ML090090189

PINGP Lr - FW: OAR, RAI on Reactor Pressure Vessel Surveillance TAC No. MD2435

ML090090189
Person / Time
Site:	Prairie Island
Issue date:	09/24/2008
From:	Office of Nuclear Reactor Regulation
To:
References
Download: ML090090189 (6)

Text

1 PrairieIslandNPEm Resource From:

Richard Plasse Sent:

Wednesday, September 24, 2008 6:16 AM To:

Eckholt, Gene F.

Subject:

FW: OAR, "RAI on Reactor Pressure Vessel Surveillance TAC No. MD2435" Attachments:

PINGP RAIs.doc draft RAIs From: Kaydian Beckford Sent: Monday, September 15, 2008 12:18 PM To: Rani Franovich Cc: Ganesh Cheruvenki; Atif Shaikh; RidsNrrDciCvib Resource; Richard Plasse

Subject:

OAR, "RAI on Reactor Pressure Vessel Surveillance TAC No. MD2435" Enclosed, please find electronic distribution of the memo:

To: Rani L. Franovich From: Matthew A. Mitchell

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)

Originators: Ganesh S. Cheruvenki, Atif Shaikh 301-415-2501 301-415-3948 ADAMS Accession No. ML082590263

• • • NOTE: The enclosed ADAMS pointer is to an advanced copy of the document mentioned above. It is currently being processed, and will be an OAR as soon as possible.***

Hearing Identifier:

Prairie_Island_NonPublic Email Number:

286 Mail Envelope Properties (Richard.Plasse@nrc.gov20080924061500)

Subject:

FW: OAR, "RAI on Reactor Pressure Vessel Surveillance TAC No. MD2435" Sent Date:

9/24/2008 6:15:31 AM Received Date:

9/24/2008 6:15:00 AM From:

Richard Plasse Created By:

Richard.Plasse@nrc.gov Recipients:

"Eckholt, Gene F." <Gene.Eckholt@xenuclear.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 1014 9/24/2008 6:15:00 AM PINGP RAIs.doc 57850 Options Priority:

Standard Return Notification:

No Reply Requested:

No Sensitivity:

Normal Expiration Date:

Recipients Received:

September 15, 2008 MEMORANDUM TO:

Rani L. Franovich, Chief License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation FROM:

Matthew A. Mitchell, Chief /RA/

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 (CVIB) 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 (RAI) is enclosed.

Docket Nos.: 50-282, 50-306

Enclosure:

Request for Additional Information CONTACT: Ganesh S. Cheruvenki, DCI/CVIB Atif A. Shaikh, DCI/CVIB (301) 415-2501 (301) 415-3948

September 15, 2008 MEMORANDUM TO:

Rani L. Franovich, Chief License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation FROM:

Matthew A. Mitchell, Chief /RA/

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 (CVIB) 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 (RAI) is enclosed.

Docket Nos.: 50-282, 50-306

Enclosure:

Request for Additional Information CONTACT: Ganesh S. Cheruvenki, DCI/CVIB Atif A. Shaikh, DCI/CVIB (301) 415-2501 (301) 415-3948 DISTRIBUTION:

DCI R/F PPatnaik RPlasse ADAMS ACCESSION NO: ML082590263 OFFICIAL RECORD COPY OFFICE NRR/DCI/CVIB NRR/DCI/CVIB NRR/DCI/CVIB NAME GCheruvenki /RA/

AShaikh /RA/

MMitchell /RA/

DATE 9/08/08 9/08/08 9/15/08

ENCLOSURE 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,

4) Peak projected reactor pressure vessel (RPV) neutron fluence for each PINGP RPV at the end of the period of extended operation,

5) The identification numbers of the capsules, and

6) Heat numbers of the surveillance materials in the capsules at both units (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.

(D) The staff requests that the applicant include the following statements in the commitment table of the license renewal application.

1) The applicant will notify the staff if there is any change in the withdrawal schedules of the surveillance capsules.

2) If a standby capsule is removed from the RPV without the intent to test it, the capsule will be stored in manner which maintains it in a condition which would permit its future use, including during the period of extended operation, if necessary.

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 staffs reactor vessel integrity database (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 found 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.