ML20212G650
| ML20212G650 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/15/1987 |
| From: | Conte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Blough A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8701210109 | |
| Download: ML20212G650 (5) | |
Text
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JAN f 5. '!987\\;
Docket No. 50-289 MEMORANDUM FOR: Allen R. Blough, Chief Reactor Projects Branch No. 1, DRP FROM:
Richard J. Conte, Chief Reactor Projects Section No lA, DRP s
SUBJECT:
TMI-1 STATUS REPORT FOR THE PERIOD DECEMBER 26, 1986 -
JANUARY 9, 1987 e
Enclosed.is,the biweekly status report from the NRC Resident Office at TMI-1 for the subject period. During this two week period, the NRC staff continued to monitor routine plant operations during cold shutdown and associated outage activities.
TMI-1 status reports are intended to provide NRC management and the public with highlights from an NRC regulatory perspective of TMI-1 activities for the previous two eeks.
Original Signed Byg Richard J. Conte, Chief Reactor Projects Section IA Branch 1, DRP i
Enclosure:
As stated
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0 0FFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
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F. Miraglia, NRR W. Travers, NRR J. Thoma, NRR J. Partlow, IE T. Gerushr,- BRP/ DER, Commonwealth of Pennsylvania R. Benko, Grvernor's Office ~of Policy, Commonwealth of Pennsylvania TMI Alert Susquehanna Valley Alliance Friends & Family of TMI H. Hucker A.-Herman C. Wolfe J. Johnsrud P. Smith C. Micka 1
D. Davenport J. Doroshow E. Harzler.
D, Davenport H. Spinelli Concerned Mothers and Women Public Document Room Local Public Document Room bec w/ enclosure:
K. Abraham, RI P. Lohaus, RI W. Kane, RI F. Young, RI (20 cys)
W. Baunack, RI Region I Docket Room (w/ concurrences)
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0FFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
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b ENCLOSURE TMI-1 STATUS REPORT FOR THE PERIOD DECEMBER 26, 1986 - JANUARY 9, 1987 1.
Plant Status As of 8:00 a.m. on January 9,1987, TMI-1 was in cold shutdown on' the IB-Train of Decay Heat Removal with reactor coolant temperature at 105 F and
-0 psig RCS pressure. On January 2, 1987, the licensee commenced refueling operations. The transfer canal inside the Reactor Building (RB) has been flooded to support refueling operations. Water level in the transfer canal is being maintained at approximately 23 feet above the the reactor vessel flange.
Refueling operations are expected to be completed during the week of January 12, 1987.
2.
Facility Work Summary The plant was maintained in cold shutdown throughout the period. The li-censee completed installation and testing of the Fuel Handling Building (FHB) Engineered Safeguard Features (ESF) ventilation system, which was required to be operational prior to refueling.
Fuel shuffling and fuel handling was being conducted in preparation for refueling activities.
Work continues on modifications with respect to upgrading fire protection and the emergency feedwater systems. The licensee continued work on major secondary components; i.e., the main turbine and main feedwater pumps.
Planned outage work is on schedule in anticipation of a mid to late March 1987 startup.
3.
Items of Special Interest Meeting with TMIA Representative On January 8, 1987, the senior resident and a resident inspector met with Mr. Eric Epstein, Three Mile Island Alert (TMIA). The meeting was held at Mr. Epstein's request to discuss general questions that were of concern to members of TMIA.
In general, the questions dealt with the last SALP report, the last Performance Appraisal Team (PAT) inspection, and special interest items described in previous TMI-1 Status Reports.
Systematic Assessment of Licensee Performance (SALP)
The NRC Region I SALP board met on December 3, 1986, to discuss licensee performance between May 1, 1986, and October 31, 1986. This report was issued on Jcnuary 5, 1987, and copies of this document are available from the TMI-1 NRC Resident Office. To obtain a copy of the SALP report, members of the general public may contact Ms. C. Hix at 948-1160 during the hours of 7:01 a m. to 3:30 p.m.
This SALP is the third of three SALP reports conducted by Region I in 1986 and the final report for the two Commission directed SALP's in their restart order. A management meeting 0FFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
11/29/80
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between NRC and GPUN to discuss the SALP is scheduled for February 24, 1987 at 1:00 p.m. in the GPU Nuclear Media Center, 99 South Cameren Street, Harrisburg, PA. The meeting is open to the public. Further a meeting between NRC staff and members of the the public is scheduled for 7:00 p.m., February 24, 1987, to discuss comments and questions on the SALP Report and the management meeting held earlier in the day. The meeting is to be held at the NRC's Middletown Office, 100 Brown Street (at the Downtown Mall) in Middletown, PA.
4.
Denial of Technical Specification Amendment Request:
Use of Fracture Mechanics Methods to Justify OTSG Tube Plugging Criteria On December 23, 1986, the Office of Nuclear Reactor Regulation (NRR) denied Technical Specification Change Request No. 148 that addressed changing the tube plugging criteria for TMI-1 Once-Through Steam Generators (OTSG's).
The denial was based on the NRC staff's concerns on the use of fracture mechanics methodology to be used to justify OTSG tube plugging criteria.
The staff did not agree with GPUN analyses and assumptions in the areas of load development, material properties, and calculation techniques. The result of this action will be to deny the licensee the use of a 70 percent throughwall degradation as the tube plugging criteria. At present, tubes must be removed from service when degradation exceeds 40 percent throughwall.
5.
NRC Staff Activities During the Period During this report period, the NRC staff consisted of the senior resident inspector and two resident inspector.
Two region-based inspectors were on site part time to conduct a review of FHB ESF testing and to witness portions of refueling operations.
Inspection Report Nos. 50-289/86-17 and 86-19 were issued December 31, 1986, and January 7,1987, respectively. These reports evaluated the licensee's plant operations for the period of September 8, to October 3, 1986, and October 3 to October 31, 1986, respectively.
Inspection Report No. 50-289/86-17 identified three apparent violations of NRC requirements.
The first concerned the improper implementation of procedures for conduct-ing surveillance testing of Engineered Safeguards Features systems. This resulted in the isolation of cooling water to a high pressure injection pump for about eighteen hours.
Contributing to this event was the lack of proper independent verification of a valve lineup that should have been used to restore systems to normal when the test was interrupted. The second apparent violation concerned to examples of failure to properly translate design basis into procedural requirements. In one case, there was no procedure to ensure that the Reactor Building equipment hatch missile barrier was in place prior to power operations, which resulted in the barrier being repositioned several days after startup. In the second case, the licensee failed to document the design basis for several new radiation monitors. The last violation concerned the licensee's failure to properly document in a written safety evaluation a change in facility components.
In this case, one of two channels of source range nuclear instrumentation was made inoperable when the power supply cable was improperly connected.
OFFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT i
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3 In an apparent violation documented in Inspection Report No. 50-289/86-19, the licensee failed to properly document an assessment of the radiation doses from plant effluents to individuals inside the site boundary as re-quired by technical specifications. This information should have been reported in the Semi-Annual Effluent Release Report.
Information regard-ing does assessment for individuals off-site was reported as required, however.
The NRC staff at TMI-1 was comprised of the following personnel during the period.
C. Hix, Secretary D. Johnson, Resident Inspector M. Miller, Radiation Specialist, Region I (RI)
J. Prell, Reactor Engineer, RI J. Rogers, Resident Inspector F. Young, Senior Resident Inspector i
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