ML20235E948
| ML20235E948 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/17/1987 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NLR-N87172, NUDOCS 8709280339 | |
| Download: ML20235E948 (6) | |
Text
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. Public Service Electric and Gas
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- Corbin A. McNeill, Jr.
Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4800 Senior Vice President -
Nuclear September 17, 1987 NLR-N87172 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen RESPONSE TO QUESTIONS ON INSERVICE INSPECTION PROGRAM LONG TERM PLAN:
HOPE CREEK GENERATING STATION DOCKET NO. 50-354 During a telephone conversation on August 27, 1987, with Mr. G.
Rivenbark of your staff, clarification was requested for certain items included in the subject inservice inspection program plan for the Hope Creek Generating Station submitted on June 29, 1987.. The responses to those questions are included in the following.
.A)
Control Rod Drive Systems - Scram Discharge Volume PSE&G has revised their position on the exemption of these lines based cn the operating pressure and temperature exemption criteria of Code Case N-408, subparagraph (b)(3).
Accordingly, the following revised page to the Plan is attached to this letter.
VOLUME C, Attachment 5-14, Appendix D, Page D-31.
Additionally, appropriate examination figure (s) will be added to Appendix B, and the 6 welds on each line (1-BF-ELB-040, and 1-BF-ELB-041) will be subject to volumetric and surface examination in accordance with the requirements of subsection IWB of Section XI.
This information will be added to the Class 2 component examination table.
B)
Reactor Core Isolation Cooling System PSE&G does not take credit for this system as an Emergency Core Cooling System (ECCS).
Therefore, the exemptions taken in the Plan are appropriate and in compliance with the provisions of Code Case N-408.
B709280339 870917
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Document Control Desk 2
SEP 171997 C)
Limitation on RPV Ligament Examination Attached to this letter are copies of Figures 14 and 15 depicting the scan area limitations, which were inadvertently omitted from Volume A, Attachment 5-13 of the June 29, 1987 submittal.
D)
Compliance to Regulatory Guide 1.150 We confirm that the procedures used for RPV examinations comply with this document, as was indicated in Section 2.1.2.1 of the Plan.
E)
Compliance with NUREG 0313 We confirm that PSE&G has complied with the requirements of this document prior to licensing by reduction of austenitic piping where possible, application of solution heat treating and corrosion resistant cladding mitigation techniques, and the use of "L" grade austenitic materials.
An augmented examination program to NUREG 0313 is therefore not applicable.
F)
Compliance with NUREG 0619 We confirm that PSE&G had committed to fully comply with the inservice inspection requirements of this document in the response to HCGS FSAR Question 210.32.
The feedwater nozzles /spargers at HCGS incorporate the triple sleeve design with two sister ring seals and an unclad nozzle.
Therefore, PSE&G will perform the ultrasonic examinations of all 6 feedwater nozzle safe ends, bores and inside blend radii by the end of the second refueling outage, and every second refueling cycle thereafter.
Our NDE vendor is presently developing a technique for examination of the bore area, and any limitations in obtaining full coverage will be addressed in a future request for relief, if necessary.
PSE&G will perform the visual inspection of the sparger flow holes and welds in sparger arms and sparger tees at the interval of every 4 refueling cycles.
PSE&G will perform the " Routine PT" of the inside surfaces of l
one nozzle following removal and grinding of the sparger, and I
the accessible portions of the other 5 nozzles.
This examination will be performed at the interval of once every 9 refueling cycles or once every 135 startup/ shutdown cycles, whichever occurs first.
j I
L Document Control Desk 3
9-17-87 Should you have any questions on this transmittal, please do not hesitate to contact us.
Sincerely, C
Mr.
G.
W.
Rivenbark USNRC Licensing Project Manager Mr.
R. W. Borchardt USNRC Senior Resident Inspector Mr.
W.
T.
Russell, Administrator USNRC Region I Mr.
D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 j
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