ML20214L162

Provides Plans to Utilize Hafa Intl,Inc Instrumented Insp Technique in Check Valve Test Program at Plant for Sys Outlined in .Nrc Approved Use of Technique as Alternative Pressure Testing Method by

ML20214L162
Person / Time
Site:	Davis Besse
Issue date:	11/24/1986
From:	Williams J TOLEDO EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
1314, NUDOCS 8612020589
Download: ML20214L162 (8)

Text

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TOLEDO

%ss EDISON Docket No. 50-346 JOE WILUAMS. JR.

w u v,mm License No. NPF-3 $$$

Serial No. 1314 November 24, 1986 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz PWR Project Directorate No. 6 Division of PWR Licensing-B United States Nuclear Regulatory Commission 7ashington, D. C. 20555

Dear Mr. Stolz:

The purpose of this letter is to provide for informational purposes Toledo Edison's plans to utilize the HAFA International, Incorporated, Instrumented Inspection Technique (IIT) in a check valve test program at the Davis-Besse Nuclear Power Station, Unit No. I for those systems outlined in Serial No. 1199, dated October 18, 1985. The NRC has approved the use of the IIT as an alternative pressure testing method for the Davis-Besse Nuclear Power Station,' Unit No. 1 by letter dated November 13, 1985 (Log No.

1861).

The IIT is an alternate method for meeting the intent of ASME Section XI requirements for pressure testing, in general, of Class 1, 2, and 3 systems and components. The IIT was submitted to the NRC in Topical Report HAFA 135 (P)(A), and was approved by the NRC on November 7,1985.

IIT has the capability of obtaining reproducible data in the detection of external system leakage and intra- and intersystem valve leakage, while reducing personnel exposure to radiation and eliminating the potential for overpressurization of lower pressure rated piping and components.

This capability has been demonstrated by developmental work and inservice experience at four plants.

This program will test those check valves listed in Enclosure 1 for functional conformation at a test frequency of at least once every two years. This frequency is based on past experience of IIT testing for check valves in non-brackish water environments. The data on which this frequency is based is available on-site for review. This frequency is also based on the 1980 Edition of ASME Section XI clarification to the performance of leak testing once every two years.

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G THE TOLEDO EDISON COMPANY ED SON PLAZA 300 MAD l SON AVENUE TOLEDO. CHO 43652 l

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Docket No. 50-346 License No. NPF-3 Serial No. 1314 November 24, 1986 Page 2 As you should be aware, Topical Report HAFA 135 (P)(A) is proprietary information and it should continue to be handled as NRC " Official Use Only" information. It should not be discussed or made available to any person not requiring such information.

Very truly yours, N

JW:EC:p1f Enclosures cc: DB-1 NRC Resident Inspector NSSS Reviewers:

B. D. Liew J. Wong

. P. T. Kuo j T.-Marsh G. Johncon i

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o Docket No. 50-346 License No. NPF-3 Serial No. 1314 November 24, 1986 Enclosure 1 Check Valves Tested or To Be Tested Post November 13, 1985 at Davis-Besse Unit 1 Nuclear Power Station, Using HAFA International's Instrumented Inspection Technique (IIT)

VALVE P&ID & LOCATION

• MS726 M-003C-6(F-5)

• MS727 M-003C-6(F-9)

• MS734 M-003C-6(F-5)

• MS735 M-003C-6(F-9)

• AS274 M-003C-6(G-5)

AF1 M-006D-1(G-6)

AF2 M-006D-1(H-4)

AFIS M-006D-1(E-10)

AF16 M-006D-1(J-9)

AF19 M-006D-1(G-11)

AF20 M-006D-1 (J-11)

AF49 M-006D-1(C-5)

AF52 M-006D-1(D-6)

AF63 M-006D-1(G-8)

AF68 M-006D-1(K-6)

AF39 M-007B-2(B-12)

AF43 M-007B-2(B-3)

AF72 M-007B-2(B-10) .

AF73 M-007B-2(A-8)

AF74 M-007B-2(A-7)

AF75 M-007B-2(B-5)

FW147 M-007B-2(E-11)

FW156 M-007B-2(F-3)

RC51 M-030A-10(C-9)

MU169 M-031B-3(D-7)

CF2A M-033-45(B-3)

CF29 M-033-45(B-2)

• • CF30 M-033-45(B-3)

• • CF31 M-033-45(B-2)

DH49 M-033-45(H-2)

• • DH76 M-033-45(B-4)

• • DH77 M-033-45(C-2)

HP48 M-033-45(C-3)

HP49 M-033-45(C-2)

HP50 M-033-45(C-3)

HP51 M-033-45(C-2)

HP56 M-033-45(C-4)

HP57 M-033-45(C-4)

HP58 M-033-45(C-4)

HP59 M-033-45(C-4)

CS9 M-034-32(D-9)

CS10 M-034-32(D-9) l CC17 M-036A-0(D-5) i

'Dockht No. 50-346 License No. NPF-3 Serial No. 1314 November 24, 1986 Enclosure 1 VALVE P&ID &^ LOCATION CC18 .M-036A-0(G-5)

CC19 M-036A-0(J-5)

CC532 ~M-036A-0(F-9)

CC533 M-036A-0 (H-9)

CC91 M-036B-0(B-3)

CC530' M-036B-0(B-5).

CC531 M-036B-0(B-3)

CC549 M-036E-0(B-4)

• These valves (MS726, MS727, MS734, MS735, AS274) were tested with water to check the leak tightness of the valve. In the future, the above mentiened valves will be tested using acoustic emissions for gross leakage.

• • These valves will'still be leak tested to the frequency as specified in the Technical Specifications for pressure boundary isolation valves.

The attached drawings provide examples of the current instrument connections for several check valves tested. Details of these tests and of all other tests,.a regression analysis of the results, and acceptance criteria applied are provided in our test procedures, which are available on-site for review. 11e acceptance criteria for the check velves are based on both in:ra- and inter-system leakage considerations for the system func-tional requirements for those valves and maintenance considerations (i.e., measured leakage, while acceptable, indicates degradation is occurring and planned maintenance may be warranted).

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A = Acoustic Emission Sensor

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o bdb yCMOk mCO MMWd3 TOLEDO EDISON Docket No. 50-346 JOE WiluAMs. JR.

Senor Vce Presort-Nuoear (419] P49-2300 License No. NPF-3 i4is)24a.s223 Serial No. 1199 October 18, 1985 Director of Nuclear Reactor Regulation

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Attention: Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Licensing United States Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Stolz:

The purpose of this letter is to request Nuclear Regulatory Commission (NRC) approval to use an alternative inspection technique at the Davis-Besse Nuclear Power Station Unit I to satisfy the Inservice Pressure Testing requirements of the ASME Code,Section XI, as permitted by 10CFR50.55a(a)(3).

The details of this alternative inspection technique, Instrumented Inspection Technique (IIT), are the subject of a H.A.F.A. International, Inc., Topical Report HAFA 135(P)(A). This topical report is currently under NRC review, and based on a meeting with NRC staff personnel on September 24, 1985, it is our understanding that the topical report will be approved in the near future.

The plant systems identified below have been evaluated in accordance with Section I7 of the topical report. Based on these evaluations, it has been determined that the IIT can be implemented on the appropriate portions of I the following systems:

Main Steam Auxiliary Feedwater l Decay Heat / Low Pressure Injection ,

High Pressure Injection l Containment Spray Core Flood Component Cooling Water Service Water Station Drain Steam Generator Sampling and Blowdown l Main Feedwater Reactor Coolant f

THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. CHIO 4365?

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4 Dockst No. 50-346 Licznsa Ns. NPF-3 Serial No. 1199 October 18, 1985 Page 2 For the current Davis-Besse Unit 1 outage, we intend to implement the IIT on portions of the Core Flood, Decay Heat, Auxiliary Feedwater and High Pressure Injection systems. Although we have chosen to conduct the ASME Section XI Code " System Hydrostatic Test" of IWA-5211(d) on the NSSS portion of the Reactor Coolant System, the IIT may also be implemented selectively within that boundary.

Because we would like to implement the IIT on some of the above systems during the current outage, we request your approval by October 30, 1985.

We are available at your convenience, if needed, to discuss this matter further.

It should be noted that Toledo Edison recognizes the capability of the IIT method to determine intersystem leakage, and therefore, may opt to take credit for this method to satisfy the Inservice Testing Program and Technical Specification requirements where appropriate.

Very truly yours,

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JW/JDE/SGW/bjs cc: DB-1 NRC Resident Inspector t

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,.[nne% t UNITED STATES l

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NUCLEAR REGULATORY COMMISSION WASmNGTON, D. C. 20555 Lscensing cc: J. WMms, Je j

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Docket No. 50-346 [M.fL.MS Stewart L A. Gnme R. G. Schuerger STA. .

Mr. Joe Williams, Jr. SAR44 -

Vice President, Nuclear UOV 13 g 5J8'.

Toledo Edison Company a.ga -

Edison Plaza - Stop 712 300 Madison Avenue MM E.caba Toledo, Ohio 43652

SUBJECT:

REQUEST FOR APPROVAL TO USE AN ALTERNATIVE PRESSURE TESTING METHOD -

DAVIS-BESSE NUCLEAR POWER STATION.

By letter dated October 18, 1985 (Serial No. 1199), Toledo Edison company requested approval to use an alternative inspection method to meet the requirements of Section XI of the ASME Code for inservice pressure tests at Davis-Besse. The alternative testing method, Instrumented Inspection Technique, is described in a topical report submitted to the NRC by HAFA International Incorporated by letter dated April 4,1985 to demonstrate that the proposed alternative would provide an acceptable level of quality and safety as required by 10 CFR 50.55a(a)(3).

We have reviewed and evaluated the proposed alternative testing method as discussed in the topical report. We have determined that the alternative testing method provides added assurance of system and component structural integrity and leak tightness when compared to conventional pressure testing and is therefore an acceptable alternative. We have also determined that the small leak detection and location capabilities of the alternative method make it applicable for intersystem leakage detection, and that the four-hour hold time requirement prior to visual inspection of the systems may be reduced to two hours. We therefore approve its use as an alternative testing method as requested in your letter, incerely, ,

e ill Jo $ F. Stolz, Chief 0 rating Reactors Branch #4 Division of Licensing cc: See next page __ i S% t Log Number '

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Mr. J. Williams Davis-Besse Nuclear Power Station Toledo Edison Company Unit No. I cc:

Donald H. Hauser, Esq. Ohio Department of Health The Cleveland Electric

• ATTN: Radiological Health Illuminating Company Program Director P. O. Box 5000 P. O. Box 118 Cleveland, Ohio 44101 Columbus, Ohio 43216 Mr. Robert F. Peters ' Attorney General Manager, Nuclear Licensing Department of Attorney Toledo Edison Company General Edison Plaza 30 East Broad Street 300 Madison Avenue Columbus, Ohio 43215 Toledo, Ohio 43652 Mr. James W. Harris, Director Gerald Charnoff, Esq. Division of Power Generation Shaw, Pittman, Potts Ohio Department of Industrial Relationt and Trowbridge 2323 West 5th Avenue 1800 M Street, l'_W. P. O. Box 825 Washington, D.C. 20036 Columbus, Ohio 43216 Paul M. Smart, Esq. Mr. Harold'Kohn, Staff Scientist

. Fuller & Henry Power Siting Commission 300 Madison Avenue 361 East Broad Street P. O. Box 2088 Columbus, Ohio 43216 Toledo, Ohio 43603 Mr. Robert B. Borsum President, Board of Babcock & Wilcox Ottawa County Nuclear Power Generation Port Clinton, Ohio 43452 Division Suite 200, 7910 Woodmont Avenue Bethesda, Maryland 20814 i Resident Inspector U.S. Nuclear Regulatory Commission 5503 N. State Rou.e 2 Oak Harbor, Ohio 43449 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

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