ML101900058
| ML101900058 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/20/2010 |
| From: | Lisa Regner License Renewal Projects Branch 2 |
| To: | Office of Nuclear Reactor Regulation |
| Regner L M, NRR/DLR, 415-1906 | |
| References | |
| Download: ML101900058 (6) | |
Text
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LICENSEE:
Arizona Public Service Company FACILITY:
Palo Verde Nuclear Generating Station, Units 1, 2, and 3
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JULY 8,2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ARIZONA PUBLIC SERVICE COMPANY, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE PALO VERDE NUCLEAR GENERATING STATION, UNITS 1,2, AND 3, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (the staff) and representatives of Arizona Public Service Company (the applicant) held a telephone conference call on July 8, 2010, to discuss and clarify the staff's draft request for additional information (RAI) concerning the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's draft RAI. provides a listing of the participants and Enclosure 2 contains a listing of the draft RAI discussed with the applicant, including a brief description on the status of the items.
The staff also discussed the response from the applicant dated June 21, 2010, concerning the buried piping and tanks aging management program modifications. The staff stated that a stronger regulatory position is necessary for the aging management of buried piping and tanks in light of the recent operating experience of age-related piping failures. The applicant agreed to submit additional regulatory commitments to strengthen the buried piping and tanks program.
The applicant had an opportunity to comment on this s Lisa M. Regner, Sr. Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-528, 50-529, and 50-530
Enclosures:
As stated cc w/encls: Distribution via Listserv
TELEPHONE CONFERENCE CALL PALO VERDE NUCLEAR GENERATING STATION, UNITS 1,2, AND 3 PARTICIPANTS Lisa Regner William Holston James Gavula Angela Krainik Glenn Michael Robert Lee Mark Hypse Eric Blocher LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JULY 8,2010 AFFILIATIONS U.S. Nuclear Regulatory Commission (NRC)
NRC NRC Arizona Public Service Company (APS)
APS APS APS Strategic Teaming and Resource Sharing (STARS) Alliance ENCLOSURE 1
DRAFT REQUEST FOR ADDITIONAL INFORMATION PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION JULY 8,2010 The U.S. Nuclear Regulatory Commission (the staff) and representatives of Arizona Public Service Company (the applicant) held a telephone conference call on July 8, 2010, to discuss and clarify the following draft request for additional information (RAI) concerning the Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3, license renewal application (LRA).
DRAFT RAI 3.3.1-1
Background
"Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants" (SRP-LR) Table 3.3.1, item 75 indicates that elastomer components exposed to raw water may undergo hardening and loss of strength due to elastomer degradation, and loss of material due to erosion. The Generic Aging Lessons Learned (GALL) Report recommends that this aging effect be managed by the Open-Cycle Cooling Water System.
The PVNGS license renewal application (LRA) Table 3.3.1, item 3.3.1.75 indicates that aging of elastomer components exposed to raw water is not applicable because PVNGS has no in-scope elastomer components exposed to raw water in the open-cycle cooling water systems. Staff examination of the LRA identified the following items which could be classified as elastomeric components exposed to raw water:
Table 3.3.2-7 identifies polyvinyl chloride (PVC) components and Table 3.3.2-22 identifies polyethylene components. In both cases, the tables cite generic Note F indicating that the materials are not in the GALL Report, and also state that there are no aging effects requiring management. Although the LRA stated that PVC is relatively unaffected by water, there were no further bases provided to justify that there were no aging effects requiring management for PVC or polyethylene. The staff was specifically concerned about the loss of material due to erosion.
Tables 3.3.2-22 and 3.3.2-30 indicate that the loss of material for carbon steel pipe with elastomer linings in raw water are to be managed through the Fire Water System Program and the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program, respectively. Since the item numbers cited in the LRA do not specifically address the loss of material for the elastomer, it was not clear to the staff that the aging management programs (AMPs) being proposed would adequately manage the loss of material for the elastomer lining. Although the cited AMPs addressed pressure boundary and leakage boundary, the potential consequences of the degraded elastomer lining material in the associated systems was not addressed.
ENCLOSURE 2
- 2 Request Provide a basis for why these components, or other elastomer components exposed to raw water in the auxiliary system are appropriately being managed for aging during the period of extended operation for the issues discussed above.
Discussion: the applicant stated the question and is clear.
DRAFT RAI 3.3.2.2.4-X
Background
The SRP-LR Section 3.3.2.2.4, Cracking due to Stress Corrosion Cracking and Cyclic Loading, recommends further evaluation of stainless steel non-regenerative heat exchanger components exposed to treated borated hot water in the chemical and volume control system. The SRP-LR states that the effectiveness of the water chemistry control program should be verified to ensure cracking is not occurring. The SRP-LR also states that an acceptable verification program includes temperature and radioactivity monitoring of the shell side water, and eddy current testing of the tubes LRA Section 3.3.2.2.4.1, stated that the Water Chemistry and One-Time Inspection Programs will be used to manage cracking due to stress corrosion cracking and cyclic loading for the stainless steel chemical volume and control system letdown (non-regenerative) heat exchanger components exposed to treated borated water. The LRA also stated that temperature and radioactivity of the shell-side water will be monitored by installed instrumentation. The LRA further stated that, in lieu of the SRP-LR recommendation for eddy current testing of heat exchanger tubes, the One-Time Inspection Program was selected. However, the LRA did not indicate the nondestructive examination methodology that would be utilized as an alternative to eddy current testing of the heat exchanger tubes.
Request
- 1) Provide the nondestructive examination method that will be utilized in the one-time inspection program, in lieu of eddy-current testing of the non-regenerative heat exchanger tubes.
- 2) Will the nondestructive examination be performed on the non-regenerative heat exchanger tubes or will an inspection of an alternate component be credited for the one time inspection?
- 3) If an alternate component will be credited, provide bases for the effectiveness of this approach, based on plant-specific or industry operating experience, to detect stress corrosion cracking in these heat exchanger tubes.
Discussion: the applicant stated the question is clear.
'.. ML101900058 OFFICE LA:RPOB:DLR PM:RPB2:DLR BC:RPB2:DLR PM:RPB2:DLR NAME
!King LRegner DWrona LRegner DATE 07/15/10 07/19/10 07/20/10 07/20/10
Memorandum to Arizona Public Service Company from L Regner dated July 20, 2010
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JULY 8,2010, BEIWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ARIZONA PUBLIC SERVICE COMPANY, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3, LICENSE RENEWAL APPLICATION DISTRIBUTION:
HARD COPY:
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