ML20207H256

Forwards Request for Addl Info in Order to Complete Evaluation of Trojan Nuclear Plant Inservice Insp Program for Second 10-yr Interval

ML20207H256
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	08/15/1988
From:	Chan T Office of Nuclear Reactor Regulation
To:	Cockfield D PORTLAND GENERAL ELECTRIC CO.
References
TAC-63974, NUDOCS 8808240418
Download: ML20207H256 (8)

Text

f August 15, 1988 Docket No.: 50-344 DISTRIBUTION' Docket File NRC & Local PDRs PDS Reading GHHolahan Mr. David W. Cockfield JLee-Vice President, Nuclear TLChan Portland General Electric Company 0GC (for info only) 121 S.W. Salmon Street EJordan Portland, Oregon 97204 BGrimes ACRS(10)

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - INSERVICE INSPECTION PROGRAM; 2ND TEN YEAR INTERVAL, TROJAN NUCLEAR PLANT (TAC N0. 63974)

By letter dated November 14, 1986 Portland General Electric Company (PGE) submitted Topical Report PGE-1049, "Trojan Nuclear Plant Inservice Inspection (ISI) Program for the Second 10-Year Interval."

Based on our review of the submittal, we find that additional information is needed in order to complete our evaluation. We ask that the information.

requested by the Enclosure be provided within 45 days from receipt of this letter, or provide an alternate schedule for doing so within 15 days.

The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, original signed by Terence L. Chan, Project Manager Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated cc: w/ enclosure See next page f4 DRSP/PD5

~j VD:PDS OFol l g TLChan:dr ighton 8//[/88 8 /88 0FFICIAL RECORD COPY 0

a i.

- i August 15, 1988 j

.s Docket No.: 50-344 DISTRIBUTION Docket File NRC & Local PDRs PD5 Reading GMHolaban l Mr. David W. Cockfield JLee l Vice President, Nuclear TLChan l Portland General Electric Company OGC (for info only) 121 S.W. Salmon Street EJordan Portland, Oregon 97204 BGrimes ACRS (10) I

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - INSERVICE INSPECTION PROGRAM; 2ND TEN YEAR INTERVAL, TROJAN NUCLEAR PLANT (TAC NO. 63974) ,

By letter dated November 14, 1986, Portland General Electric Company (PGE) submitted Topical Report PGE-1049, "Trojan Nuclear Plant Inservice Inspection l (ISI) Program for the Second 10-Year Interval."

Based on our review of the submittal, we find that additional information is l needed in order to complete our evaluation. We ask that the information  !

requested by the Enclosure be provided within 45 days from receipt of this letter, or provide an alternate schedule for doing so within 15 days.

The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely. l l

original signed by Terence L. Chan, Project Manager  !

Project Directorate V i Division of Reactor Projects - III, IV, Y and Special Projects  !

Office of Nuclear Reactor Regulation

Enclosure:

As stated 1 cc: w/ enclosure  !

See next page DRSP/PD5

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SP/D:PD5 TLChan:dr ghton  !

i 8//[/88 8/ /88 '

0FFICIAL RECORD COPY 1

o reso 8 '

'o Eg. UNITED STATES E'~ '

g NUCLEAR REGULATORY COMMISSION r

..  :; y; WASHINGTON,0. C. 20555 k+...+,/ August 15, 1938 Docket No.: 50-344 Mr. David W. Cockfield Vice President, Nuclear Portland General Electric Company 121 S.W. Salmon Street Portland, Oregon 97204

SUBJECT:

RE0 VEST FOR ADDITIONAL INFORMATION - INSERVICE INSPECTION PROGRAM; 2ND TEN YEAR INTERVAL, TROJAN NUCLEAR PLANT (TAC NO. 63974)

By letter dated November 14, 1986, Portland General Electric Company (PGE) submitted Topical Report PGE-1049, "Trojan Nuclear Plant Inservice Inspection (ISI) Program for the Second 10-Year Interval."

Based on our review of the submittal, we find that additional information is i needed in order to complete our evaluation. We ask that the information requested by the Enclosure be provided within 45 days from receipt of this letter, or provide an alternate schedule for doing so within 15 days.

The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Since ly. -

l M .

l Terence L. Chan, Project Manager l Project Directorate V l Division of Reactor Projects - III.

IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated cc: w/ enclosure See next page l

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l'r. David W. Cockfield Portland General Electric Company Trojan Nuclear Plant ec:

Senior Resident inspector U.S. Nuclear Regulatory Commission Trojan Nuclear Plant Post Office Box 0 Rainier, Oregon 97048 Mr. Michael J. Sykes, Chairman Board of County Commissioners Columbia County St. Helens, Oregon 97501 Mr. William T. Dixon Oregon Department of Energy Salem, Oregon 97310 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 t' aria Lane, Suite 210 Walnut Creek, California 94596

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.. PORTLAND GENERAL ELECTRIC COMPANY 1

TROJAN NUCLEAR PLANT i

! DOCKET NUMBER 50 344

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Raouest for Additional Infomation - Second 10-Year Interval Inservice  ;

{ Insoection Procram Plan e

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1. Scone / Status of Review s

Throughout the service life of a water-cooled nuclear power facility, '

10 CFR 50.55a(g)(4) requires that components (including supports) which '

i are classified as American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Class 1, Class 2, and Class 3 meet the .

requirements, except design and access provisions and preservice

!, examination requirements, set forth in the ASME Code Section XI, "Rules  !

{ for Inservice Inspection of Nuclear Power Plant Comporents," to the ,

j extent practical within the limitations of design, geometry, and j l materials of construction of the components. This section of the -

) regulations also requires that inservice examinations of components and  !

l system pressure tests conducted during the successive 120 month .,

I inspection interval shall comply with the requirements in the latest 1 l

edition and addenda of the Code incorporated by reference in  !

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10 CFR 50.55a(b) on the date 12 months prior to the start of the ,  ;

j 120 month inspection interval, subject to the limitations and j

j modifications listed therein. The components (including supports) may i l meet requirements set forth in subsequent editions and addenda of this -

) Code which are incorporated by reference in 10 CFR 50.55a(b) subject to l

the limitations and modifications listed therein. Based on the start ,

date of May to,1986 for the second 10-year interval, the Inservice Inspection (ISI) Program Plan has been prepared to meet the requirements  ;

) of the 1983 Edition, Summer 1983 Addenda (83S83) of the ASME Code l

Section XI except that the extent of examination for Code Class 1 and Code Class 2 piping welds has been determined by the 1974 Edition 1

throughSummer1975 Addenda (74575).

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. l As required by 10 CFR 50.55a(g)(5), if the licensee detemines that '

certain Code examination requirements are impractical and relief is requested, the licensee shall submit information to the Nuclear Regulatory Comission (NRC) to support that determination.

The staff has reviewed the available infomation in the Trojan Nuclear Plant Second 10-Year Interval ISI Program H an, submitted '

November 14, 1986, and the requests for relief from the ASME Code Section XI requirements which the Licensee has detemined to be impractical.

2. Additional Information Reauired Based on the above review, the staff has concluded that the following information and/or clarification is required in order to complete the review of the ISI Program Plan:

A. Paragraph 10 CFR 50.55a(b)(2)(iv) requires that ASME Code Class 2 piping welds in the Residual Heat Removal (RHR), Emergency Core Cooling (ECC), and Containment Heat Removal (CHR) systems shall be examined. These systems should not be completely exempted from

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inservice volumetric examination based on Section XI exclusion criteria contained in IWC-1220.

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Based on the 74S75 Section XI exclusion criteria contained in IWC-1220(a), the Trojan Nuclear Plant Second 10-Year Interval ISI -

Program, Section 4.2.1 exempts components in the Ri!R, ECC, and CHR systems (i.e., Safety Injection System, Chemical and Volume Control System) from inservice examinations when both the design pressure and temperature are equal to or less than 275 psig and 200'F, respectively. To satisfy the inspection requirements of General Design Criteria 36, 39, 42, and 45, the inservice inspection program

must include volumetric examination of a representative sample of i

welds in the RHR, ECC, and CHR systems. The staff points out that

later editions and addenda of the Code do not pemit the '

, temperatura/prassure exclusion for these systems. Verify that the 2

.' temperature / pressure exclusion will not be used and that the ISI Program Plan will be revised to include examinations for these systems, as applicable.

Item (4) on page 31 of the ISI Program Plan exempts all Class 2 piping in the Containment Spray System based on the 74S75 Section XI exclusion criteria contained in IWC-1220(b). Since tha Containment Spray System is part of the CHR System, it should not be completely exempted from inservice volumetric examinations based on the l

exclusioncriteriAcontainedinIWC1220(b). The staff has l previously determined that a 7.5% augmented volumetric sample constitutes an acceptable resolution at similar plants. Verify that l volumetric examination will be perfonned on at least a 7.5% sample of the Class 2 piping welds in the Containment Spray System.

l B. Provide the staff with the Boundary Diagrams which define the ASME Code Class 1, Class 2, and Class 3 boundaries for the systems in the Trojan Nuclear Plant Second 10-Year Interval ISI Program Plan. t l

C. Provide the staff with an itemized listing of the components subject '

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l to examination during the second 10-year interval. The requested I 1

listing will permit the staff to determine if the extent of ISI

examinations meets the applicable Code requirements.

4 D. Provide isometric and/or component drawings showing the welds, components, and supports which Section XI of the ASME Code requires be examined, i

j E. Provide a list of the ultrasonic calibration standards being used during the second 10-year interval ISI at Trojan Nuclear Plant.

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l This list should include the calibration standard identifications, i material specifications, and sizes.

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j F. Relief Request No. 3.3.2: With regard to the bottom head nozzle inner radius sections on the steam generators, relief is requested from performing the Code required volumetric examination because of '

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,. the as cast condition of the outer surface and the clad inner j surface of the bottom head. If relief from examining the nozzle inner radius sections is to be considered, sufficient technical justification must be provided. What attempts have been nade to ,

obtain construction drawings, to select transducers, and to perform the Code required volumetric examination of the nozzle inner radius sections? If the full Code required volumetric examination cannot l be completed, describe a 'best-effort" volumetric examination that could be performed.

G. Relief Request No. 4.3.6: Discuss what efforts have been made to perform the Code-required volumetric examination of the cast regenerative heat exchanger circumferential shell welds. Has a refracted lonattudinal wave ultrasonic examination been attempted? '

The Licensee should monitor the development of new or improved examination techniques. As improvements in these areas are achieved, the staff requires that these enhanced techniques be made a part of the inservice examination requirements for the components or welds which  !

received a limited examination.

l The schedule for, timely completion of this review requires that the ~

l Licensee provide, by the requested date, the above requested information and/or clarifications with regard to the Trojan Nuclear Plant Second '

l 10-Year Interval ISI Program Plan.

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