ML17278A902
| ML17278A902 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/10/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| References | |
| NUDOCS 8606200249 | |
| Download: ML17278A902 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 June 10, 1986 Docket No. 50-397 Mr. G.
C. Sorensen, Manager Reoulatory Programs Washington Public Power Supply System P.O.
Box 968 3000 George Washington Way Richland, Washington 99352
Dear Mr. Sorensen:
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DISTRIBUTION:
cket Files NRC PDR Local PDR PRC System P hVD Subiect:
WNP-2 Ten Year Interval Inservice Inspection Program Reauest for Additional Information The staff of the Nuclear Regulatory Commission is reviewing and evaluating the Inservice Inspection Prooram for the first ten-year interval of operation for the WPPSS Nuclear Proiect No. 2.
On the basis nf this review, we find that we need additional information as identified in the enclosed Request for Additional Information.
We estimate that a minimum of six months after receiot of the in<ormation will be required for preparation of the safety evaluation so your prompt. response will be helpful and appreciated.
Sincerely, Elinnr G. Adensa irector BWR Project Directorate No.
3 Division of BWR Licensing
Enclosure:
As stated cc:
See next page DZSEGHjg i
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Mr. G.
C. Sorensen, Manager Washington Public Power Supply System WPPSS Nuclear Pro,iect No.
2 (WNP-2)
CC:
Nicholas S: Reynolds, Esq.
Bishop, Libezman,
- Cook, Purcell E Reynolds 1200 Seventeenth
- Street, N.W.
Washington, D.C.
20036 Mr. G.
E.
Doupe, Esquire Washington Public Poyer Supplv System P. 0.
Box 968 3000 George Washington Way
- Richland, Washington 99532 Mr. Curtis Eschels, Chairman Energy Facility Site Evaluation Council Mail Stop PY-11 Olympia, Washington 98504 P. L. Powell, Licensing Manaqer Washington Public Power Supply System P. 0.
Box 968, MD 956B
- Richland, Washington 99352 Mr.
W.
G.
Conn Burns and Roe, Incorporated c/o Washington Public Power Supply System P. 0.
Box 968, MD 994E
- Richland, Washington 99352 R. B. Glasscock, Director Licensing and Assurance Washington Public Power Supply System P. 0.
Box 968, MD 280
- Richland, Washington 99352 Mr. C.
M. Powers WNP-2 Plant Manager Washington Public Power Supply System P. 0.
Box MD 927M Richland, Washington 99352 Regional Administrator, Region V
U.S. Nuclear Regulatorv Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 REQUEST FOR ADDITIONAL INFORMATION FOR WASHINGTON PUBLIC POWER SlIPPLY SYSTEM WPPSS NUCLFAR PLANT NO.
2 DOCKET NUMBER 50-397 Request for Additional Information - First Interval Inservice Inspection Program 1.
Scope/Status of Review 10 CFR 50.55a(g)(4) reouires that throughout the service life of a water-cooled nuclear power facility, components (includinq supports) which are classified as ASME Code Class 1, Class 2, and Class 3 meet the requirements, except design and access provisions and preservice examination requirements, set forth in ASME Code Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components,"
to the extent practical within the limitations, of
- design, geometry, and materials of construction of the components.
This section of the regulations also requires that inservice examinations of components and system pressure tests conducted during the initial 120-month inspection interval shall comply with the requirements in the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the date of issuance of the operatinq license, subiect to the limitations and modifications listed therein.
The components tincluding supports) may 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 the limitations and modifications list'ed therein.
Based on the Operatinq License date of December 20, 1983, the Licensee has prepared the ISI Program in compliance with the requirements of the, 1980 Edition, Winter 1980 Addenda (1980W80) of ASME Code Section XI:except that the Licensee has updated the following to later Editions and Addenda:
- 1) IWA-2300(a)(l) upqraded to 1983W83 2)
Code Category C-F upgraded to 1983W83
- 3) IWF-3400 upgraded to 1980W81
=10CFR'50.55a(g)(5) requires that if the licensee determines that certain code examination requirements are impractical and relief is requested, the licensee shall:submit information to the commission to support that determi'nat'ion.
The staff has reviewed the available information in the WNP-2 Inservice Inspection Program Plan submitted May 29, 1985 and the requests for relief from ASME Code Section XI requirements which the Licensee has determined to be impractical to perform at WNP-2.
2.
Staff Evaluation The staff has concluded that the following information and/or clarification is required in order to complete the review of the Inservice Inspection Program Plan:
A.
In Section 14.0, "Meld and Component Identification Diagrams", of the ISI Program Plan, the Program Plan and Schedule Tables list the follnwing welds as being inspected to Table INC-2500-1, Examination Category C-F-7, Item C5.51 0f the Code with only surface examination being required:
WELD NljMBERS 18RHR(20)A-1 18RHR(20)A-2 18RHR(20)A-3 18RHR(20)A-4 18RHR(20)B-1 18RHR(20)B-2 18RHR(20)R-3 18RHR(70)B-4 To satisfy the inspection requirements of Item C5.51, these welds require both surface and volumetric examinations.
Clarification of this issue" is needed.
B.
Isometric Drawing No. HPCS-202-4 is missing from the ISI Program Plan.
Provide the staff with a copy of this drawing.
C.
In Relief Request ISI-2-001, relief from performing a 1001 volumetric, examination on 13 Class 1,
ASME Section XI, Category B-A, pressure retaining welds in the reactor pressure vessel was requested on the basis of partial inaccessibility of the welds due to plant desion.
For the proposed partial volumetric examination of these welds, the Licensee should define the percentage of each weld to be examined.
D.
Relief Request ISI-2-002 requests use of a schedule 40 calibration block instead o< a schedule 80 calibration block for inspectinn nf Reactor Recirculation 4-inch decontamination connections (8 welds, Examination Cateqory B-J, Item B9. 11).
The staff requests a copy of the procedure that will be used for calibration of the inspection equipment using the substitute calibration block.
Specifically, what ad,iustments are made'or the difference in wall thickness between the schedule 40 calibration block and the schedule 80 connections and how is the Code required examination volume coverage verified?
Justify the determination of impracticality for the use of the schedule 80 calibration block.
The Licensee should provide the above requested information and/or clarifica-tions as soon as possible so that the review of the Inservice Inspection Program Plan can be completed.
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