedwater line break.
l 4.4.5.4 Accentance Criteria a.
As used in this Specification:
1.
Imoerfection means an exception to the dimensions, finish or contour of a
tube or sleeve from that 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.
Deoradation 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 Dearadation 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 pernit the passage of the eddy-current inspection probe shall be deemed a defective tube.
6.
Plucainc or Reoair 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 becabee it may become unserviceable prior to the next inspection.
The plugging or repair limit imperfection depths are specified in percentage of nominal wall thickness as follows:
a.
Original tube wall 40%
b.
ABB Combustion Engineering TIG welded sleeve wall 32%
l c.
Westinghouse laser welded sleeve wall 25%
BFAVER VALLEY - UNIT 2 3/4 4-14 Amendment No. 98 V5?R%
NPF-73 REACTOR COOLANT SYSTEM 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 steamline l
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-band to the top support to the cold leg.
9.
Tube ReDair 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 h' ave been found acceptable:
a)
ABB Combustion Engineering TIG welded
- sleeves, CEN-629-P,. Revision 02 and CEN-629-P Addendum 1.
. erstinghouse laser welded
- sleeves, WCAP-13483, b)
W 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 Reports 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 j
submitted in a Special Report in accordance with 10 CFR 50.4.
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b.
The complete results of the steam generator tube and sleeve iniservice inspection shall be submitted in a Special Report in-accordance with 10 CFR 50.4 within 12 months following the completion of-the inspection.
This Special Report shall include:
1.
H & r.and extent of tubes and sleeves inspected.
BEAVER VALLEY - UNIT 2 3/4 4-14a Amendment No. 98
i
- NPF-73' REACTOR COOLANT' SYSTEM
' BASES L3/4.4.5 STEAM GENERATORS (Continued) decay ' heat removal capabilities for RCS temperatures greater than 350'F if one steam generator becomes inoperable due-to single failure considerations.
Below '350 F, decay heat is removed by the RHR system.
~.The: Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be. maintained.
The program for inservice inspection of steam generator. tubes is; based on a modification of Regulatory Guide 1.83, J
Revision
- 1..
Inservice inspection. of steam generator tubing is j
-essential in order.to maintain surveillance of the conditions-of the J
tubes in f the event that there is evidence of mechanical damage or 1
progressive degradation due to. design, manufacturing
- errors, or inservice conditions.that! lead to corrosion.
' Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be'taken.
The plant is expected to be operated in a manner such that the secondary ; coolant will be maintained within those parameter limits found to result-in. negligible corrosion of the steam generator tubes.
If the secondary' coolant chemistry is not maintained within these parameter limits, localized ' corrosion may likely result in stress corrosion cracking. -
The extent _ of cracking during plant operation
.would be limited by_ the limitation of steam generator tube leakage between Lthe primary-coolant system and the secondary coolant system
.(primary to secondary LEAKAGE 500 gallons per day per steam
=
. generator).
Cracks having a primar'J to secondary LEAKAGE less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents.
Operating plants have demonstrated that primary to secondary _ LEAKAGE of _ 500 gallors per day per steam generator can readily be detected by radiation monitors of steam generator blowdown.
Leakage in excess of this limit will require plant shutdown and ' an unscheduled inspection, during which the leaking tubes L will be -located and plugged or repaired by sleeving.
The technical-. bases for sleeving are described in the approved vendor reports listed in Surveillance Requirement 4.4.5.4.a.9.
Wastage-type defects are unlikely with the all volatile treatment (AVT) of. secondary coolant.
However, even if a defect of similar
. type should develop -in service, it will be found during scheduled
' inservice steam' generator tube examinations.
Plugging or repair will be mquired _ of all. tubes with imperfections exceeding the - plugging or repair limit.
Degraded steam generator tubes may be BEAVER' VALLEY - UNIT-2 B 3/4 4-3 Amendment No.98