ML20210J580
| ML20210J580 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/13/1997 |
| From: | David Diec NRC (Affiliation Not Assigned) |
| To: | Richard Anderson NORTHERN STATES POWER CO. |
| References | |
| TAC-M98944, TAC-M98945, NUDOCS 9708180147 | |
| Download: ML20210J580 (4) | |
Text
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l August 13, 1997 Mr. Roger O. Anderson, Director j
Licensing and Management Issues i
Northern States Power Company i
di 4 Nicollet Mall Minneapolis, Minnesota $5401
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE PRAIRIE ISLAND
)
NUCLEAR GENERATING PLANT, UNITS 1 AND 2, AMENDMENT REQUEST ON INCORPORATION OF VOLTAGE BASED STEAM GENERATOR TUBE I
REPAIR CRITERIA (TAC NOS. M98944 AND M98945)
Dear Mr. Anderson:
By letter dated May 15,19^7 f tarn States Power (NSP) Company submitted for staff -
review a license amendmen! *gmW M incorporate the voltage-based steam generator tube repair criteria in the technical spat.uions (TS) for the Prairie Island Nuclear Generating -
Plant. The proposed changes would be made to TS 3.1.C," Reactor Coolant System Leakage," and 4.12, " Steam Generator Tube Surveillance " After reviewing the information, the staff requires further information. Our request for additional information (RAI) is enclosed.
In order to continue our review of your submittal, please provide your response to the staff's 1
RAI within 20 days of the receipt of this letter in order to support your requested outage schedule. If you have any questions regarding the content of the RAI, please contact me at i
(301) 415 2834.
Sincerely, Orig. signed by e
David T. Diec, Acting Project Manager Project Directorate 1111 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket Nos. 50-282, 50-306
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Enclosure:
As stated cc w/ encl: See next page DISTRIBUTION:
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- g..,o August 13. 1997 Mr. Roger O. Anderson, Director Licensing and Management issues Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota $5401
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2, AMENDMENT REQUEST ON INCORPORATION OF VOLTAGE BASED STEAM GENERATOR TUBE REPAIR CRITERIA (TAC NOS. M980
- n M98945)
Dear Mr. Anderson:
By letter dated May 15,1997 Northern States Power (MP) Company submitted for staff review a license amendment request to incorporate the voltage based steam generator tubu repair criteria in the technical specifications (TS) for the Prairie Island Nuclear Generating Plant. The proposed changes would be made to TS 3.1.C. " Reactor Coolant System Leakage," and 4.12. " Steam Generator Tube Surveillance." After reviewing the information, the staff requires further information. Our request for additionalinformation (RAl)is enclosed.
In order to continue our review of your submittal, please provide your response to the staff's RAI within 20 days of the receipt of this letter in order to support your requested outage schedule. If you have any questions regarding the content of the RAI, please contact me at (301) 415 2834.
Sincerely,
/
c David T. Diec, Acting Project Manager Project Directorate ill-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket Nos. 50-282, 50-306
Enclosure:
As stated cc w/ encl: See next page
=
i Mr. Roger O. Anderson, Director Prairie Island Nuclear Generating i
Northem States Power Company Plant ec:
J. E. Silberg, Esquire Site Licensing Shaw, Pittman, Potts and Trowbridge Prairie Island Nuclear Generating 2300 N Street, N. W.
Plant Washington DC 20037 Northem States Power Company 1717 Wakonado Drive East l
Plant Manager Welch, Minnesota 5508g Prairie Island Nuclear Generating Plant Tribal Council Northern States Power Company Prairie Island Indian Community 1717 Wakonsde Drive East ATTN: Environmental Department Welch, Minnesota 5508g 5636 Sturgeon Lake Road Welch, Minnesota 5508g Adonis A. Noblett Assistant Attomey General Office of the Attomey General 455 Minnesota Street Suite 900 St. Paul, Minnesota 55101 2127 U.S. Nuclear Regulatory Commission Resident inspector's Office 171g Wakonade Drive East Welch, Minnesota 5508g-9642 Regional Administrator, Region til U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Mr. Jeff Cole, Auditor / Treasurer Goodhue County Courthouse Box 408 Red Wing, Minnesota 55066-0408 l
Kris Sanda, Commissioner Department of Public Service 121 Seventh Place East i
l Suite 200 l
St. Paul, Minnesota 55101 2145 November 1996
~
REQUEST FOR ADDITIONAL INFORMATION REVIEW OF LICENSE AMENDMENT REGARDING VOLTAGE BASED STEAM GENERATOR TUBE REPAIR CRITERIA AT THE PRAIRIE ISLAND NUCLEAR GENERATING #LANT (TAC NOS. M98944 AND M98945)
Q1. Page 2 of Exhibit D. Northem States Power (NSP) states that the latest approved EPRI i
[ Electric Power Research Institute) database (7/8-inch diameter tubing) will t e used in performing Generic Letter (GL) 95 05 (" Voltage Based Repair Criteria for Westinghouse Steam Generator Tubes Affected By Outside Diameter Stress Corrosion Cra: king')
specified calculations. The staff has agreed, in principle, with the Nuclear Energy Institute (NEI) on a protocol by which the industry will periodically update the database used to perform GL 95 05-specified calculations (
Reference:
Letter from Brian Sheron, NRC, to David Modeen, NEl, dated April 10,1997). Licensees, including NSP, should follow the guidance of the protocol and provide the staff with the latest database used in performing GL 95-05-specified calculations.
Q2. Page 2 of Exhibit D. NSP states that tube integrity evaluation will be consistent with Westinghouse WCAP-14277, "SLB Leak Rate and Tube Burst Probability Analysis 3
Methods for ODSCC at TSP Intersections." However, on page 9 of Exhibit A, NSP references WCAP-14277, Revision 1. Please verify the WCAP revision used to evaluate tube integrity.
Q3. Address how guidelines in Section 2 of Attachment 1 to GL 95-05 would be implemented. Specifically, (a) discuss the differentir) pressure (across the tube walls) required for conditional tube burst probability; [The differential pressure is dependent on the operability requirements of the pressurizer power-operated relief valves (PORVs) during power operation.} and (b) verify that Prairie Island satisfies the requirements of i
GL 90-06, " Resolution of Generic issue 70, ' Power-Operated Relief Valve and Block Valve Reliability,' and Generic Issue 94, ' Additional Low-temperature Overpressure i
Protection for Light-water Reactors,' pursuant to 10 CFR 50.54(f)."
Q4. Page 4 of Exhibit D. It is stated that the industry methodology will be used for new probe variability as approved by the NRC. Discuss which industry methodology will be used and provide reference documents that contain the methodology, Q5. Pass 4 of Exhibit D. It is not clear to the staff that NSP has committed to the guidelines in Sections 3.b.2, 3.b.3, 3.b.4, 3.c.1, 3.c.2, 3.c.5, 3.c.6, 3.c.7, and 3.c.8 of Attachment i to GL 95-05. Please confirm and/or address whether NSP has committed to the above-mentioned guidelines.
- 06. Section 5.b of Attachment 1 to GL 95-05 recommends that the effectiveness of monitoring procedures for ensuring the timely detection, trending, and response to rapidly increasing leaks should be assessed. In addition, the appropriateness of alarm setpoints on the primary-to-secondary leakage detection instrumentation and the various criteria for operator action in response to detected leakage should also be assessed.
D;scuss whether the above assessments have been performed to satisfy Section 5.b of to GL 95-05.
Enclosure
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