ML20196H400
| ML20196H400 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/23/1997 |
| From: | Brinkman D NRC (Affiliation Not Assigned) |
| To: | Cross J DUQUESNE LIGHT CO. |
| References | |
| TAC-M98253, TAC-M98254, NUDOCS 9707250137 | |
| Download: ML20196H400 (7) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20ss54001 o
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July 23, 1997 p ry h
Mr. J. E. Cross President - Generation Group Duquesne Light Company Post Office Box 4 Shippingport. PA 15077
SUBJECT:
. REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING REVIEW 0F BEAVEP, VALLEY POWER STATION (BVPS) UNIT NOS 1 AND 2. SECOND AND THIRD 10-YEAR INTERVAL INSERVICE INSPECTION (ISI) PROGRAM RELIEF REQUESTS (TAC NOS. M98253 and M98254)
Dear Mr. Cross:
By letter dated March 25, 1997 Duquesne Light Company (DLC) submitted relief Programs. pplicable to Unit No.1 and Unit No. 2 second and third Ten-Year ISI requests a The current Unit 1 interval ends on Se)tember 20, 1997, and the Unit 2 interval ends on November 16. 1997.
Each Jnit's ISI Program is based on the 1983 Edition through the Summer 1983 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code.Section XI. The next ISI interval will be based on the 1989 Edition of the ASME Section XI Code.
The NRC staff, with assistance from its contractor. Idaho National Engineering and Environmental Laboratory (INEEL). is reviewing and evaluating the second 10-year interval inservice inspection program plan requests for relief from the ASME B&PV Code.Section XI requirements for BVPS Unit Nos.1 and 2.
The staff has determined that additional information is required from DLC to complete the review. The required additional information is identified in the enclosed RAI.
DLC is requested to provide the additional information within 60 days of receipt of this letter, so that the NRC staff may complete the review within a timely manner.
In order to ex>edite the review process, please send a copy of the RAI response to the 4RC's contractor. INEEL at the following address:
Mr. Michael T. Anderson INEEL Research Center 2151 North Boulevard i
P.O. Box 1625 f
pl s Idaho Falls. Idaho 83415-2209 1
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J. Cross July 23, 1997 Should you have any questions on this matter, please contact me-at (301)415-1409.
Sincerely, mv Donald S. Brinkman. Senior Project Manager l
Project Directorate I-2 l
Division of Reactor Projects - I/II-
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Office of Nuclear. Reactor Regulation Docket Nos. 50-334/412
Enclosure:
RAI cc w/ encl: See next page I
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1-J. Cross July 23, 1997 i
I Should you have any' questions on this matter, please contact me at (301)415-1409.
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Sincerely, (Original signed by) i Donald S. Brinkman. Senior Project Manager -
Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation -
Docket Nos. 50-334/412
Enclosure:
RAI i
cc w/ encl:
See next page
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J. E. Cross Beaver Valley Power Station Duquesne Light Company Units 1 & 2 cc:
Jay E. Silberg, Esquire Bureau of Radiation Protection Shaw, Pittman, Potts & Trowbridge -
Pennsylvania Department of 2300 N Street, NW.
Environmental Resources
- Washington, DC 20037 ATTN:
Michael P. Murphy Post Office Box 2063 Director-Safety and Licensing Harrisburg, PA 17120 Department (BV-A)
Duquesne Light Company Mayor of the Borrough of Beaser Valley Power Station Shippingport PO Box 4 Post Office Box 3 Shippingport, PA 15077 Shippingport, PA 15077 Ocenissioner Roy M. Smith Regional Administrator, Region I West Virginia Department of Labor U.S. Nuclear Regulatory Commission Building 3. Room 319 475 Allendale Road Capitol Complex King of Prussia, PA 19406 Charleston, WVA 25305 Resident Inspector Director, Utilities Department U.S. Nuclear Regulatory Commission Public Utilities Commission Post Office Box 298 180 East Broad Street Shippingport, PA 15077 Columbus, OH 43266-0573 Director.-Pennsylvania Emergency Duquesne Light Company Management Agency Beaver Valley Power Station Post Office Box 3321 PO Box 4 Harrisburg, PA 17105-3321 Shippingport, PA 15077 ATTN:
S. C. Jain, Vice President Ohio EPA-DERR Nuclear Services (BV-A)
ATTN: Zack A. Clayton Post Office Box 1049 Columbus, OH 43266-0149 Dr. Judith Johnsrud National Energy Ccamittee Sierra Club 433 Orlando Avenue State College, PA 16803 Duquesne Lighi Company Beaver Valley Power Station PO Box 4 Shippingport, PA 15077 ATTN:
R. L. Grand Division Vice President. Nuclear Operations Group and Plant Manager (BV-SOSB-7)
T RE0 VEST FOR ADDITIONAL INFORMATION REGARDING SECOND AND THIRD 10-YEAR INTERVAL INSERVICE INSPECTION (ISI) PROGRAM RELIEF REOUESTS BEAVER VALLEY POWER STATION. UNIT NOS 1 AND 2 DOCKET NOS. 50-334 AND 50-412 1.
Scoce/ Status of Review The Nuclear Regulatory Commission (NRC) is responsible for the review and disposition of licensee submittals relating to ISI requirements contained in the Code of Federal Reaulations (CFR) 10 CFR 50.55a, and the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV).
Section XI.
Included within a submittal, licensees are required to provide both a regulatory basis (by citing the appropriate section of 10 CFR 50.55a),
and a technical discussion, to support the request.
This information is used to establish the context of each evaluation.
By letter dated March 25. 1997 Duquesne Light Company (DLC or the licensee) submitted relief requests applicable to Unit No. 1 and Unit No. 2, 10-Year ISI Programs. The NRC staff, with assistance from its contractor, Idaho National Engineering and Enviror...iental Laboratory (INEEL), is reviewing and evaluating the second and third 10-year interval ISI program plan requests for relief from the ASME B&PV Code,Section XI, requirements for Beaver Valley Power Station (BVPS), Unit Nos. 1 and 2.
The staff has determined that additional information and clarification are required from DLC to complete the review.
The required additional information is identified in the following section.
2.
Additional Information Reauired A.
By this submittal, it is not clear which interval the relief (s) applies to (it appears that several requests are associated with the second interval and several with the third).
Relief requests must be interval-specific. Therefore, the licensee should review the submittals to verify that the applicable interval is saecified.
Please describe the i
action the licensee proposes regarding t11s observation.
B.
It appears that several relief requests associated with reactor pressure vessel examinations also include augmented reactor 3ressure vessel examination information.
It should be noted that w1en the augmented reactor pressure vessel examinations are not satisfied, the licensee is required to submit information regarding the lir.ited examinations and a proposed alternative to the rule.
This submittal should be separate from relief requests associated with the Code requirements.
Please describe the action the licensee proposes regarding this observation.
2-C.
For Request for Relief BV2-D2.20-1, the licensee has completed the examination of 97% of the integral attachment welds required to be examined in the current interval. The licensee has requested that the examinations performed to date be accepted in lieu of the examination of 100% of the integral attachment welds.
Please discuss the percentage of integral attachments examined in each period, of the subject interval.
D.
For Request for Relief BV3-IWA-1 Revision 0. the licensee has proposed an alternative to the Code-required removal of insulation on borated systems for VT-2 visual examination during This alternative is similar to Code Case N-533. pressure tests.
However, as part of the proposed alternative, the licensee has proposed the following:
"A visual. VT-2 examination will be performed during the system pressure tests of IWB-5000 and IWC-5000 with the insulation installed.
In addition, insulation will be removed from all Class 1 and 2 bolted connections located inside the reactor containment building in systems borated for the purposes of controlling reactivity, at least once per inspection period during an outage and a visual VT-2 examination shall be performed for evidence of leakage (residue of boron) regardless if system pressure exists or not."
The purpose of a VT-2 visual examination is to look for evidence of leakage and, if leakage has occurred, to take corrective action.
The staff has determined that because hydrostatic pressure test requirements can be satisfied by pressure tests performed at normal operating pressure and because the subject VT-2 test can be perfonned during refueling outages by looking for evidence of leakage the subject insulation removal frequency is not pressure test frequency dependent.
Therefore, the alternative to Code required insulation removal that has been found acceptable, is the removal of insulation for VT-2 visual examinations of all bolted connections in Class 1 and 2 systems borated for controlling reactivity gitch refueling outage.
Please confirm that insulation removal will be performed for both Class 1 and 2 borated systems each refueling outage.
E.
In Request for Relief BV3-IWA-2 Revision 0, the licensee stated:
"If the leakage was identified with the bolted connection in service and the review supports continued service, the VT-3 examination may l
be deferred to the next outage of sufficient duration.
If this review warrants further evaluation of the bolted connection, the bolt closett to the leakage source shall be removed. VT-3 examined, and evaluated in accordance with IWA-3100(a). When the removed bolt has rejectable degradation, the remaining bolts will be removed. VT-3 examined and evaluated in accordance with IWA-3100(a)."
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Note 5, included under Examination Category B-G-1, requires a VT-1 visual examination of bolting, when leakage is detected when performing VT-2 visual examinations in accordance with the requirements of IWA-5250(a)(2). When considering the corrective action proposed for bolt (s) removed for evaluation it has been determined that the VT-1 visual examination is the appropriate examination. The-licensee has proposed to perform a VT-3 visual examinatior Please confirm that a VT-1 will be performed in lieu of the currently proposed VT-3 visual examination.
Later editions of the Code have provided an alternative to the removal
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of all bolting at a leaking connection. The licensee's approach to perform an evaluation of the bolted joint for the determination of bolt e
removal deferral when degradation is occurring is considered overly subjective.
Deferral of bolt removal when degradation is occurring is i
unacceptable.
Therefore, the' licensee should consider the withdrawal of this part of the proposed alternative.
Please describe the action the licensee proposes regarding this concern, 4
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