ML18191A263
| ML18191A263 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/08/1976 |
| From: | Renberger D Washington Public Power Supply System |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| G02-76-447 | |
| Download: ML18191A263 (5) | |
Text
NRC FORM 195 I2 7B)
U.S. NUCLEAR REGULATOR MISSION ABC DISTRIBUTION FoR PART 50 DOCKET MATER!AI DOCKET NUMBER 50-397 Mr. S. A. Varga"'ROM:
Washington Public Power Supply Stm.
- Richland, Washington D. L. Renberger FII.E NUMBER ISc. g DATE OF DOCUMFNT 10/8/76 DATE RECEIVED 10/14/'76 LETTER jHCOR IGINAL Qcopv ONOTORIZED
/UNCLASSIFIED PROP INPUT FORM NUMBER OF(COPIES RECEIVED DESCRIPTION Ltr.;,re our 9/21/76 ltr..and their 8/19/76
- ltr....concerning Schedule for Annulus Pressurization
& Reactor Feedwater Nozzle cxactI jnfotmation.
I (2-P)
PLANT NAME:
WPPSS DISTRIBUTION FOR REACTOR VESSEL SUPPORT INFO FOR OPERATING REACTORS PER MR, 'HlAMMELL 7 12 7
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@8I4b Q O~s Number 50-397 October 99352 PHONE(509) 946-16j1 Mr. S.
A. Varga, Chief Light Water Reactors Branch 4
Division of Project Management U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
WPPSS NUCLEAR PROJECT NO.
2 SCHEDULE FOR ANNULUS PRESSURIZATION AND REACTOR FEEDWATER NOZZLE CRACK INFORMATION'al-I[i
Reference:
1.
S.
A. Varga, NRC, to J. J. Stein,
- WPPSS, dated September 21,
- 1976, HReactor Vessel
- Support, Loads, and Feedwater Nozzle Cracks" 2.
N. 0. Strand to A. Giambusso, "Response to Request for Additional Information Sacrificial Shield Wall Design," August 19, 1975 (G02-75-240)
Dear Mr. Varga:
You requested, in Reference No. 1, a schedule by which additional information for the WPPSS Nuclear Project No.
2 (WNP-2) could be supplied to you concerning annulus pressurization and radial cracks in reactor feedwater nozzles.
Our nuclear steam supplier (General Electric) was advised of this request and a schedule has been estab-lished by which additional analyses and the required information can be completed.
An evaluation of WNP-2 for the effects of postulated pipe breaks in the annulus was performed for shield wall structural compatibility and was filed on our Docket Number 50-397 in response to a Commission concern in August 1975 (Reference No. 2).
General Electric has indicated that the results of'a complete impact analysis of annulus pressurization effects on the'RPV can be available for filing in an amendment to the FSAR during the'first or second quarters of 1978.
General Electric has undertaken an extensive test program to investigate the thermal cycling and associated nozzle blend radii cracks which have occurred on reactor vessel feedwater nozzles.
The program includes facilities which can reproduce the thermal cycling phenomena which will allow evaluation of 'proposed modifications to ensure thermal cycling is reduced.
'Testing is scheduled for completion in mid-1977.
Mr. S. A. Varga Page 2
Additionally, in-service inspection of the nozzle inside radius section of the RPV feedwater inlet nozzles will be accomplished by ultrasonic examination from the exterior surfaces in accordance with ASME code requirements.
If the investigation into thermal cycling and associated cracking indi-cates that additional protective measures are warranted, design modifications and/or supplemental in-service inspections will be implemented as appropriate.
Very truly yours, DLR/GAK/rsl D. L.
RENBERGER Assistant Director Generation and Technology cc:
J. J.
- Byrnes, BSR J. J. Verderber, B8R J.
D. Wilson, BSR D. Roe, BPA F. A. MacLean, GE
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