ML18016A485
| ML18016A485 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/14/1998 |
| From: | Scott Flanders NRC (Affiliation Not Assigned) |
| To: | Robinson W CAROLINA POWER & LIGHT CO. |
| References | |
| TAC-MA0989, TAC-MA989, NUDOCS 9807200301 | |
| Download: ML18016A485 (6) | |
Text
July 14, 1998 Mr. W, R. Robinson, Vice President
'hearon Harris Nuclear Power Plant Carolina Power 8 Light Company Post Office Box 165 - Mail Code: Zone 1
New Hill, North Carolina 27562-0165
SUBJECT:
SHEARON HARRIS UNIT 1 - REQUEST FOR ADDITIONALINFORMATION (RAI) REGARDING THE SECOND 10-YEAR INTERVALINSERVICE INSPECTION PROGRAM PLAN REQUESTS FOR RELIEF (TAC NO. MA0989)
Dear Mr. Robinson:
By letter'ated January 27, 1998, Carolina Power 8 Light Company (CP8L) submitted the Shearon Harris Inservice Inspection (ISI) Program Plan for the second 10-year inspection interval. The ISI Program Plan included 19 relief requests which require NRC review and approval.
By "HNP-98-049, Requests That NRC Review Relief Requests 2R1-010,2R1-003, 2R1-004,2R1-006,2R2-003 & [[SSC" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Prior to 980930 in Order to Avoid Adverse Impact on Schedule for ISI to Be Performed During RFO8|letter dated April 17, 1998]], CP8L informed the NRC that 6 of the 19 relief requests, 2R1-003, 2R1-004, 2R1-006, 2R1-010, 2R2-003, and 2R2-005, involve inspections that are planned to be conducted during the upcoming refueling outage, scheduled for October 24, 1998. As a result, CP8L requested that the NRC review and approve these six relief requests expeditiously to avoid adverse impact on the schedule for inservice inspections for the upcoming outage.
To ensure a timely review of this submittal, the staff requests a response to the enclosed questions by August 10, 1998.
Ifthis is not achievable, CP8L should notify the staff and propose a date for submittal of a response to the RAI. Should you have any questions related to this letter or the enclosed RAI, please contact me at (301) 415-1172.
Sincerely, Original signed by:
Scott C. Flanders, Project Manager Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-400
Enclosure:
As stated cc w/enclosure:
See next page
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RE EST FO DDITIONA I
FORMATION - RELIEF E
UESTS RELATED 0 SECOND 10-YEA I TERVAL INSERVICE NSPEC IO P 0 RAM PLAN FOR SHEARON HA RIS UNIT1 eview co e/S a us Sco e/S a us of v'
Throughout the service life of a water-cooled nuclear power facility, 10 CFR 50.55a(g)(4) requires that components (including supports) that are classified as American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Class 1, Class 2, and Class 3 meet the requirements, except design and access provisions and preservice examination requirements, set forth in Section XI of the ASME Code, "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.
successive 120-month inspection intervals comply with the requirements in the latest e'dition and addenda of the Code incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the start of an 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 and subject to Nuclear Regulatory Commission (NRC) approval.
The licensee, Carolina Power 8 Light Company, has prepared the Shearon Harris Nuclear Power Plant ISI Program Plan for the second 10-year inservice inspection interval.
ddi 'o a for a ion e uired Requests for Relief 2R1-003, and 2R2-003-The licensee is seeking relief from the required volumetric examination coverage for several welds in these two.
requests.
The licensee has provided generic examples of the limitations encountered, namely pipe-to-flange, pipe-to-valve, and pipe-to-elbow configurations.
The licensee also stated in Request for Relief 2R1-003, that "specific limitations and restrictions for all examinations are as indicated on the attached list." However, there does not appear to be an attached list providing the specific limitations and restrictions.
The attachment provided in the request for relief identifies the components, Categories, and Item Numbers, and a Comment section utilized for specific examination coverage percentages obtained.
To evaluate the subject requests for relief, more specific information concerning the limitations is required.
Provide a detailed description, including drawings ifavailable, of the limitations associated with each individual weld.
Also, describe actions that have been taken to maximize examination coverages.
Request for Relief 2R1-004-Examination Category B-A, Item Number B1.40 requires volumetric and surface examinations of the reactor pressure vessel Enclosure head-to-flange weld. The licensee is seeking relief from the Code-required volumetric coverage for II-RV-001FTHW-RV-18FA, B, C.
It appears from the attachment supplied with the request for relief that only 48% of the required examination has been completed and that the limitation to the examination is due to lifting lug interference.
Provide additional information (include drawings if available) describing in more detail the limitation associated with the subject weld.
'equest for Relief 2R1-006 - The licensee is seeking relief from the Code-required volumetric examination coverage for nineteen nozzle-to-vessel welds.
and six nozzle-to-safe end butt welds. The licensee stated that these welds are not conducive to two-sided volumetric examinations due to nozzle configurations.
In addition, obstructions, which are a part of the component design, prevent accessibility to the weld.
Provide a more detailed description of the nozzle configuration associated with the subject welds (include type of nozzle configuration as described in Figures IWB-2500-7, a - d). Also, provide additional information describing the examination coverage obtained (e.g., circumferential and axial scans were performed on shell side of the weld only). Describe any actions that have been taken to maximize cove'rage of the subject welds.
Request for Relief 2R2-003 - The licensee is seeking relief from the required volumetric examination coverages for welds in Categories C-F-1 and C-F-2. The licensee has provided an attachment listing the specific welds., It appears from the licensee's program plan that at least two other welds that specifically reference 2R2-003 may need to be included in the request for relief attachment.
These welds are identified in the program plan as II-SI-008SI-FW-450 (Category C-F-1, Page 37 of 178) and II-MS-007MS-96-FW-101 (Category. C-F-2, Page 45 of 60).
It is also noted that several welds listed in the request for relief attachment have an item number that does not correspond with the item number listed in the program plan. For example, the relief request attachment has Weld II-CS-007SI-FW-25 listed as Item C5.11 while the program plan has the weld listed as Item C5.21.
It is unclear whether the program plan designation or the request for relief designation is correct.
To properly review the licensee's program plan and the associated requests for, relief, all items requiring relief must be correctly identified. Provide additional information correctly identifying the Item numbers for the welds requiring relief.
Request for Relief 2R2-005 - The licensee stated that "Component weld configurations and obstructions prevent 100 percent volumetric (UT) and/or surface examinations."
It is unclear from the attachment provided whether the
'xamination coverages listed are for volumetric examinations only or for both volumetric and surface'examinations.
Provide the surface examination and volumetric examination coverages for the applicable welds..
Enclosure
Relief is also requested from performing the Code-required volumetric examination of the steam generator nozzle inner radius sections.
The licensee stated that the steam generators were designed without a nozzle inner radius section.
Provide additional information concerning the configuration/design of steam generator Nozzles II-SG-001SGA-MSNIR-15, II-SG-001SGB-MSNIR-1 5, and II-SG-001SGC-MSNIR-15 and discuss the need for this relief request.
Enclosure