ML19352A775
| ML19352A775 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Indian Point, Kewaunee, Saint Lucie, Point Beach, Oyster Creek, Cooper, Sequoyah, Pilgrim, Arkansas Nuclear, Susquehanna, Summer, Prairie Island, Brunswick, Surry, North Anna, Turkey Point, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Duane Arnold, Farley, Robinson, San Onofre, Cook, Yankee Rowe, Maine Yankee, Quad Cities, La Crosse, Big Rock Point, Rancho Seco, Zion, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Zimmer, Fort Saint Vrain, Trojan, Crane  |
| Issue date: | 05/19/1981 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19352A776 | List: |
| References | |
| NUDOCS 8106020057 | |
| Download: ML19352A775 (3) | |
Text
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NUCLEAR REGULATORY COMMISSION 2 1 X(.g k
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WASHINGTON, D. C. 20555 h'.AY 19 G1 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation W
C Darrell G. Eisenhut, Director Division of Licensing FROM:
Thomas M. Novak, Assistant Director for Operating Reactors, DL
SUBJECT:
STATUS OF FORTY SHUTDOWN FACILITIES ON MAY 13, 1981 In response to your inquiry of May 13, 1981, "Over 40 facilities down!
What's happening?", the following summary information is provided.
Group 1 - Spring Refuelino Outages As you are well aware, many licensees deliberately plan refueling outages in the spring (and the fall, also) as this is the period of lowest power consumption. The facilities in refueling outages with no other major problems are:
Arkansas 2 Browns Ferry 1 Cooper D. C. Cook 2 (now starting up) thli4 Duane Arnold G
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Maine Yankee
/,f4 E2 5 4,,,hPf7g8 Nine Mile Point 1 i
Point Beach 2 k
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North Anna 2 p
n, Trejan s
Group 2 - Sh*;tdown for Major Problems d
The following facilities ha d expY ier[ced major mechanical failures or other l
problems as noted. Three Mile Island 2 is included _in this group for completeness.
t Browns Ferry 2 - trip recovery (has returned to power) l Brunswick 1 - miscellaneous repairs Brunswick 2 - RHR heat exchanger repair t
Davis Besse 1 - (has returned to power)
Farley 2 - startup physics testing 810602005'f
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2-Indian Point 2 - major repairs (in the process of startup)
Millstone 1 - damaged turbine Peach Bottom 2 - recirc. oumo motor bearings f
Rancho Seco - repairs (has returned to power)
San Onofre - steam generator repairs Sequoyah'1 - steam generator repairs Surry 1 - steam generator replacement Three Mile Island 2 - Accident Turkey Point 3 - Failed main generator Group 3 - Shutdown in Accordance with or to meet NRC Requirements
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This group of facilities 'is* separated from Group 2 only because the major repairs stem from some NRC requirements to ensure or improve reactor safety.
Dresden 1 - Ordered shutdown /in hearing Hatch 1 - Mark 1 containment modifications Millstone 2 - Inoperable mechanical snubbers / Bulletin 81-01 Oyster Creek - BWR scram system and environmental qualifications /
Bulletin 79-01 Peach Bottom 3 - Mark l containment modifications Yankee Rowe - Modifications for AFWS upgrade, TMI requirements and SEP Group 4 - Shutdown Awaiting NRC Licensing Action i
This grouping is necessary since these facilities were counted in the 40 shutdown units.
Diablo Canyon 1 - 12 months delay LaSalle - no delay McGuire - 6 months delay Salem 2 - ready since May 1979 Susquehanna 12.onths delay i
Summer - 5 months delay Three Mile Island 1 - hearing Zimmer - no delay
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These four groups categcrize the reasons for the 40 shutdown facilities as shown on the enclosed IE Plant Status Report of May 13, 1981.
In addition, the following facilities are limited or are operating significantly below their licensed power level.
l Big Rock Point - 88% due to thermal limits on fuel Davis Besse 1 - threeRCP operation limits power to %75%
Fort Calhoun - 45% conserving fuel (low area power consumption) i 1
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3-Fort St. Vrain - 70% license limit Indian Point 3 - 67% due to failed main transformer Lacross - 94% to extend core life r
Pilgrim 1 - 90% limit due to condenser delta temperature Point Beach 1 - 80% by licensee to reduce steam generator tubes degradation U
omas M. Novak, Assistant Director for Operating Reactors Division of Licensing
Enclosure:
As stated.
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