ML20141E994
| ML20141E994 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 05/15/1997 |
| From: | Hopkins J NRC (Affiliation Not Assigned) |
| To: | Myers L CENTERIOR ENERGY |
| References | |
| TAC-M97694, NUDOCS 9705210168 | |
| Download: ML20141E994 (5) | |
Text
,
e-May 15, 1997 c
Mr.'Lew Wi Myers.-
Vice President Nuclear _ -Perry _.
Centerior Service Company P.O. Box-97, A200
! Perry, OH 44081'
SUBJECT:
l REQUEST FOR ADDITIONAL INFORMATION, PERRY NUCLEAR POWER PLANT, UNIT NO._1 (TAC NO. M97694)
Dear Mr. Myers:
By letter dated January 1, 1997, you requested approval to use American Society of Mechanical Engineers (ASME) Code Cases N-498-1, N-522, and N-546 as alternatives to the ASME,Section XI, Code requirements at the Perry Nuclear
. Power Plant. The NRC staff, with assistance from its contractor, Idaho National Engineering and Environmental Laboratory (INEEL), has performed an
. initial review of the requests and finds that we need additional information (to complete our review (see_ enclosure).
Please respond within 45 days of receiving this letter.
In addition, _to expedite the review process, please send a copy of your response to NRC's contractor, INEEL, at the following address:
Michael T. An'derson..
INEEL Research Center >
2151 North Boulevard P.O.. Box 1625' Idaho Falls, ID 83415-2209
?
Please contact me at (301) 415-3027 if 'you have -any questions.
Sincerely, Original sign'ed by:
NRC FRE CENwER CO-M' Jon B. Hopkins, Sr. Project tanager Pre 3ect Directorate m _3 Division of Reactor Projects III/IV
' Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosure:
Request for AMitional Information
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May 15,' 1997 Mr. Lew W. Myers Vice President Nuclear - Perry-Centerior Service Company-P.O. Box 97, A200 Perry, OH 44081
SUBJECT:
- . REQUEST FOR ADDITIONAL INFORMATION, PERRY NUCLEAR POWER' PLANT, UNIT NO. 1 (TAC NO. M97694)
Dear Mr. Myers:
By letter dated January 7,1997, you requested approval to use American Society of Mechanical Engineers (ASME) Code Cases N-498-1, N-522, and N-546-as
. alterna.tives to the ASME,Section XI,' Code requirements at the Perry Nuclear Power Plant.
The NRC staff, with assistance from its contractor, Idaho National Engineering and Environmental Laboratory (INEEL), has performed an initial review of the-requests and finds that we need additional information to complete our review (see enclosure).
Please respond within 45 days of receiving this letter.
In addition, to expedite the review process, please send a copy of your response to NRC'.s contractor, INEEL, at the follouing address:
Michael T. Anderson INEEL Research Center 2151 North Boulevard P.O. Box 1625 Idaho Falls, ID 83415-2209 Please contact me at (301) 415-3027 if you have any questions.
Sincerely, Original signed by:
Jon B. Hopkins, Sr. Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosure:
Request for Additional Information i
cc w/eacl:
See next page DISIRIBUTION:
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L'. Myers Perry Nuclear Power Plant Centerior Service Company Unit Nos. I and 2 cc:
Jay E. Silberg, Esq.
Donna Owens, Director Shaw, Pittman, Potts & Trowbridge Ohio Department of Comerce L
2300 N Street, N. W.
Division of Industrial Compliance Washington, D. C.
20037 Bureau of 0 erations & Maintenance 6606 Tussin Road Mary E. O'Reilly P.O. Box 40 9 Centerior Energy Corporation Reynoldsburg, Ohio 43068-9009 300 Madison Avenue Toledo, Ohio 43652 Mayor, Village of North Perry North Perry Village Hall-Resident Inspector's Office 4778 Lockwood Road U. S. Nuclear Regulatory Comission North Perry. Village, Ohio 44081 Parmly at Center Road Perry, Ohio 44081 Attorney General-Department of Attorney General Regional Administrator, Region III 30 East Broad Street U. S. Nuclear Regulatory Comission Columbus, Ohio 43216 801 Warrenville Road Lisle, Illinois 60532-4531 Radiological Health Program Ohio Department of Health Lake County Prosecutor P.O. Box 118 Lake County Administration Bidg.
Columbus, Ohio 43266-0118-105 Main Street Painesville, Ohio 44077 Ohio Environmental Protection Agency Sue Hiatt DERR--Compliance Unit OCRE Interim Representative ATTN: Mr. Zack A. Clayton 8275 Munson P.O. Box 1049 Mentor, Ohio 44060 Columbus, Ohio 43266-0149 Terry J. Lodge, Esq.
Chairman 618 N. Michigan Street, Suite 105 Perry Township Board of Trustees Toledo, Ohio 43624 3750 Center Rd., Box 65 Perry, Ohio 44081 Ashtabula County Prosecutor 25 West Jefferson Street Statc of Ohio Jefferson, Ohio 44047 Public Utilities Comission East Broad Street Henry L. Hegrat Columbus, Ohio 43266-0573 i
Regulatory Affairs Manager Cleveland Electric Illuminating Co.
Richard D. Brandt, Plant Manager i
Perry Nuclear Power Plant Cleveland Electric Illuminating Co.
P. O. Box 97, A210 Perry Nuclear Power Plant Perry, Ohio 44081 P.O. Box 97, SB306 Perry, Ohio 41081 Chief of. Staff Roy P. Lessy, Jr., Esq.
Ohio Emergency Management Agency Andrew G. Berg, Esq.
L
~ 2855 West Dublin Granville Road Akin Gump, Strauss, Hauer &
Columbus, Ohio ' 43235-2206 Feld,L.L.P.
Suite 400
' Mayor, Village of Perry' 1333 New Hampshire Avenue, NW.
- 4203 Har)er Street Washington, D.C. 20036 Perry, 0110 : 44081-
]
=i REQUEST FOR ADDITIONAL INFORMATION PERRY NUCLEAR POWER. PLANT, UNIT NO. 1 DOCKET NO. 50-440 TAC NO. M97694 1.
Scone / Status of Review
-Throughout th6 service ~ life of a water-cooled nuclear power facility, 10 CFR 59.55a(g)(4) requires that components (including supports) that are classified as American Society of Mechanical Engineers (ASME), Boiler and
- Pressure Vessel Code (Code), Class 1, -2, and -3 meet the requirements, except design and access provisions and preservice examination requ.irements, set
~
forth in ASME,Section XI, " Rules for Inservice Insroction 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 120-month inspection interval-comply with the-requirements in the latest edition and addenda of the Code incorporated by reference in the Code of Federal Regulations (CFR),
i 10 CFR 50.55a(b), on the date 12 months prior to the start of the 120-month 1
interval, subject to the limitations and modifications listed therein.
The
- components (including supports) may meet requirements set forth in subsequent editions and addenda of the Code that are incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein. The licensee, The Cleveland Electric Illuminating Company (CEI), has prepared the
" Perry Nuclear Power Plant, Unit 1, First 10-Year Interval Inservice Inspection Program Plan," Revision 0, to meet the requirements of the 1983 edition ~through the summer 1983 addenda of Section XI of the ASME Code.
The staff has reviewed the " Perry Nuclear Power Plant, Unit 1, First 10-Year Interval Inservice Inspection Program Plan," Revision 0, relief requests submitted by letters dated January 7, 1997, and February 12, 1997.
The first 10-year interval ends November 13, 1997.
2.
. Additional Information Reauired Based on its review, the staff hes concluded that additional information and/or clarification is required to complete the review of the inservice inspection program plan.
In accordance with 10 CFR 50.55a(c)(3), 10 CFR 50.55a(d)(2), and 10 CFR 50.55a(e)(2), ASME Code cases may be used as altern'atives to Code requirements.
Code cases that the NRC has approved for use are published in Regulatory Guide (RG) 1.147, " Inservice Inspection Code Case Acceptability,"
with any additional conditions the NRC may have imposed. When used, these Code cases must be implemented in their entirety.
ASME-approved Code cases awaiting NRC approval and subsequent publication in RG 1.147 may be adopted only if-the licensee requests, and the NRC authorizes, their use on a case-by-
. case basis..
4 s
b ENCLOSURE
For Code cases not published in RG 1.147, NRC may approve the cases when conditions deemed appropriate by the NRC are included; a licensee proposing the use of currently unpublished Code cases shall commit to such conditions.
A.
In Relief Request PT-005, CEI requested to implement the alternative to Code requirements contained in Code Case N-522, " Pressure Testing of Containment Penetration Piping." The NRC finds this alternative to Code requirements acceptable for use with the following conditions:
(1) the test is conducted at the peak calculated containment pressure; and (2) the test procedure provides criteria for the detection and location of through-wall leakages in CIVs and pipe segments between the CIVs.
B.
In Relief Request PT-006, CEI proposed to implement the alternatives to Code requirements contained in Code Case N-546, " Alternative Requirements for Qualification of VT-2 Visual Examination Personnel." The NRC staff finds this Code case acceptable for us with the following conditions:
(1) develop procedural guidelines for obtaining consistent, quality VT-2 ' visual examinations; (2) document and maintain records to verify the qualification of persons selected to perform VT-2 visual examinations; and i
(3) implement independent review and evaluation of leakage by persons other than those that performed the VT-2 visual examinations.
If the licensee elects to use the subject alternatives, the licensee should submit additional information that incorporates the aforementioned conditions.
This information will provide the docketed commitments that are necessary before the alternatives can be authorized.