ML20079L723
| ML20079L723 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/15/1983 |
| From: | Larson C NORTHERN STATES POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| REF-SSINS-6820 IEB-82-02, IEB-82-2, NUDOCS 8302230427 | |
| Download: ML20079L723 (2) | |
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Northem States Power Company 414 Ncollet Mall Minneapolis, Minnesota 55401 Telephone (612) 330-5500 February 15, 1983 Mr. James G. Keppler Regional Administrator - III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 Docket No. 50-306 License No. DPR-60 The following report provides the information requested by Action Item 4 of IE Bulletin 82-02:
Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of PWR Plants.
The information was collected during the Unit I refueling outage ending December 18, 1982.
Action Item 4:
A written report signed under oath or affirmation under provisions of Section 182a, Atomic Energy Act of 1954 as amended, shall be submitted to the Regional Adminis-trator of the appropriate NRC Regional Office within 60 days following the comple tion of the outage during which Action Item 2 was performed.
The report is to include:
a.
A statement that Action Item 1 has been completed.
b.
Identification of the specific connections examined as required by Action Item 2.
c.
The results of the examinations performed on the threaded fasteners as required by Action Item 2.
If no degradation was observed for a particular connection, a statement to that effect, identifi-cation of the connection and, whether the fasteners were examined in place or removed is all that is required.
If degradation wac observed, the report should provide detailed information.
8302230427 830215 PDR ADOCK 05000282 O
PDR FEB 17 E63 ZE //
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Mr.-James G. Keppler
--2
. February.- 15, 1983
Response
l a.
Action Item 1 has been completed.
The following closure connections,,that were within b.
the scope of the bulletin, were opened for. maintenance and:were inspected as required by the bulletin.-
(1) Reactor Vessel Head Closure Studs - 16 of 48.
(2) Both Steam Generators Primary-Side Manways Bolts.
4 (3) Both Reactor Coolant Pumps Upper and Lower Seal Housing Bolts.
(4) Pressurizer Safety Valves RC-10-1 and RC-10-2, Upstream Flange Bolts.
c.
Examination of the above listed connections revealed no degradation.
All the fasteners inspected were removed for examination.
Yours very tr C.E. Larso Director, Nuclear Generation l
CEL/ts l-cc Mr. C. Charnoff Mr. C. Feierabend i
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