ML20138L578

Forwards Request for Addl Info Re Plant Third 10-yr Interval ISI Program Plan Associated Requests for Relief

ML20138L578
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	02/19/1997
From:	Addy R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TAC-M96210, NUDOCS 9702240416
Download: ML20138L578 (18)

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consumers l

Patrick M Donnelly Pfortt Manager l

ASKMGAW5 99llNHRE55 i

Sq) Rock Po.nt Nuclear Plant,10269 US 31 North, Charlevoix, MI 49720 February 19, 1997 l 4

Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-I55 - LICENSE DPR BIG ROCK POINT PLANT - 60 DAY REPLY TO A I REQUEST FOR ADDITIONAL INFORNATION REGARDING THE BIG ROCK POINT PLANT THIRD I 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAN PLAN ASSOCIATED REQUESTS FOR i RELIEF.  ;

In order for the Staff to complete its review of the third 10-year interval l inservice inspection program plan, additional information was requested. The required information has been included as an attachment to this letter.

At the Staff's request, a copy has also been sent to your contractor, INEL, at the following address:

Michael T. Anderson i INEL Research Center i

2151 North Boulevard PO Box 1625 Idaho Falls, Idaho 83415-2209 h3 Robert J Addy Assistant Plant Manage /

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l CC: Administrator, Region III, USNRC 240030 pq, NRC Resident Inspector Big Rock Point ATTACHMENTS

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9702240416 970219 l PDR ADOCK 05000155 G PDR l A Gts ENE7tGYCOMPANY

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ATTACHMENT 1 CONSUMERS POWER COMPANY BIG ROCK P0 INT PLANT  ;

DOCKET 50-155 I i

I 60 DAY REPLY TO A REQUEST FOR ADDITIONAL INFORMATION REGARDING THE BIG ROCK POINT PLANT THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN ASSOCIATED REQUESTS FOR RELIEF.

Submitted February 19, 1997 l

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4 5 Pages

,' R!sponse to Request Fcr Additignal Infcrmaticn 1 !

. Third 10-Ycar Int:rval Ins:rvice Inspection Prsgram Plan and Associated Requests For Relief Dated December 31, 1996 (TAC No. N96210) ,

The following information is in response to an additional information request dated December 31, 1996 to allow the NRC to complete their review of the ISI .

Program P1an.  ;

In addition, to expedite the review process and per your request, a copy of  !

the RAI response is being sent to your contractor INEL Research Center, 2151 l North Boulevard, P.O. Box 1625, Idaho Falls, Idaho 83415-2209, Attn:  !

Michael T. Anderson.  ;

NRC Reauest: l 2A) Based on the initial review of the Ifcensee's submittal, the staff have '

concluded that appropriate paragraphs of the regulations have not been

. referenced in all cases. For each of Requests for Relief RR-A15 through RR-A22, cite the appropriate paragraph of the regulations to ensure that i the request is evaluated in accordance with the appropriate criteria, as discussed below. Verify that the regulatory basis has been adequately i' supported.

l The regulations provide that a Itcensee may propose an alternative to CFR  ;

or Code Requirements in accordance with 10 CFR 50.55a(s)(3)(f) or 10 CFR ,

50.55a(a)(3)(ii). Under 10 CFR 50.55a(s)(3)(f), the proposed alternative '

must be shown to provide an acceptable level of quality and safety, f.e.,

essentially be equivalent to the original requirement in terms of quality ,

and safety. Under 10 CFR 50.55a(a)(3)(if), the Ifcensee must show that i compliance with the original requirement results in a hardship or unusual {'

difficulty without a compensating increase in the level of quality and safety. Examples of hardship and/or unusual difficulty include, but are not limited to, excessive radiation exposure, disassembly of components solely to provide access for examination, and development of sophisticated \

tooling that would result in only minimal increases in examination 1 coverage. l A licensee may also submit a request for relief from ASME requirements.

In accordance with 10 CFR 50.55(g)(5)(fif), if a Ifcensee determines that conformance with certain code requirements is impractical for its facility, the ifcensee shall notify the Commission and submit, as specified in 10 CFR 50.4, information to support that determination. When a Ifcensee determines that an inspection requirement is impractical, e.g.,

the system would have to be redesigned, or a component would have to be replaced to enable inspection, the licensee should cite 10 CFR 50.55a(g)(5)(if f). The NRC may, giving due consideration to the burden placed on the licensee, impose an alternative examination requirement.

Licensee's Reply:

l Consumers Power Company has reviewed the Requests for Relief RR-AIS through l RR-A22 and has verified that the appropriate paragraph of the regulations for each of the Requests for Relief is 10 CFR 50.55a(g)(5)(iii).

l NRC Reauest l

28) For each of Requests for Relief RR-A15 through RR-A22, describe how

. volumetric examination coverage is determined at Big Rock Point Plant and i confirm that the subject welds have been examined in four directions to '

the extent practical. In each of these requests, the angle beam coverage is

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, R:spons2 to Requ st Fcr Addititnal Infcrmatien 2

. Thiril 10-Ycar Ictcrval Ins:rvic2 Inspecticn Progran Plan and Ass:ciated Requests For Relief Dated December 31,1996 (TAC No. M96210) 4 presented in terms of "two directional coverage achieved." However, there is no indication of which two of the four required directions (two axial and two circumferentf al) have been examined. The examination requirements

, for the subject welds are contained in Section V, Article 4, Paragraph T-

441.3.2.5, Angle Beam Scanning, which states (in part)

"The examination volume shall be scanned with angle beam search units directed both at right angles to the weld axis and along the weld axis. Wherever feasible, each examination shall be performed in two directions, f.e., approaching the weld from opposite directions and parallel to the weld from opposite directions.

These examinations shall be conducted using two beam angles (nominal 45* and 60*) from each direction."

licensee's Reolv:

Volumetric examination coverage at the Big Rock Point Plant is determined

] by the most limiting ultrasonic beam angle with two direction coverage (i.e., approaching the weld from opposite directions). The Big Rock Point Plant believes that this conservative approach is the correct way to determine the percent of coverage rather than taking an average of the four code required examinations.

A review of examination. data for the subject welds has been performed.

This review was conducted to verify that the code required axial

, (approaching the weld from opposite directions) and transverse to weld 4

(clockwise and counter-clockwise directions) examinations were performed to the extent practical. Upon completion of this review it has been 4

confirmed that these examinations have been performed to the maximum

extent possible. -

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Also, it should be noted that the percentage of the required examination i volume with two direction coverage as identified on Request for Relief RR-A15 through RR-A22 is based on the axial scan " approaching the weld from opposite directions." The transverse to weld, (clockwise and counter-clockwise) examinations are not included in Request for Relief RR-A15

] through RR-A22 based on the following:

. Relief is not required based on using Code Case N-460, which allows a reduction in coverage for a particular weld previded it is less than 10%.

NRC Reauest 2C) For Requests for Relief RR-16, RR-A18, RR-A19, RR-A20, RR-A21 and RR-A22, provide a detailed technical discussion, including drawings if necessary, describing the component and the factors limiting examination.

Considering that the coverage achieved was low for each of these requests (e.g., <50%), describe how reasonable assurance of continued structural integrity will be provided for the subject welds.

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, R:spois2 to Requ:st F:r Additicnal Infcreaticn 3

. Thini 10-Ysar Intarval Ins:rvica Inspectien Program Plan and Ass:ciated

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Requests For Relief Dated December 31,1996 (TAC No. M96210)

Licensee's Reply:

RR-16 " Reactor Pressure Vessel Closure Head - Head to Flange Weld" (Weld Number 806-2).

Due to the component design configuration (Reference Drawing E-201-806-4) relating to the weld and flange proximity, the required volumetric examination is limited as identified on the Request for Relief. Also, compliance with the exact Section XI required inspection would necessitate a redesign of the closure head. Even after a redesign, complete compliance with the requirements of Section XI probably could not be achieved.

Examination of this weld to the maximum extent possible along with the pre-startup hydrostatic test, should provide reasonable assurance of continued structural integrity. {

1 RR-A18 " Reactor Vessel Closure - Nozzle to Head Welds" l (Weld Number (s): 807-2A, 807-2B, 807-3, 807-1A and 807-18)

(Reference drawing: E-201-806-4 and E-201-807-4) l l

RR-A19 " Steam Drum - Steam Outlet Nozzle to Shell Welds"  !

(Weld Number (s): D-1, D-2, D-3 and D-4)

(Reference drawing: E-230-101-9)

RR-A20 Emergency Condenser System - Nozzle to Shell Welds" (Weld Number (s): 103N, 103S, 104N and 104S)

(Reference drawing: 132-533C)

RR-A21 " Clean-up Demineralizer Tank - Nozzle to Shell Welds" (Weld Number (s): 212, 213, 214 and 215)

(Reference drawing (s): Y30-4858-1 and Y30-4858-3)

RR-A22 " Clean-up Regenerative Heat Exchanger - Nozzle to Shell Welds" (Weld Number (s)

A-7, B-8, C-8 and D-7) l (Reference drawing (s): DM-86366)

Based on a review of the drawings and past examination data, the code required l l axial (approaching the weld from opposite directions) examinations are ,

l limited. i 1

[ The limitations for these examinations are based on the following:

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RR-A18: Adjacent Nozzles, insulation lugs and nozzle configuration l

RR-A19: Insulation lugs and nozzle configuration RR-A20 Lifting lugs and nozzle configuration RR-A21: Nozzle configuration RR-A22: Support lugs and nozzle configuration.

Providing access to obtain the required examination coverage would require design modifications. Also, even after design modifications, complete compliance with the requirements of Section XI probably could not be achieved.

,' R2sponsa to Requ:st Fcr Additional Infctuatien 4

. Thirti 10-Ycar Intsrval Inssrvica Inspecticn Progran Plan and Asstciated Requests For Relief Dated December 31,1996 (TAC No. N96210) i Examination of the subject nozzle welds to the maximum extent possible, along with the pre-startup hydrostatic test, should provide reasonable assurance of continued structural integrity.

NRC Reauest:

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20) Provide a listing of the specific welds included in each of Requests for Relief RR-A18 through RR-A22.

Licensee's Reolv:

The specific welds associated with Request for Relief RR-A18 through RR-A22 are identified below.

RR-A18, Weld (s) 807-1A (3"), 807-1B (3"), 807-2A (10"), 807-2B (10") and 807-3 (10")

RR-A19, Weld (s) D-1 (8"), D-2 (8"), D-3 (8") and D-4 (8")

RR-A20, Weld (s) 103N (6"), 103S (6"), 104N (4") and 104S (4")

RR-A21, Weld (s) 212 (3"), 213 (3"), 214 (2") and 215 (2")

RR-A22, Weld (s) A-7 (3"), B-8 (3"), C-8 (3") and D-7 (3")

NRC Reauest:  ;

i 2E) In accordance with 10 CFR 50.55a(c)(3),10 CFR 50.55a(d)(2), and 10 CFR 50.55a(e)(2), ASME Code Cases may be used as alternatives to code requirements. Code Cases that the NRC has approved for use are listed in Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, with any additional conditions deemed necessary by the NRC. Code Cases not referenced in Regulatory Guide 1.147 may be adopted only if authorized by the NRC on a case by case basis. In some cases, use of unapproved Code Cases may be acceptable for use when certain conditions are included. To ensure consistent implementation, ifcensees proposing the use of currently unapproved Code Case (s), must commit to such conditions, if applicable.

In Request for Relief RR-A23, the Ifcensee has proposed to implement the alternatives contained in ASME Code Case N-522, Pressure Testing of Containment Penetration Piping for Class 2 containment penetrations associated with non-safety class systems. This Code Case may be l considered acceptable for use with the following conditions: i a) The leak test is performed at the peak calculated containment design l

pressure; and b) A test procedure is used that provides for detection and location of through-wall leakage in the pipe segments that are being tested.

! In order to authorize the proposed alternative, incorporation of the above

conditions into Request for Relief RR-A23 is necessary. Confirm that the conditions stated above will be met.

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, R:spons2 to Requ2st Fer Additicnal Infernatien 5

, , Thini 10-Yzar Intsrval Irsirvice Inspectien Program Plan and Ass:clated Requests For Relief 3ated December 31, 1996 (TAC Mo. M96210)

Licensee's Reolv:

The proposed alternative examination based on following the guidance of  !

Code Case N-522 for pressure testing of safety class 2 containment penetrations associated with non-safety class systems identified in Relief l Request RR-A23 will be implemented at the Big Rock Point Plant as follcws:

a) All leak tests are performed at or above the peak calculated containment design pressure;  ;

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' b) Big Rock Point's 10 CFR 50, Appendix J testing is performed by plant '

auxiliary .s erators (A0's). Big Rock Point certifies the A0's as VT-2 examiners in accordance with Section XI. Therefore, Appendix J testing is performed by personnel trained to recognize unacceptable i leakage from a pressure boundary.

c) The techniques identified in the Big Rock Point test procedure provide for the detection of through-wall leakage. Also, if the test results ,

are determined to be unacceptable, the location of through-wall leakage is determined by supplemental testing. '

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ATTACHMENT 2 CONSUMERS POWER COMPANY i

BIG ROCK POINT PLANT i DOCKET 50-155 l

60 DAY REPLY TO A REQUEST FOR ADDITIONAL INFORMATION REGARDING THE BIG ROCK POINT PLANT THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN ASSOCIATED REQUESTS FOR RELIEF.

DRAWINGS Submitted February 19, 1997 l

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