ML20154N028
| ML20154N028 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/25/1988 |
| From: | Mcneil S Office of Nuclear Reactor Regulation |
| To: | Tiernan J BALTIMORE GAS & ELECTRIC CO. |
| References | |
| TAC-67094, TAC-67095, NUDOCS 8806020163 | |
| Download: ML20154N028 (5) | |
Text
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May 26, 1988 Docket Nos. 50-317 DISTRIBUTION and 50-318
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0GC-WF Mr. J. A. Tiernan SVarga EJordan Vice President-Nuclear Energy BBoger
' JPartlow Baltimore Gas and Electric Company CVogan ACRS(10)
P.O. Box 1475 SMcNeil
' Baltimore, Maryland 21203
Dear Mr. Tiernan:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - PROPOSED SECOND 10-YEAR INSERVICE INSPECTION PROGRAM (TACS 67094 and 67095)
We have detemined that additional information is necessary to facilitate our review of your proposed inservice inspection (ISI) program plan as provided in your January 14, 1988 submittal. The request for additional information is enclosed.
Please respond within 60 days of the date of issuance of this letter.
If your are unable to respond within this period please notify us of your intended schedule within 35 days of this letter's issuance.
This request for information affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Briginalsun.,5,,
1 Scott Alexander McNeil, Project Manager Project Directorate I-1 Division of Reactor Projects, I/II L
1
Enclosure:
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As stated cc: see next page PDI PDI-1J4M PDI-1 CVogan SMcNeil: dig RCapra 5/$88 5/)f/88 5/25/88
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Mr. J. A. Tiernan Baltinore Gas & Electric Company
.Calvert Cliffs Nuclear Power Plant cc:
Mr. John M. Gott, President Regional Administrator, Region I Calvert County Board of U.S. Nuclear Regulatory Comnission Commissioners 475 Allendale Road Prince Frederick, Maryland 20768 King of Prussia, Pennsylvania 19406 D. A. Brune, Esq.
General Counsel Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Mr. Jay E. Silberg, Esq.
Shaw, Pittman, Potts and Trowbridge 1800 M Street, NW Washington, DC 20036 Mr. M. E. Bowman, General Supervisor
' Technical Services Engineering Calvert Cliffs Nuclear Power Plant MD Rts 2 & 4, P. O. Box 1535 Lusby, Maryland 20657-0073 Resident Inspector c/o U.S. Nuclear Regulatory Commission P. O. Box 437 Lusby, Maryland 20657-0073 Bechtel Power Corporation ATTN: Mr. D. E. Stewart Calvert Cliffs Project Engineer 15740 Shady Grove Road Gaithersburg, Maryland 20760 Combustion Engineering, Inc.
ATTN: Mr. W. R. Horlacher, III Project Manager P. O. Box 500 1000 Prospect Hill Road Windsor, Connecticut 06095-0500 Department of Natural Resources Energy Administration, Power Plant Siting Program ATTN: Mr. T. Magette Tawes State Office Building Annapolis, Maryland 21204 i
1
RE00EST FOR ADDITIONAL INFORMATION INSERVICE INSPECTION PROGRAM PLAN SECOND TEN-YEAR INTERVAL BALTIRDRE GAS AND ELECTRIC COMPANY, CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-317 AND 50-318 1.
Scope / Status of Review Throughout the service life of a water-cooled nuclear power facility, 10 CFR 50.55a(g)(4) requires that conponents (includino supports) which are classified as American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Class 1, 2, or 3 meet the requirements, except design and access provisions and preservice examination requirements, set forth in the ASME Code Section XI, to the extent practical within the limitations of design, geometry, and materials of construction of the components.
10 CFR 50.55a(g)(4) also requires that inservice examinations of components and systen pressure tests conducted during successive 120-month inspection intervals shall comply with the requirements in the latest edition and addenda of the Code incorporated by reference in 10 CFR 5J.55a(b) on the date 12 months prior to the start of the 120-month inspection interval, subject to the limitations and modifications listed therein.
The components (including 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 listed therein.
Based on the start date of April 1,1987 for the second 10-year interval, the Inservice Inspection (ISI) Program Plan has been prepared to meet the requirements of the 1983 Edition, Sumer 1983 Addenda (83S83) of the ASME Code Section XI except that the extent of examination for Code Class 1 piping welds has been determined by the 1974 Edition through Sumer 1975 Addenda (74S75) and the extent of examination for Code Class 2 piping welds has been determined by ASME Code Case N a08, "Alternative Rules for Examination of Class 2 Piping."
As reouired by 10 CFR 50.55a(g)(5), if the licensee determines that certain Code examination requirements are impractical and relief is requested, the licensee shall submit inforr: tion to the Nuclear Regulatory Comission (NRC) to support the determination.
l The staff has reviewed the available information in the Calvert Cliffs l
Nuclear Power Plant, Units 1 and 2, Second 10-Year Interval ISI Program l
Plan, submitted January 14, 1988, and the requests for relief from the ASME Code Section XI recuirements which the licensee has determined to be l
impractical.
2.
Additional Information/ Clarification Required l
Based on the above review, the staff has concluded that the following l
information and/or clarification is required in order to complete the l
review of the ISI Progran Plan:
1 l
l
. A.
Provide the staff with the Boundary Diagrams which define the ASME Code Class 1, 2, and 3 boundaries for the Units 1 and 2 in the ISI Program Plan.
B.
Provide isometeric and/or component drawings showing the welds, l
components, and supports which Section XI of the ASME Code requires to be examined during the second 10-year interval.
C.
Provide the staff with an itemized listing of the welds / components subject to examination during the second 10-year interval. The requested listing, along with the isometric drawings, will permit the staff to determine if the extent of ISI examinations meets the applicable Code reouirements.
D.
Provide a list of the ultrasonic calibration standards being used during the second 10-year interval at both Units 1 and 2.
This list should include the calibration standard identifications, material specifications, and sizes.
E.
Provida a list of the nondestructive examination procedures that are being used during the second inspection interval, including identifications, titles, and general descriptions of the components to which each procedure is applicable-F.
Augmented examinations have been established by the NRC when added assurance of structural reliability is deemed necessary. Examples of documents which require augmented examinations are:
(1) High Energy Fluid Systems, Protection Against Postulated Piping Failures In Fluid System Outside Containment, Branch Technical Position ASB 3-1; and (2) Regulatory Guide 1.150, Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations.
Address the degree of compliance with these and any other augmented examinations which may have been incorporated in the Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Second 10-Year Interval Inservice Inspection Program Plan.
G.
Request for Relief No. 1:
Relief is requested from performing the ASME Code-required surface examination of the reactor pressure vessel norzle-to-pipe transition welds. The licensee has proposed performing 45-degree shear-wave ultrasonic examination of the outside surface using mechanized ultrasonic techniques from the inside of the pipe. The licensee reports that this method of examination has been qualified for the detection of unacceptable outside surface flaws through the use of a mock-up with induced cracks ranging from 1/2 the maximum to the maximum allowable Code flaw depth.
j
O
. The proposal could be considered acceptable provided that the remote volumetric examination includes the entire weld volume and heat-affected zone instead of only the inner one-third of the weld as required by the Code. Provide a discussion of this condition.
H.
Request for Relief No. 4:
Relief is requested from performing the Code-required hydrostatic pressure test of the Class 2 piping from the High Pressure Safety Injection (HPSI), Auxiliary HPSI, and Low Pressure Safety Injection MOVs to the Reactor Coolant System.
It is proposed that, in lieu of the Code requirement, hydrostatic pressure testing be performed to the Class 1 hydrostatic pressure requirenent for some of the piping. For the portions of piping that cannot be hydrostatically pressure tested, it is proposed that a leakage test be performed each refueling cycle in accordance with the Technical Specifications.
Discuss the impact of making temporary modifications to the systems which would permit pressurizing the Class 2 piping to the Code-required test pressure.
I.
With regard to examination of component supports, provide an estinate of the sample size versus the entire population, separated by Code class.
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