ML090090163
| ML090090163 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/07/2008 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| Download: ML090090163 (6) | |
Text
1 PrairieIslandNPEm Resource From:
Richard Plasse Sent:
Tuesday, October 07, 2008 2:14 PM To:
Eckholt, Gene F.
Subject:
PINGP RAIs.doc draft RAIs updated
Hearing Identifier:
Prairie_Island_NonPublic Email Number:
279 Mail Envelope Properties (Richard.Plasse@nrc.gov20081007141300)
Subject:
10/7/2008 2:13:33 PM Received Date:
10/7/2008 2:13:00 PM From:
Richard Plasse Created By:
Richard.Plasse@nrc.gov Recipients:
"Eckholt, Gene F." <Gene.Eckholt@nmcco.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 20 10/7/2008 2:13:00 PM PINGP RAIs.doc 52334 Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
Recipients Received:
MEMORANDUM TO:
Rani L. Franovich, Chief License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation FROM:
Matthew A. Mitchell, Chief Vessels & Internals Integrity Branch Division of Component Integrity Office of Nuclear Reactor Regulation
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON REACTOR PRESSURE VESSEL SURVEILLANCE AGING MANAGEMENT PROGRAM, PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS.
MD8513, MD8514)
The Vessels & Internals Integrity Branch has reviewed the information provided by Nuclear Management Company for the reactor pressure vessel (RPV) surveillance aging management program at Prairie Island Nuclear Generating Plant, Units 1 and 2. The staff has identified that additional information is needed to complete the review. The staffs request for additional information is enclosed.
Docket Nos.: 50-282, 50-306
Enclosure:
Request for Additional Information CONTACT: Ganesh S. Cheruvenki, DCI/CVIB (301) 415-2501 Atif A. Shaikh, DCI/CVIB (301) 415-3948
MEMORANDUM TO:
Rani L. Franovich, Chief License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation FROM:
Matthew A. Mitchell, Chief Vessels & Internals Integrity Branch Division of Component Integrity Office of Nuclear Reactor Regulation
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON REACTOR PRESSURE VESSEL SURVEILLANCE AGING MANAGEMENT PROGRAM, PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS.
MD8513, MD8514)
The Vessels & Internals Integrity Branch has reviewed the information provided by Nuclear Management Company for the reactor pressure vessel (RPV) surveillance aging management program at Prairie Island Nuclear Generating Plant, Units 1 and 2. The staff has identified that additional information is needed to complete the review. The staffs request for additional information is enclosed.
Docket Nos.: 50-282, 50-306
Enclosure:
Request for Additional Information CONTACT: Ganesh S. Cheruvenki, DCI/CVIB (301) 415-2501 Atif A. Shaikh, DCI/CVIB (301) 415-3948 DISTRIBUTION:
DCI RF GCheruvenki PPatnaik RPlasse DLRA AShaikh OFFICIAL RECORD COPY OFFICE DCI/CVIB DCI/CVIB DCI/CVIB NAME GCheruvenki AShaikh MMitchell DATE
ENCLOSURE 3
REQUEST FOR ADDITIONAL INFORMATION ON REACTOR VESSEL SURVEILLANCE PROGRAM PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNITS 1 AND 2 LICENSE RENEWAL APPLICATION DOCKET NOS. 50-282, 50-306 RAI-B.2.1.34 (A) Section 6.0 in aging management program XI.31, Reactor Vessel Surveillance, in NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Volume 2, Revision 1 states that if an applicant has a surveillance program that consists of capsules with a projected fluence of less than the projected 60 year fluence at the end of 40 years, at least one capsule is to remain in the reactor vessel and tested during the extended period of operation.
Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2 has tested four of the six surveillance capsules in each unit to date, and the latest capsules of Units 1 and 2 were tested at projected fluence values which are less than 60 year fluence. To ensure that the applicant is in compliance with the aforementioned GALL requirement, one of the two remaining capsules in each unit should be tested during the extended period of operation and the following relevant information regarding the testing of the capsules should be provided to the staff.
(1) Applicants plan to test an additional surveillance capsule from each unit, (2) The projected refueling outages of withdrawal for each unit, (3) Projected neutron fluence value for each capsule at the time of withdrawal, (B) The staff requests that the applicant confirm that the withdrawal schedule of the capsules to be used for future tests during the extended period of operation is consistent with the requirements, specifically the limitations on lead factor, specified in paragraph 7.6.2 of the American Society of Testing Materials (ASTM) E 185, Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels.
(C) The staff requests that the applicant confirm that untested surveillance capsules (standby capsules) will be stored for future use at PINGP, Units 1 and 2.
ENCLOSURE 4
RAI: 4.2.2 Based on the beltline material Circumferential Weld - Nozzle Shell Forging B to Intermediate Shell Forging C, the staff assumes that there is a small line nozzle penetration in the beltline region of the RPV. The staff requests the applicant to confirm this detail.
RAI: 4.2.3 In Table 4.2-5 of the PINGP LRA, the RTNDT(u) for beltline material Lower Shell Forging D (22642) is listed as -4 ºF. However, the value of RTNDT(u) for this beltline material is listed as 2 ºF in the PINGP RVID. Provide information which documents where the value of -4 ºF comes from and demonstrate that is applicable to this forging.
RAI: 4.2.4 Per the requirements of 10 CFR 54.21(c)(1)(i) and the staff guidance in NUREG 1800, the projected neutron fluence and subsequent adjusted reference temperature (ART) values at the end of the extended period of operation are reviewed to verify that they are bound by the embrittlement assumed in the existing P-T limit analysis. Therefore, the staff requests the applicant to provide current 1/4 T and 3/4 T (ART) values for all the beltline materials.
RAI: 4.7.2 In section 4.7.2 of the PINGP LRA, the applicant states that the number of design cycles and transients assumed in topical report WCAP-15338, A Review of Cracking with Weld Deposited Cladding in Operating PWR Plants, analyses bound the number of design cycles and transients projected for 60 years of operation as presented in Table 4.3-1 of the PINGP LRA. However, the WCAP-15338 report does not explicitly state the number of design cycles and transients used in the analyses of crack growth for 60 years of operation of the RPV. The staff requests the applicant to provide the bounding number of design cycles and transients that were used in the WCAP-15338 report analyses.