ML18065B159
| ML18065B159 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 01/29/1998 |
| From: | Bordine T CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9802060077 | |
| Download: ML18065B159 (5) | |
Text
A CMS Energy Company January 29, 1998 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT Tllomaa C. Bardin&
Manager Licensing RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION - PRIMARY COOLANT PUMP FLYWHEEL INSPECTION TECHNICAL SPECIFICATIONS CHANGE REQUEST On December 5, 1997, the NRC requested additional information regarding the Technical Specifications Change Request (TSCR) submitted by Consumers Energy on October 1, 1997. The information requested was to be submitted within 30 days of the date of the NRC's letter. However, the NRC Palisades Project Manager authorized an extension until January 31, 1998, to provide the requested information. The attachment to this letter provides the Consumers Energy response to the request for additional information.
The October 1, 1997, TSCR proposed that the Technical Specifications Primary Coolant Pump flywheel inspection period be lengthened to 10 years. This would result in a decrease in the frequency of the inspections from the current requirement of every refueling outage. The Combustion Engineering Owner's Group Report SIR-94-080-A supports a complete elimination of the flywheel inspections.
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Palisades Nuclear Plant
- 27780 Blue Star Memorial Highway
- Coveil, Ml 49043
- Tel: 616 764 2913
- Fax: 616 764 2490
SUMMARY
OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments.
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Thomas C. Berdine Manager, Licensing CC Administrator, Region Ill, USNRC Project Manager, NRR, USNRC NRC Resident Inspector - Palisades Attachment 2
ATTACHMENT CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PRIMARY COOLANT PUMP FLYWHEEL INSPECTION TECHNICAL SPECIFICATIONS CHANGE REQUEST 2 Pages
,RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PRIMARY COOLANT PUMP FLYWHEEL INSPECTION TECHNICAL SPECIFICATIONS CHANGE REQUEST NRC REQUEST The application of topical report SIR-94-080-A, "Relaxation of Reactor Coolant Pump Flywheel Inspection Requirements," to Palisades requires that the licensee (1) verify the reference temperature, RTN0 r, for the flywheel material (ASTM A-108 (1017) low carbon steel), and (2) justify the use of the K1c vs. (T-RTNor) curve in Appendix A of Section XI of the ASME Code. It does not appear as if these requirements have been adequately addressed in the licensee's submittals. Please provide:
(1)
Plant-specific test data or data from other sources to demonstrate that the NOT is 40°F and the RTNor is also 40°F.
(2)
Plant-specific test data or data from other sources to demonstrate that the K1c vs. (T-RTNor) curve for ASTM A-108 (1017) low carbon steel is similar to the K1c vs. (T-RTNor) curve in Appendix A of Section XI of the ASME Code derived from test data for SA 5338 and SA 508 materials. The cited 100 ksi-id~ was estimated from the ASME curve; however, the applicability of the ASME curve to the Palisades flywheel material has not been established.
CONSUMERS ENERGY RESPONSE The material information which was used in the topical report SIR-94-080-A was obtained from previous correspondence between the NRC and Consumers Energy (then Consumers Power Company). The correspondence was the draft NRC safety evaluation for the Systematic Evaluation Program (SEP) Topic 111-10.8 dated May 15, 1981, from the NRC to Consumers Energy (Reference No. 7 in Report SIR-94-080-A).
The final NRC safety evaluation, dated February 2, 1982, also contained the identical information. The source of the information was stated in the October 1, 1997, TSCR submittal, Attachment 1, Pages 3-4. The information which was the source for the NRC's safety evaluation for SEP Topic 111-10.B is not specifically known. However, the flywheel material was stated to be SAE 1017, type 1020 material with a NOT of +40°F in a submittal dated August 26, 1969. This submittal provided an amendment to the application for the Reactor Construction Permit and Operating License. Documentation by certified material test reports of the flywheel material is not known to exist at this time.
(1)
The NOT of 40°F was contained in all of the above referenced correspondence. The topical report SIR-94-080-A used the information 1
~ESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PRIMARY COOLANT PUMP FLYWHEEL INSPECTION TECHNICAL SPECIFICATIONS CHANGE REQUEST provided by the NRC draft safety evaluation for SEP Topic 111-10.8 dated May 15, 1981. The RT Nor was considered to be the same as the NOT in the topical report. RT Nor is defined in the ASME Code, Section Ill, N8-2331, as equal to TNor when at least 50 ft-lb and 35 mils lateral expansion is met at a temperature of (T Nor+ 60°F).
T Nor= the nil-ductility transition temperature by drop weight tests, also taken as equivalent to NOT from the NRC draft safety evaluation Alternatively, RT Nor is the higher temperature of T Nor or (T ev - 60 ° F).
T ev = the temperature where the 50 ft-lb and 35 mils lateral expansion properties are met if not at (T Nor + 60 ° F)
While the mils lateral expansion data are not available, the Charpy V-notch (CVN) at 70°F is documented as 100 ft-lb in the NRC draft safety evaluation for SEP Topic 111-10.8 of May 15, 1981. This margin supports the conclusion that the RT Nor may be conservatively considered as 40°F, the same as T Nor and therefore the NOT.
(2)
As stated in the October 1, 1997, submittal, the curve in Appendix A of Section XI of the ASME Code was not used to derive the value of K1e for the Palisades flywheels. Therefore, the justification for the use of the Appendix A curve was not applicable. The topical report SIR-94-080-A used the dynamic stress intensity value of 100 ksi-inY. for the flywheels that was contained in the NRC draft safety evaluation for SEP Topic 111-10.8 dated May 15, 1981. In the topical report, the K1e value was considered to be the same as the dynamic stress intensity.
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