ML19323E134
| ML19323E134 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 05/14/1980 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Duvall G AFFILIATION NOT ASSIGNED |
| References | |
| FOIA-80-233 NUDOCS 8005230032 | |
| Download: ML19323E134 (4) | |
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Docket flo. 50-460 May 14, 1980 Mr. George DuVall 1820 16th Avenue, #405 IN RESPONSE REFER Seattle, WA 98122 TO F01A-80-233
Dear Mr. DuVall:
This is in response to your letter of April 21, 1980, in which you requested, pursuant to the Freedom of Information Act, nine categories of documents regarding the Washington Public Power Supply Systems Nuclear Project, Number 2 (WPN-2).
Please find enclosed documents, as listed on Appendix A, which have been found to be subject to your request.
In addition, the following responses are subject to your request under the specific items as enumerated in your letter:
ITEM 2: The operating license application for WPR-2 was docketed in June 1978 and has been completed through the first round of questions.
ITEM 3:
Conservative bounding load criteria have been required by the NRC staff as a result of the ongoing load definition program for the pool dynamic loads associated with the Mark II vapor suppression containment system.
These conservative load criteria necessitated modifications to the structures subjected to pool dynamic loads.
ITEM 4:
None.
ITEM 5:
There are a total of ten units which have Mark II vapor
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suppression containment systems. Their construction status as of December 31, 1979, was as follows:
Unit Percent Complete Zimmer 95%
LaSalle 1 93%
Shoreham 80%
WPN-2 80%
LaSalle 2 74%
Susquehanna 1 74%
Limerick 1 56%
Susquehanna 2 46%
Limerick 2 32%
Bailly 1%
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Mr. George DuVall.
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This information was taken from NUREG-0030, Volume III, No.1, dated February 1980, " Construction Status Report Nuclear Power Plants."
ITEM 6:
Zimmer is a BWR-5/ Mark II plant similar but not identical to WPN-2. While both plants have General Electric as the vendor of the nuclear steam supply system, there are two different architect-engineers responsible for the total design of the plant.
ITEM 7: There are two Abnormal Occurrences subject to the request.
The first, A0 75-5, " Cracks in Pipes at Boiling Water Reactors," was first reported to Congress in NUREG-75/090 and updated in NUREG-0090-1, 2, 3, 9, Vol. I, No. 3; Vol. II, No. 2; and Vol. 2, No. 4.
The other is A0 76-1, l
" Deficiencies in the Mark I Containment System of Certain Boiling Water Reactors," first reported in NUREG-0090-3 and updated in NUREG-0090-4, 6, Vol. I, No.1; Vol. I, No. 3; and Vol. II, No. 3.
These documents can be purchased from the National Technical Information Service, 5285 Port Royal Road, Springfield, Virginia 22161.
In addition, these documents are publicly available in an NRC Local Public Document Room near you.
The address is as follows:
Ms. D. E. Roberts, Librarian, Richland Public Library, Swift.& Northgate Street, Richland, Washington 99352 (509-943-9118).
ITEM 8: There was no specific information received by the NRC in 1975 which led the NRC to re-evaluate the Mark II pool dynamic loads.
However, General Electric presented data to the NRC in late 1974 relating to the pool swell loads that would occur in the event of a design basis loss-of-coolant accident. Whjle these loads were measured in a test facility representative of the Mark III containment, it was believed that the same phenomenon would occur in both the Mark I and Mark II vapor suppression containnents.
The NRC staff also became aware in 1974 of significant pool dynamic loads observed during a test of the safety-relief valves in a Western European reactor.
This information reinforced observations of structural damage occurring in the Mark I containments that was believed to be the result of loads caused by the discharge of the safety-relief valves.
Mr. George DuVell
- ITEM 9: The enclosed computer printout indicates all LER's involving relief valves as an involved component for operating Mark I, BWR plants.
The printout includes only major incidents from sudden steam relief valve discharges.
From this, "blowdowns" due to steam relief valve discharge (unplanned) can be discerned, such as on page 1, item 4, February 12, 1974, at Brown's Ferry Uni t 1.
This completes action on your request.
Sinc ely, J. M. Felton, Director Division of Rules and Records Office of Administration
Enclosures:
As stated t
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Re:
F01A-80-233 APPENDIX A 1.
Undated Listing of Boiling Water Reactors (2 pages) 2..
May 8, 1980 LER Output on Relief Val'ves, thrk I Operating Plants from 1969 to the Present (56 pages) 3.
Undated Facility Status Summary (3 pages) 4.
February 29, 1980 Excerpt from Regulatory Licensino:
Status Summary Repert, Data for Decisions, Nuclear Power Plants (3 page's)
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5.
August 1979 Excerpt from " Plant Design Assessment Report for SRV and LOCA Loads (26 pages) 6.
October 1978 NUREG-0487, " Mark II Containment Lead Plant Program Load Evaluation and Acceptance Criteria" 7.
July 1978 NUREG-0474, "A Technical Update of Pressure Suppression Type Containments in Use in U.S.
Light Water Reactor Nuclear Power Plants" O
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