ML20235G806

Summary of 870715 Meeting W/Util,Bechtel & Gao Re Main Steam Support Adequacy & Main Feedwater Pipe Thinning.List of Attendees & Util Presentation Encl

ML20235G806
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	09/25/1987
From:	Chan T Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-65726, TAC-65727, NUDOCS 8709300229
Download: ML20235G806 (39)

Text

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1 SEP 2 51987 J

i Docket No.: 50-344 LICENSEE: Portland General Electric Company (PGE)

FACILITY: Trojan Nuclear Plant

SUMMARY

OF JULY 15, 1987 MEETING ON MAIN STEAM SUPPORT ADEQUACY AND MAINFEEDWATERPIPETHINNING(TACNOS.65726and65727)

On July 15, 1987, the staff met with representatives of and consultants for PGE to 1) discuss inspection observations and pipe replacement effort related to observed pipe thinning in the feedwater system, and 2) discuss the results of the pipe support design verification effort that resulted from concerns regarding main steam support adequacy. A list of attendees is contained in.

Feedwater Pipe Thinning During the 1987 refueling outage, while performing inspection of the feedwater piping in the vicinity of the flow venturi, portions of safety-related feedwater piping were observed tn have thinned to wall thicknesses below the minimum required by the ASME Code. Discussions of this issue centered on the expanded inspection effort, observed thinning, locations of thinning, and locations of replaced piping. PGE stated that the preliminary assessment as to the cause of the thinning was erosion / corrosion. Although much of the thinning occurred in fittings, thinning was also observed in straight sections of pipe. Due to the " tiger striped" nature of thinning in the straight pipe, it was thought that corrosion played a minimal role there.

PGE had not yet completed their detailed metallurgical evaluation of any pipe section, but did commit to provide the staff with their results once the evaluation was complete.

PGE stated that thinning was also observed in the nonsafety-related portion of the feedwater system, with the most severe degradation occurring immediately downstream from the main feedwater pump discharge.

i PGE had instituted an erosion / corrosion inspection program in order to detect potential pipe wall thickness degradation, based upon EPRI guidelines.

Although many of the observed thinning locations were predicted by the EPRI guidelines, PGE stated that the EPRI guidelines were not able to predict thinning in the straight piping.

PGE's presentation handout on this issue is included as Enclosure 2.

8709300229 870925 PDR ADOCK 05000344 P

PDR

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1 Pipe Support Desian Verification In early June 1987, while investigating a potential nonconformance of a support on the main steam (MS) system, PGE discovered that the design requirements for 14 main steam supports specifically installed for turbine trip load considerations, were inadequately specified in that the design calculations did not include the turbine trip dynamic loads. This discovery was made as a result of a PGE/Bechtel design verification of the MS supports.

Region V and NRR audited the PGE/Bechtel verification effort at the Bechtel-San Francisco office on June 22 - 23, 1987. During this audit, ten concerns were expressed, for which responses were provided informally to the staff during and following the audit. These concerns and the corresponding responses formed the basis of the staff's July 9, 1987 letter which requested information regarding the adequacy of safety related pipe support design and analyses, pursuant to 10 CFR 50.54(f).

PGE responded to the staff's 10 CFR 50.54(f) request by letter dated July 10, 1987. This letter included as part of its response, 1) responses to the ten staffconcernspreviouslyprovidedinformally,and2)anactionplanwhichwas developed at the time the design discrepancy was discovered. This letter provided the background for this discussion.

PGE opened the presentation of their verification program with a discussion regarding the observed nonconformance of main steam support SS-81.

It was through the evaluation of the adequacy of this support, that the design adequacy of the other main steam supports became suspect. As a result of their review, PGE stated that the deficiency was limited only to 14 main steam supports added in 1975 for turbine trip loads, and that the associated design i

effort was confined only to the Bechtel Civil Engineering Group during this particular time period.

Of the 14 MS turbine trip load supports, 10 supports did not satisfy the Upgraded Final Safety Analysis Report (UFSAR) acceptance criteria when subjected to the original design loads. Of these 10 supports, 7 supports did not satisfy the UFSAR acceptance criteria when subjected to revised (reduced) design loads, and thus were modified to meet the criteria.

PGE also stated that the review of the supports was expanded to include the remaining supports in the main steam system (50), all other civil-designed pipe supports (339), and all safety-related vendor designed pipe supports with dynamic loads, i.e., pressurizer relief valve discharge, and Auxiliary Feed Waterpumpsteamsupply(76). All of these supports were found to have satisfied or were expected to satisfy (following load confirmation from Westinghouse), the UFSAR criteria. For this reason, PGE felt that the design problem had been identified, adequately bounded and resolved, and that the MS system would have been operable.

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(*

o 1 l-Bechtel provided a discussion regarding the division of responsibility for pipe support design between Bechtel and vendor. Bechtel also presented reasons for the absence of. original strength calculations for the supports. During discussion of the technical execution of the verification program, interest centered around the use, incorporation, and comparison of loads specified by piping isometrics to those load specified by the support drawings. Discussion also focused on the threshold at which a change in load as specified in a piping isometric would require a review of the support's capability, and the mechanism by which that review would be initiated.

The staff had remaining concerns regarding, 1) the assurance that all civil-designed supports had been identified and that the problem was limited to Bechtel-Civil, and 2)~ completeness of verification documentation. The staff refrained from concluding the adequacy of the support verification effort pending the confirmation of loads by Westinghouse for 33 supports, and the results of the staff audit of the licensee's verification effort to be held at the Bechtel-San Francisco office, July 21 - 23, 1987. contains PGE's presentation handouts on this issue.

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

Enclosures:

As stated cc w/ enclosures:

See next page DISTRIBUTION iDocket, File; EJordan NRC & L PDRs JPartlow PD5 Reading ACRS(10)

TChan T0 Martin-ED0 Jtee MRJohnson-EDO GKnighton OGC-Bethesda PDV/PM P

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TChan:cw CAni ton 09/ /87 09/ g37

Mr. David W. Cockfield Portland General Electric. Company Trojan Nuclear Plant CC:

Senior Resident Inspector U.S. Nuclear Regulatory Comission Trojan Nuclear Plant Post Office Box 0

' Rainier, Oregon 97048 Michael J. Sykes, Chaiman Board of County Commissioners Columbia County St. Helens, Oregon 97501 Mr. David Kish Oregon Department of Energy Labor and Industries Building Room 111 Salem. Oregon 97310 Regional Administrator, Region V U.S; Nuclear Regulatory Comission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 I

7 e

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~ $

Enclosure.1 L

l List of Attendees

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July 15, 1987 Feedwater Pipe Thinning and Support Design Verification NRC PGE BECHTEL' L. Shao C. Yundt R. Fosse J. Richardson-T. Walt K. Burrowes L. Marsh T. Bushnell M. Rudicki J. Crews A. Roller W. White S. Hou.

D. Swan L. Memula T. Chan R. Mitchell P..T.Kuo D. Bjorkbom C. Cheng W.-Hazelton R. Kiessel GA0

' M. Vagins P. Wu R. Coleman C. McCracken W. McDowell V. Ferrarini, EAS G. DeGrassi, BNL

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i ENCLOSURE 2 TROJAN NUCLEAR PLANT 1987 i

FEEDWATER PIPING EROSION - CORROSION PROGRAM l

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1 EVALUATION OF 1987 DATA e

Determine wear allowances on piping components, using baseline data for new replacement fittings and pipe sections e

Select a sample of the replacement components to examine in 1988 to establish erosion / corrosion rates Select a sample of components not replaced in 1987 e

to reexamine in 1988 to establish actual erosion /

corrosion rates e

Calculate erosion / corrosion rates, using the EPRI CHEC Program, and calculate remaining time to reach minimum wall thickness (reexamine in 1988 if less than 2 years)

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PROGRAM ENHANCEMENTS Develop definitive guidance on the selection e

of piping for inspection and on sample size expansion Standardize ultrasonic thickness measurement e

and recording techniques Develop definitive guidance on data evaluation e

(EPRI CHEC Program)

Establish an erosion / corrosion data base with e

each fitting, pipe section, and weld uniquely identified

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DISCOVERY OF PROBLEM - T. E. BUSHNELL, CIVIL ENGINEERING.

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CHEMICAL AND VOLUME CONTROL (8)

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PRESSURIZER SPRAY (3)

RESIDUAL HEAT REMOVAL (7)

REACTOR COOLANT PUMP SEAL WATER (7)

SAFETY-RELATED PIPE SUPPORT ANCHORAGES AND STRUCTURAL MEMBERS

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COMPOWENT COOLING WATER SYSTEM (18)

PRESSURIZER RELIEF AND SAFETY VALVE (26)

PRESSURIZER SPRAY (20)

REACTOR COOLANT INSTRUMENTATION (49)

REACTOR COOLANT PUMP SEAL WATER (37) e REACTOR COOLANT SYSTEM DRAIN (8)

RESIDUAL HEAT REMOVAL SYSTEM (28)

SAFETY INJECTION SYSTEM (33)

STEAM GENERATOR BLOWDOWN AWD SAMPLE SYSTEM (12) 1

TURBINE BUILDING PIPE SUPPORT STRUCTURES TYPICAL

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MAIN STEAM LINES TO TURBINE-DRIVEN AFW PUMP (16)

DYNAMIC LOADS INCORPORATED IN DESIGN i

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23 DESIGNED BY civil SAilSFACTORY FOR REVISED LOADS 7 DESIGNED BY CIVIL WERE MODIFIED TO MEET REVISED DESIGN LOADS ALL OTHER PIPE SUPPORTS WITH CIVIL DESIGN 33/33 SAFETY-RELATED PIPE ANCHORS SATISFACTORY (SUBJECT TO LOAD CONFIRMATION) 265/265 SAFETY-RELATED SNUBBER / RESTRAINT SUPPORTS SATISFACTORY j

I 41/41 NON SAFETY-RELATED TURBINE BUILDING PIPE SUPPORT STRUCTURES SATISFACTORY 1

VENDOR-DESIGNED PIPE SUPPORTS WITH DYNAMIC LOADS 76/76 SATISFACTORY l

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