ML20206K478
| ML20206K478 | |
| Person / Time | |
|---|---|
| Site: | Catawba, Grand Gulf, Columbia, Clinton, LaSalle  |
| Issue date: | 05/28/1982 |
| From: | Palladino N NRC COMMISSION (OCM) |
| To: | Bevill T HOUSE OF REP., APPROPRIATIONS |
| References | |
| NUDOCS 9905130170 | |
| Download: ML20206K478 (18) | |
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- UNITED STATES -A[ M
{Qg, y pj 3 NUCLEAR REGULATORY COMMISSION U -
- WASHINGTON, D. C. 20555 k j g4 May 28,1982 MI%" jd g CHAIRMAN U JJN 4 c't 3 50 4/
The Honorable Tom Bevill, Chairman Subcommittee on Energy and Water 7
Development ,,
Comittee on Appropriations m 1
United States House of Representatives uJ Washington, DC 20513 l
{ I Dear Mr. Chairman.
{
This monthly status report is in response to the direction given in House Report 96-1093. Enclosed is our nineteenth report covering the period from April 15,1982 to Fby 15,1982. This nineteenth report discusses actions that were taken during this period on operating reactors and on licensing reviews of new facilities. [c' On April 17, 1982, the Director, Office of Nuclear Reactor Regulation, issued an operating license (limited to fuel loading and 5% power operation) for LaSalle Unit 1. As a condition to the operating license for LaSalle Unit 1, g the licensee shall complete an assessment of the rebar damaged due. to drilling and coring in concrete and the structural adequacy of the off-gas building roof. The results will be reported to the NRC staff for review and approval, [
prior to power operation following initial criticality and zero power physics testing. .l Recently, changes in the construction completion dates have been announced by the utilities for Grand Gulf (from April 1982 to Fby 1982), Clinton 1 (from January 1983 to January 1984), Catawba (from August 1983 to October 1984), and ,
WNP-2 (from Fbrch 1983 to August 1983).
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Since many applicant construction completion dates have slipped, the Commis- j sion is considering revising Commission decision dates for full-power licenses /
in Table 1 to be commensurate with the applicant's need for a full-power license. The NRC staff will be contacting your staff concerning this issue. [%!
I The report also discusses the recent events concerning cracks found in nozzles !
on makeup water lines and damage to the auxiliary feedwater header at some Babcock and Wilcox plants, cracks in recirculation loop ~ safe-ends found at Nine Mile Point, followup actions regarding the Ginna steam generator tube rupture, and the status of the restart of TMI-1.
Sincerely, 4
Nunzio J. Palladino
Enclosure:
NRC Fbnthly Status Report to Congress ;
cc: The Honorable John T. Ftrers 9905130170 820528 PDR v
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. N*/; ., NRC MONTHLY STATUS REPORT TO CONGRESS
'Thi's is.the nineteenth monthly status report to Congress in response to the '
' direction given in House Report 96-1093. This report provides a discussion of major actions that were taken on operating reactors and on licensing reviews-l of new facilities during the period of time between April 15,1982 and
.May 15,1982.
TMI Unit 1 Restart The Special Master, who presided over the reopened hearing on the cheating !
l issue, issued his decision on the matter on April 28, 1982. The decision was I unfavorable regarding the licensee's training and testing program and was critical of the NRC examination given to the reactor operators. The decision also recommended (1) excluding some people from operations, (2) criminal prosecutions of the. 2. terminated employees, and (3) revision of NRC exams. It also' criticized
.the Operations Staff. The Special Master's decision is now before the Licensing Board. ]
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.Last month, it was reported that the staff was undertaking actions to develop an ;
environmental assessment on t'.a effect of psychological stress on residents near TMI, as ordered by the U.S. Court of Appeal,s. The judges' opinions were issued in May. The staff is continuing its efforts to develop an environmental assessment on this issue by June 1982.
General- Public Utilities '(GPU) has submitted a letter to the NRC dated April 30, 1982 that provided an updated status on the steam generator analysis and repair plans,- and requested the NRC staff's advice regarding the need for a licensing 4 action,'with the associated hearing potential, on the steam generator matter.
Th'e GPU request is under review.
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L The GPU has decided to seal (to the upper tube sheet) virtually all of the 31,000 tubes in.both Once Through Steam Generators. Not all 31,000 tubes show indications of damage but the licensee feels it will be more efficient to seal most of them, whether or not defects were indicated.
Also, a total of 500 to 700 tubes in the two generators are likely to be plugged and _taken out of service. GPU reports that this decision is not i expected to have a substantial impact on the original $25 million cost estimate for repair of the TMI-1 steam generators. j The-licensee's schedule for the completion of the repairs is unchanged from the previous report, early fall 1982. Subject to NRC approval for restart, I
GPU's estimates of plant readiness would permit the return of Unit 1 ]
l to service before the end of the year. . ,
I Ginna Rochester Gas & Electric Corporation (RG&E) has completed its investiga-
- tion as to the failure mechanism of the ruptured steam generator tube
' in the B steam generator at R. E. Ginna. RG&E has concluded that the initkal damage to the peripheral tubes was caused by impact from a 4 inch 1
by 6 inch by 1/2 inch steel' foreign object found in the steam generator.
Degradation was initially. detected by the inservice inspection program l
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After these tubes were plugged, continued influence of the foreign object resulted in the tube' collapsing and eventually severing at the tube sheet.- The severed
. tubes were then free to impact the tubes in the inboard rows. The inboard tubes
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were also subsequently plugged. It was one of these tubes that eventually severed and led to the final' tube rupture. The severed tube rubbed against the good tube, l thus thinning the tube wall until the interior pressure was sufficient to burst l l
the tube.
l The NRC staff has obtained a nunber of tube samples from RG&E and an
' independent laboratory examination was performed. The results were evaluated.
The NRC staff has reviewed RG&E's evaluation of the steam generator tube rupture event. A final Safety Evaluation Report favorable to the restart of the R. E. Ginna Nuclear Power Plant was issued on May 22, 1982. The plant was restarted on May 22.
The staff is also continuing its generic review of the event, along with other recent steam generator problems.
l Make-up Line Nozzle Cracking in Babcock and Wilcox (B&W) Plants As previously reported, thermal stress-induced cracks were found on the make-up nozzles of four of the eight B&W plants. These plants were Crystal River Unit 3, Oconee Units 2 and 3, and the Rancho Seco plant.
All sleeve repairs and replacement of cracked nozzles have been completed'on these plants. The Rancho Seco plant is evaluating the acceptability of resuning '
operation with a loose thermal sleeve in the bottom of the reactor vessel, as discussed in last month's report.
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2 It appears from operating experience that make-up nozzle cracking only occurred where there was a corresponding loose thermal. sleeve, i.e. , an internal cylindri-
. cal shield designed- to protect the nozzle from thermal shocks. The B&W group has been requested to report on the cause of the cracking problem and present long-tenn solutions to prevent recurrence.
Auxiliary Feedwater Header Damage in Babcock and Wilcox (B&W)
Reactor Plants i During a scheduled outage'at Davis-Besse Unit 1, a visual inspection of a Steam )
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- Generator (SG) Internal Auxiliary Feedwater (AFW) header was perfonned. The
-header was found bowed inward. The support brackets were distorted and support pins were missing. Similar damage was found in both SG's. The other operating plants with a similar AFW header design are Rancho Seco and Oconee Unit 3.
Similar degradation:was found at these plants. Midland Units 1 and 2 presently under construction have the same auxiliary feedwater header design as the three operating plants noted above.
The defonnation of the internal header could impact AFW system safety and reliability. In addition,'the structural integrity of header and potential damage to the tubes from the loose parts is being evaluated. The affected plants are !
shut down.
Bab'co'ck & Wilcox (B&W) is presently evaluating this problem and will recommend corrective actions to the licensees. The owners of the affected plants are expected to meet with the staff this month to present their preliminary analysis of the- problem and repair plan.
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p Nirie-Mile' Point Unit 1 Safe-End Cracks On March' 23, 1982, a hydrostatic test revealed leakage in recirculation loop safe-ends. A meeting was held on April 22, 1982 with Niagara Mohawk Power
- Corporation 'to discuss the -present status of Nine Mile Point Nuclear Plant, and the licensee's intentions for decontamination of the recirculation system.
l The reactor. of the Nine Mile plant has been defueled and all fuel and control rods have been placed in the spent fuel pool. All five recirculation loops have been j decontaminated between loop isolation valves. The licensee has estimated a one-year outage to replace all recirculation system safe-ends. A mid-May L
l . commencement of drywell work is presently planned.
Niagara Mohawk has not reached a decision regarding the extent of decontamina-tion, i.e., whether to include the lower portion of the reactor vessel during
( recirculation system decontamination. On May 10,1982, the NRC staff approved <
partial decontamination of the recirculation system.
The licensee has been required to submit details of the Nine Mile Point Unit 1 l
work before significant.and irreversible programs are undertaken.
l l The NRC staff-is continuing to evaluate this issue on the four other i
! i l-BWR's with operating licenses which have unciad sensitized stainless l steel safe-ends. Of these, Dresden Unit 1 and Humboldt Bay are in l
l : extended ' shutdown and are not scheduled to operate before 1986. The licensees of the other two facilities, Big Rock Point and Dresden Unit 2, f have' been requested to. identify the actions they intend to take to imple-I ment the ' recommendations, with respect to minimizing safe-end stress corrosion cracking, of. NUREG-0313, " Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping."
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OPERAT.ING LICENSE APPLICATf0NS
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', Licensing Schedules During the_ past month, the staff continued its review and processing of a 1 number. of operating license applications. The present licensing schedule for allc. plants with pending OL applications is given in Table 1. Pl ants - 1 are listed chronologically--according to Commission decision date. The ]
schedules shown for CY 1983 plants.and- beyond are based on standard assump-tions for review and hearing. times, except for those plants that are expected to be. heavily contested (Seabrook Unit 1, Byron Unit 1, and Midland Unit 2). For those plants, the projected schedules allow for a 13-month (rather than the typical 11-month) hearing phase from issuance of the Staff Supplemental Safety Evaluation Report (SSER) to Commission decision date on a full-power license. The staff review process for those cases has been accelerated to compensate for the additional time allotted for the hearing process, i
The estimated regulatory delays and the target dates for Commission decision shown in Table 1 do not reflect any. potential impact from the schedules for FEMA findings on off-site' emergency preparedness. Any additional potential-delays, based on the staff's. analysis of the schedules for the FEMA findings, are included in a monthly report to the Sen' ate Subcommittee on Nuclear ~ j i
Regulation,' which is transmitted jointly by the NRC and FEMA. !
On April .17,1982, the Director, Office of Nuclear Reactor Regulation, 1 issued an operating license (limited to fuel loading and 51, power oper- l L
j ation) for.LaSalle Unit 1. As a condition to the operating license for i
LaSalle 1, the licensee shall complete an assessment of the reinforcing
-bars damaged.due to drilling and coring in concrete and the structural adequacy of the.off-gas building roof. The results will be reported to
.the NRC staff for review and approval prior to power operation following initial criticality and 0-power physics testing.
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t Recently, changes in the construction completion dates have been announced by the utilities for Grand Gulf Unit 1 (from April 1982 to May 1982),
Clinton Unit 1 (from January 1983 to January 1984), Catawba (from August 1983 to October 1984), and WNP-2 (from March 1983 to August 1983). Summer 1 has changed from May to July 1982 based on infonnation from the applicant. !
PLANT-BY-PLANT DISCUSSION OF DELAYED PLANTS The only plant presently projected to have a regulatory delay is Shoreham j j
Unit 1. The projected regulatory delay for Summer Unit 1 was eliminated due to a change in the applicant's expected construction completion date. Although l
Diablo Canyon Unit 1, San Onofre Unit 2, and Midland Unit 2 do not have a j i
projected regulatory delay, they are included in the discussion due to other l l
causes.
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- 1. San Onofre Unit 2 - The.NRC issued an operating license on February 16, 1982. It was restricted to 5% power in accordance with the ASLB decision.
On April 26, 1982, the Appeal Board denied the intervenor's request for a stay of the license (ALAB 673). Fuel loading has been completed. The startup test program is in progress. Slippages to date have resulted from leaking check valves. and other minor repairs. The unit is expected to be ready l 1
for operation above 5% power in late June. On May 14,1982, the ASLB issued an initial decision authorizing the issuance of a full-power operating license for San Onofre Units 2 and 3 subject to certain conditions relating to emergency I k planning deficiencies. Authorization of full-power operation for Unit 2 is currently projected for June 1982.
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- 2. Diablo Canyon Unit 1 - On March 4,- 1982 the Commission approved the approach to,be used for Phase I- of the . independent design verification program with certain modifications. Phase I-is required to' be completed before fuel loading can -be recommended. On March 19,198'. the staff accepted Teledyne Engineering Services as the manager ~ for.the program._ The NRC staff approved the Phase 1 plan 'on April 27th.- Jo -audit of the quality assurance program, including implementation, of PG&E and of seismic service-related contractors, has been completed by R. F. Reedy as a Teledyne subcontractor. The conclusions.
of this audit raise questions as to the adequacy of the PG&E quality assurance
. program in other than design activities. The staff has under consideration the question of expanding the scope of the reverification program required of this unit prior to fuel load. A decision on this issue will be made before currently ongoing activities in the Phase I program are completed.
'3. Summer Unit 1 - Based upon information from the applicant, the projected
- construction completion date for the facility is currently July 1982.
'This' eliminates the previously projected one-month delay for this facility.
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- 4. Shoreham Unit 1 - The hearing started May 4,1982 and is expected to continue through the summer and fall of 1982. A partial initial decision on all matters, except for off-site emergency planning, is projected for the end of December 1982 and a complete initial decision no earlier than March ~1983. Based on the applicant's current official estimated completion date, this projected. schedule would result in a licensing impact of at least three months and possibly six months. The extent
'of the impact will depend on whether the partial initial decision (projected for. December 1982) will allow for issuance of a license for fuel load and operations at less than 5% power.-
- 5. Midland 2 - The Midland SER was issued-in May 1982. ACRS meetings are_ expected _to commence the second week in June 1982. On the basis of these two milestones, the first Supplemental SER (SSER) is scheduled for July 1982. Concurrent with the OL licensing effort, a series of ASLB hearings relating to the soils settlement problems are being held. Pursuant to an ASLB Memorandum and Order on April 30, 1982, the staff is issuing Amendment 3 to the CP's to require the appli-
- cant to obtain explicit prior NRC staff approval before proceeding with
- soils-related activities.
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Construction Permit Applications On March 2,1982, Duke Power Company requested cancellation of the CP application for Perkins Units 1, 2, and 3 without prejudice. A Board
- decision is' pending.
On April 9,1982, the lead applicant for Pebble Springs Units 1 and 2, Portland' General Electric Company, withdrew its application for a site certificate from the State of Oregon, and requested cancellation of the scheduled alternate sites hearing by the NRC.
t On December 31,1981, Puget Sound Power & Light Company submitted an amended Environmental Report and a Preliminary Safety Analysis Report (PSAR) amend-ment reflecting a relocation of the proposed Skagit/Hanford Nuclear Project (S/HNP) to the Hanford Reservation. The site relocation Draft Environmental Statement was issued in April 1982. The Final Environmental Statement is scheduled to be issued in August 1982. The staff is currently reviewing the PSAR amendment, and a Safety Evaluation Report Supplement is scheduled to be issued June 1982.
Clinch River Breeder Reactor The Clinch River Breeder Reactor (CRBR) plant applicants are currently pursuing a Limited Work Authorization which, if granted, would authorize
-the applicants to begin site preparation following the completion of public hearings on environmental and site suitability matters. A decision on the issuance of a Limited Work Authorization is scheduled for May 1983. ]
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, 1 The NRC staff is' currently reviewing the radiological health and safety ,
aspects of. the CRBR plant, as well as assessing the environmental impact of: the changes that have occurred since its FES was issued in 1977.
The presiding Atomic' Safety and Licensing Board has ordered that the public hearings commence on August 24, 1982. A prehearing. conference was held on April 20, 1982 to discuss the scope of safety issues for the Limited Work Authorization phase of the hearing. The Board agreed that the staff need consider the impact of a reactor of the size and type considered at-the Clinch River site for LWA (NEPA) purposes. A deposition ' session was held May 6,1982 to respond to intervenor interrogatories.
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The staff. met with the ACRS on May 4 5 and on May 24-25 in support of the CRBR safety review.
On May 14,1982, the Department of-Energy (D0E) requested reconsideration of Commission = action denying the DOE request for exemption. On May 17, 1982, the Commission rejected the DOE request for reconsideration.
Tables'
- 1. Licensing Schedules for Pending OL Applications
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