View source for B12669, Forwards Relief Requests 5.0 & 4.0 for Relief from ASME Code Section XI Requirements for Inservice Insp of Category B-J Welds & Specific Valve Internal Surface Visual Exams, Respectively.W/One Oversize Drawing.Fee Paid

{{Adams
| number = ML20235G924
| issue date = 09/23/1987
| title = Forwards Relief Requests 5.0 & 4.0 for Relief from ASME Code Section XI Requirements for Inservice Insp of Category B-J Welds & Specific Valve Internal Surface Visual Exams, Respectively.W/One Oversize Drawing.Fee Paid
| author name = Mroczka E
| author affiliation = CONNECTICUT YANKEE ATOMIC POWER CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000213
| license number = 
| contact person = 
| document report number = B12669, NUDOCS 8709300292
| package number = ML20235G927
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 15
| project = 
| stage = Request
}}

=Text=
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CONNECTICUT YANKEE ATOMIC POWER COMPA NY B E R L I N, CONNECTICUT P.O. BOX 270   HARTFORD, CONNECTICUT 06141-0270 T ELE PHONE 203-665 4000 September 23,1987 Docket No. 50-213
$                                                                                                                               B12669 Re: 10CFR50.55a(g)
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 i    

==References:==
(1)  3. F. Opeka to C.1. Grimes, ISI Relief Request for Code Category B-3 Welds, dated September 16,1986.
(2)  F. M. Akstulewicz letter to 3. F. Opeka, RAI on 151 Relief Request for Code Category B-3 Welds, dated November 6, 1986.
(3)  E. 3. Mroczka letter to U. S. NRC, Response to Requests for Additional Information, dated January 26,1987.
(4)  C. O. Thomas letter to E. 3. Mroczka, Relief from ASME Code Section XI Requirements for Inservice Inspection of Category B-3 Welds, dated May 7,1987.
Gentlemen:
Haddam Neck Plant Request for Relief from ASME Code Section XI Requirements for Inservice Inspection of Category B-3 Welds and Specific Valve Internal Surface Visual Exams in Reference (1) information was provided to support a relief request originally denied because of lack of supporting information.ll) As a result of NRC review and further response to requests for additional information (see References (2) and (3)), an SER was issued by Reference (4). This SER represented approval of a Relief Request for all previously inspected second interval Category B-3 welds that could not be inspected to Code requirements because of geometry or support interference, in a July 9,1986 call it was agreed that during the 1987 refueling outage, those Category B-3 welds, which were determined to need relief from code examination requirements, would be identified and a listing (1)                          See the C.1. Grimes letter to 3. F. Opeka, dated May 12,1936. This letter stated that in order to obtain relief an up-to-date list of Category B-3                                                       t welds to be inspected should be provided and specific information relative                                                f to individual welds should be provided.
8709300292 870923                                                                                                                                         d PDR                                ADOCK 05000213                                                                                           1 , p G                                                                                PDR

U. S. Nuclear Regulatory Commission
                  ' B12669/Page 2 September 23,1987 provided to the NRC in order that specific relief be granted prior to startup. As discussed,, the reason for this was that many of these welds were not easily
                  -accessible during full power operation and none were inspected previously.
Attachment I contains Relief Request 5.0 and provides a listing of those ASME l
Code Section XI category B-3 welds that require relief from the examination requirements. The isometric drawing number, ISI weld number, extent of exam                                                             'l performed and reason for not meeting the Code Requirements is included in the Relief Request description and the actual drawings are included at the back of the attachment. With the exception of the previously identified partially inspected welds and these partially inspected welds, " percentage of welds inspected" requirements for the second interval have been met.
Attachment 2 forwards Relief Request 4.0. This Relief Request is being made                                                               )
pursuant to 10CFR50.55a(g)(5)(iii) and requests relief from performing visual examination on valve internal surfaces as identified in Table 1 of the Relief Request.
Should you have any additional questions on these requests, feel free to contact us directly..
Pursuant to the requiremerits of 10CFR170.12(c), enclosed for Relief Requests 4.0 and 5.0 is an application fee of $150.00.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY                                                             f
{
                                                                 /$dn// a                                                                                     j E .'~3  'iroczka                                                                                     )
Se     r Vice President                                                                             )
                                                                                                                                                              )
cc:   W. T. Russell, Region I Administrator F. M. Akstulewicz, NRC Project Manager, Haddam Neck Plant
: 3. T. Shediosky, Resident Inspector, Haddam Neck Plant I

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(
Docket No. 50-213 l                                                                         B12669 Attachment 1 Relief Request 5.0 Category B-3 Welds Requiring Relief September,1987

Attachment i B12669/Page1 Attachment 1 RELIEF REQUEST 5.0 Code Class: I                                                                                                                                                                        g Code Category B-3, pressore retaining welds in piping                                                                                                                                   1 Code item No.: B9.11 System Reactor Coolant Drawing No.                                                                                                                   Weld No. Design Configuration l
16103-20275 SH 22                                                                                                                               22-12      Pipe-to-valve 16103-20275 SH 33                                                                                                                              33-08      Pipe-to-elbow 16103-20275 SH 33                                                                                                                              33-09      Pipe-to-elbow 16103-20275 SH 33                                                                                                                              33-12      Pipe-to-valve        _ ..
16103-2-275 SH 43                                                                                                                              43-12       Pipe-to-valve Code Requirement Section XI of ASME B&PV Code,1980 Edition, with addenda through the Winter of 1980, requires that a surface and volumetric examination of the weld be performed in accordance with the requirements of Fig. IWB-2500-8.
The extent of examinations are in accordance with the requirements of ASME Section XI 1974 Edition, with addenda through the summer of 1975.
Ultrasonic examination requirements from mandatory Appendix III, Article III-4000 require examination for:
A.                 Reflectors parallel to the weld seam.
The angle beam examination for reflectors parallel to the weld seam shall be performed by a full V-path from one side or a one-half V-Path from two sides of the weld when applicable.
B.                 Reflectors transverse to the weld seam.
: 1)    The angle beam examination for reflectors transverse to the weld                                                                                            ,
seam shall be performed on the weld crown on a single scan path to examine the weld root by one-half V-path in two directions along the weld.
: 2)    For inservice examination, only those welds showing reportable preservice indications need to be examined for transverse reflectors.
Pursuant to 10CFR55a(g)(5Xiii), relief is requested from performing the code required volumetric exam to the extent required by Fig. IWB-2500-A.

Attachment 1 B12669/Page 2 Reason for Relief The arrangements and details of the Class I piping systems and components were designed and fabricated before the examination requirements of Section XI of the code were formalized. Generally, limitations exist at pipe-to-fitting welds such as pipe to valve and pipe to elbow, where geometry and surface conditions preclude ultrasonic coupling or access for the required scan length.
Specifically, ultrasonic examinations of the required volume of the cast stainless ,
steel material of the valve and fitting cannot be performed due to the high        I attenuation of materials. A full vee path scan from the pipe side of the weld will not penetrate and produce a useful signal to noise ratio. Furthermore, examination from the fitting side of the weld could not be performed due to the geometry.
Proposed Alternate Examination                                                     j The bottom one-third of the weld received an ultrasonic examination in accordance with the methods provided in the code. The exam was performed from the pipe side of the weld in all cases. Approximately 50% of each weld required volume was examined with a 45 degree transducer. A code required surface examination was performed on each of the subject welds.
The required visual examinations will be performed in accordance with Category B-P IWB-2500-1 of the code.
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1 Docket No. 50-213   i B12669
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l Attachment 2 Relief Request 4.0 Visual Examination on Valve Internal Surfaces September 1987 L___.________.

l, Attachment 2 B12669/Page1 Relief Request 4.0 Code Class: 1 Code Category: B-M-2                                                              ,
Code Item No.: B12.40 I                  System: Reactor Coolant, Core Deluge, and Residual Heat Removal Systems Code Requirement Section XI of the ASME B&PV code,1980 Edition, with addenda through the winter of 1980, requires a visual examination of the valve internal surfaces once during each inspection interval.
Examinations'are limited to one valve within each group of valves that are of the same construction design and manufacturing method and that are performing similar functions in the system.
Code Relief Request Pursuant to 10CFR50.55a(g)($)(iii), relief is requested from performing the code required visual examination on the valve internal surfaces.
Reason for Relief There are four valves (as identified in Table 1) scheduled for examination to fulfill the requirements to examine one of each type of valve of the same manufacturing method and construction design and that are performing similar functions. None of the valves scheduled for examination or any of the valves of similar type and design are being disassembled for maintenance or repair. This is the last scheduled refueling outage prior to the end of the second ten year interval. An ALARA review was performed to determine the expected man rem exposure to perform the inservice examination of each valve. A value of approximately 26.5 man rem was estimated to perform all of the required examinations.      CYAPCO believes that the examinations performed are impractical and not commensurate with the increased safety achieved by this examination. To disassemble these valves would provide a very small potential for increasing plant safety margins with a disproportionate impact on man rem expenditures and resources.
Proposed Alternative Examination The subject valves will receive a visual examination (VT-2) during the code-required pressure tests.
If the valves are disassembled for maintenance, the code required visual           i examination (VT-3) will be performed.
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Attachm'ent 2-B12669/Page 2 Table 1 Subject Valves of Relief Request 4.0 l
MANREM FOR SYSTEM         VALVE NUMBER        EXAMINATION          DRAWING NO.
RCS               MOV-510              12               16103-20275 SH 46 Core Deluge       MOV-871 A            7.2              16103-20275 SH 72 RHR               MOV-781              2.58             16103-20275 SH 14 RHR               M OV-804             4.8               16103-20275 SH 24 1
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