ML20235U196
| ML20235U196 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/01/1989 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20235U200 | List:
|
| References | |
| TAC-56682, TAC-56683, NUDOCS 8903090092 | |
| Download: ML20235U196 (6) | |
Text
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. DuxE POWER COMPANY P.O. DOX 33180 CHARLOTTE, N.O. 28242 HALB.TUGKER Tet.nruowe suo e amoreverion t
March 1, 1989 U.S. Nuclear
- Regulatory Commission Document Control Desk
. Washington, D.C.
20555
Subject:
McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 Response to Request for Additional Information Regarding Inservice Inspection Program (TACS 50682 and 56683)
Gentlemen:
Pursuant to your letter of November 15, 1988 and our tele-conference of December 2, 1988, find attached our response to your questions.
Should you have any additional questions or concerns, please contact S.E. LeRoy at (704) 373-6233.
Very truly yours, W
Hal B. Tucker SEL/ISI/sel.
Attachment xc: Mr. S.D. Ebneter, Region II Administrator U.S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 Atlanta, GA 30723 Mr. Darl Hood, Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.
20555 Mr. P.K. Van Doorn, Senior Resident Inspector Nuclear Regulatory Commission y
McGuire Nuclear Station r
Mr. Tory Whitehead, SAIC P.O. Box 50697 101 South Park Avenue - Suite 5 f}
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Document Control Desk
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March 1, 1989 l-Page 2 bxc: A.F. Batts C.B. Cheezem R.C. Futrell R.L. Gill R.O. Sharpe J.S. Warren MC 801.01 (7) i
Document Control Desk March 1, 1989 ATTACHMENT Duke Power Company McGuire Nuclear Station Response to Request for Additional Information Regarding Inservice Inspection (ISI) TACS 56682 & 56683 During a tele-conference with Darl Hood of NRC and Tory Whitehead, SAIC consultant, on December 2,.1988, it was agreed that the following information would be submitted in response to questions from the NRC consultant.
As agreed, due to the large volume of drawings requested, (approximately 300), the following items will only be sent to the NRC Public Document Room and to Tory Whitehead of SAIC in response to Questions 1-3.
- 1) Color coded flow diagrams identifying non-exei;t pressure boundaries;
- 2) Class 1, 2, and 3 Hydro drawings; and,
- 3) A new revision (#11) to the McGuire ISI Plan.
The following information is provided in response to your questions.
Question No. 4 Section 1.0 of the ISI Plan states:
'" Examinations of Class 3 components included in examination category D-B will be selected in accordance with Table IWD-2500-1 of the 1980 Edition of ASME Section XI as allowed by paragraph 50.55a(g)(4)(iv) of 10 CFR 50."
Paragraph 50.55a(g)(4)(iv) permits updating to more recent versions of the code.
The 1980 Edition of ASME Section XI with Addenda through Winter 1980 (80E80W) has I
baen selected as the applicable version of the code for McGuire (MNS) 1 and 2.
l Selecting the 1980 without addenda is not consistent with paragraph I
50.55(g)(4)(iv). Clarify the requirements that will be used for the examination of Class 3, Category D-B components.
Response
Section 1.0 of the MNS ISI Plan has been changed to read:
Examination of Class 3 components included in examination category D-B will be selected in accordance with Table IWD-2500-1 of the 1980 Edition of ASME Section XI, including all addenda through Winter 1982, as allowed by paragraph 50.55a(g)(4)(iv) of 10 CFR
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l Document Control Desk March 1, 1989 Attachment Page 2 of 4
- Question No. 5 The ISI plan does not state that the 1974 Edition, Summer 1975 Addenda of the Code is being used for the extent of examination for Class O piping welds in the Residual Heat Removal (RHR), Emergency Core Cooling (ECC), and Containment Heat Removal (CHR), systems as required by 10 CFR 50.55a(b)(2)(iv). The plan should state that this regulation is being met'and identify the welds selected to satisfy the requirements of 10 CFR 50.55a(b)(2)(iv).
Response
Appropriate piping welds in the Residual Heat Removal (ND), Emergency Core Cooling
- (NI), and Containment Heat Removal (NS) systems were selected for examination as required by 10 CFR 50.55a(b)(2)(iv). The welds were chosen to equal or exceed the minimum requirements of the ASME Code,Section XI 1974 Edition with Addenda through Summer 1975. To maintain a consistent plan format and provide compatibility with subsequent intervals, the specific welds selected were chosen using the criteria shown in Table IWC-2500-1, Category C-F for all other Class 2
' Systems.
Question No. 6 The ISI Program Plan for Units 1 and 2 is written to be in accordance with tho 1980 Edition of ASME Seitton XI, including all Addenda through Winter 1980. This edition is appropriate for Unit 2, however, the Unit 1 operating license is dated July 8,1981, which gives the Code of record as 1977 through 1979.
Formal approval must be requested per 10 CFR 50.55a (g)(4)(iv) to update the Unit 1 ISI program plan to the 1980 Edition of ASME Section XI, including aH addenda through Winter 1980.
If this vequest was made previously, provide copies of appropriate documents.
Resoonse A formal request to update McGuire Unit 1 to the 1980 Edition of ASME Section XI including Addenda through Winter 1986 has been submitted to the NRC by our letter dated February 28, 1989. A copy of this request is attached for your review.
Question No. 7 With regards to limitations due to metallurgical properties of cast stainless steel (SA351 Grade CF8A), the staff has continued to monitor the development of new or improved examination techniques. As improvements in these areas are achieved, the staff is requiring that these new techniques be made part of the ISI examination procedures.. Discuss the ISI examination procedures for the ultrasonic examination of the MNS 1 & 2 primary coolant system and, in particular, the
' improved examination techniques and procedures which will be incorporated to increase the level of conpitance with the Code exar9 nation requirements.
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Docunient Control Desk j
March 1, 1989 Attachment Page 3 of 4
Response
We are using the most current improved examination techniques available for the examination of cast stainless stael piping at MNS. A 45 degree refracted I
longitudinal wave transducer is being used for the engle beam examination. These transducers were designed for special applications on highly attenuating materials. This technique was demonstrated to NRC Region II personnel in Atlanta on October 2, 1987.
' Question No. 8 Code Case N-356 is not referenced in Regulatory Guide 1.147 es an NRC approved code case. Therefore, this code case, as referenced in Section 1.2 of the ISI l
Program Plan, should not be used.
Please provide justification for the use of this' code case or submit a request for relief along with technical justifications as to why the code required Section XI requirements are impractical.
Response
By letter dated February 28, 1989, we submitted a request to the NRC reAuesting A
use of Code Case N-356 at our McGuire, Catawba, and Oconee Nuclear Stations.
copy is attached for your 16 formation.
Question No. 9 As required by 10 CFR 50.55a(g)(5), if certain code examination requirements are determined to be ingractical and relief is requested, you must submit information to the NRC to support that determination.
Section 9.0, " Requests for Relipf from ASME Code Requirements," of the ISI Program Plan does not include any formal request for relief from Section XI of the ASME Code.
You submitted several requests for relief from hydrostatic testing and snubber testing requirements by individual letters. Please revise Section 9.0 of the ISI Plan to inc'lude all requests for relief whether previously submitted or not, including supporting technical j. justifications.
Each request for relief should be a " stand-alone" document, (i.e., all the support 9ng information should be included as part of the Pelief request).
Response
We have complied with Appendix A, " Inservice Inspection: Guidance for Preparing Request for Relief from certain requirements pursuant to 10 CFR 50.55a(g)(5).
The Unit 1 and 2 Safety Injection Accumulator Tank Shell Welds are the only items for which relief has been requested during the first interval. This information has begn included in revision 11 of the ISI Plan, Volume i, Section 9.0.
The request for relief was submitted to NRC by our letter dated November 8, 1988. To date, NRC approval has not been granted.
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Document Control Desk March 1, 1989-Attachinent Page 4 of 4 Question No. 10 The staff is using the submittals listed in Attachment 2 to review the first interval ISI plL;, end relief requests for MNS 1 and 2.
Provide copies of documents not listed in Attachment 2 that should be used in the review of your first ISI Plan.
Response
A review of our records revealed one relief request that was not include in of your 17tter. McGuire Relief Request No. 88-08 requested relief from certain requirements as described in our response to Question No. 9 above.
A copy of the request is attached for your information.
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