ML20212B095
| ML20212B095 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/19/1986 |
| From: | Conte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Blough A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8612290168 | |
| Download: ML20212B095 (5) | |
Text
,
i DEC 191996 Docket No. 50-289 MEMORANDUM FOR: Allen R. Blough, Chief Projects Branch No. 1 FROM:
Richard J. Conte, Chief Reactor Projects Section 1A
SUBJECT:
TMI-1 STATUS REPORT FOR THE PERIOD NOVEMBER 28 -
DECEMBER 12, 1986 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 weeks.
Original sisnod l'y Richard J. Conte, Chief Reactor Projects Section 1A Branch 1, DRP
Enclosure:
As stated cc w/ enclosure:
F. Miraglia, NRR W. Travers, NRR J. Thoma, NRR J. Partlow, IE DbNok$$$89 PDR OFFICIAL RECORD COPY TMI1 WEEKLY STATUS REPORT -
11/29/80 NO g
Allen R. Blough 2
cc w/ enclosure:
(Continued)
T. Gerusky, BRP/ DER, Commonwealth of Pennsylvania R. Benko, Governor'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 E. Harzler D. Davenport Concerned Mothers and Women Public Document Room Local Public Document Room bec w/ enclosure:
K. Abraham, RI P. Lohaus, RI W. Kane, RI H. Kister, RI i
F. Young, RI (20 cys)
W. Baunack, RI R. Freudenberger, RI Region I Docket Room (w/ concurrences)
RIhl RI:DRP Conth Blough i
12//,f/86 12//l/86 0FFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
11/29/80 l
ENCLOSURE TMI-I STATUS REPORT FOR THE PERIOD NOVEMBER 28 - DECEMBER 12, 1986 1.
Plant Status As of 8:00 a.m. on December 12, 1986, TMI-1 was in cold shutdown on the 18-Train of Decay Heat Removal with reactor coolant temperature at 105* F and 0 psig RCS pressure. Reactor vessel (RV) water level is being main-tained at 10-18 inches above the center line of the RV cold leg inlet piping.
2.
Facility Work Summary The plant was maintained in cold shutdown throughout the period. The li-censee completed eddy current testing and 0TSG tube plugging evolutions as discussed below.
Reactor Coolant Pump (RCP) seal work continued with the completion of the "C" RCP and commencement of work on the "A" and "D" RCP seal packages. Work was also in progress on the cleaning of various 480 V a.c. electrical busses.
The "A" emergency diesel generator was taken out of service for the annual inspection. The diesel will be disassembled with a major overhaul being completed on the pistons and cylirders. The licensee also completed shipping of the high pressure turbine rotor to a General Electric facility in Philadelphia. The rotor will under go exten-sive examination and repair. Work continues on modifications with respect to upgrading fire protection and emergency feedwater system to safety grade.
In addition, work continued in the area of refueling preparations and in-stallation of engineered safety features ventilation system for the fuel handling building.
3.
Items of Special Interest Steam Generator Tube Plugging The licensee completed required eddy current testing (ECT) of both steam generator tubes.
In addition to the required Technical Specification sampling of tubes to be tested, a group of tubes, which are under special surveillance for each ECT, was also tested. One indication of greater than 40 percent throughwall defect on one tube in the initial 3 percent sample in both steam generators required the licensee to perform a second 3 percent sample of tubes in both Once-Through Steam Generators (OTSG's).
An indication greater than 40 percent on one tube in the second 3 percent sample in the "B" 0TSG required required an additional six percent sample (third sample group) inspection in the "B" OTSG.
No indications greater than 40 percent throughwall were noted in the second 3 percent sample in-spection in the "A" OTSG or the third sample inspection of the "B" OTSG.
The licensee is still in the process of evaluating the data that has been collected and will generate a final report after the data has been reviewed.
From the data, the licensee tentatively concluded thirty-nine tubes required removal from service.
In addition to plugging the tubes noted above, an additional 36 tubes will be plugged from the special surveillance group or, in general, to be conservative for tubes with data close to the 40 percent limit. The licensee has plugged nineteen tubes in the "A" 0TSG and twenty 0FFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
11/29/80
2 Enclosure tubes in the "B" 0TSG. At the end of the report period, the licensee was in the process of reinstalling the manway closures and re-establishing the reactor boundary associated with the OTSG's in preparation for refueling.
Systematic Assessment of License Performance (SAlp)
The NRC Region I SALP Board met at 10:30 a.m. on December 4, 1986, to assess the licensee's performance during the period of May 1, 1986, to October 31, 1986. The SALP Board's written report issuance is expected in about one month. This is the final NRC Commission-directed SALP that will be performed on a six-month basis. Assessment periods typically are performed on an annual basis and the next SALP for TMI-1 will be performed accordingly.
Non-Routine Release from the Reactor Building During periods of time on November 28 and 30, 1986, the Reactor Building (RB) purge was secured for work on the purge valve debris screens and for surveillance testing on RM-A-9.
A positive pressure buildup in the RB was experienced due to heat-up of the RB atmosphere.
Licensee radiological engineering personnel calculated that during these periods minor unmonitor-ed releases occurred out of the RB equipment hatch, which had been removed for the outage. Air flow was estimated to be approximately 100 cubic feet per minute (cfm) and, with the atmospheric sample results obtained from the RB atmosphere, the following releases were estimated by the licensee:
on November 18, 1986, 0.11 micro curies of Iodine 131 and 0.06 micro curies of Cobalt 58; and, on November 30, 1986, 0.02 micro curies of Iodine 131, 538 micro curies of tritium, and 6214 micro curies of Xenon 133. The first release represents 1.8 E-3 percent and the second release represents 4.33 E-4 percent of Technical Specifications quarterly limits.
Enforcement Conference on Environmental Qualification Issues On December 4, 1986, an Enforcement Conference was held in the NRC Region I office, King of Prussia, Pennsylvania, to di! cuss the findings of an investigation conducted by the NRC Office of Investigation concerning the deficiencies in the Equipment Qualification (EQ) Program at TMI-1 during the 1981 to 1984 time frame. The investigation determined that the li-censee's program for correcting EQ deficiencies internally identified by GPUN's Quality Assurance (QA) Department was ineffective and the the inter-face between the Technical Functions Department responsible for the EQ program, the QA Department, and the licensing individuals who prepared the correspondence was poor.
The meeting discussed apparent lack of sensitivity within the Technical Functions Department to the importance of QA findings and, also, the need for managers within the department to exhibit an increased sense of respon-sibility in (a) responding to problems identified by the QA Department as well as other personnel and (b) taking prompt and effective action to cor-rect the problems. The licensee presented their corrective actions and their analysis of the root cause.
The result of the conference will be documented in future correspondence.
-- j
1 3
Enclosure 4.
NRC Staff Activities During the Period During this report period, the NRC staff consisted of the senior resident-inspector and two resident inspectors. One region-based inspector was on site part time to conduct a review of inservice inspection activities.
On December 5, 1986, the on-site NRC staff conducted their monthly exit meeting with licensee personnel for Inspection Report No. 50-289/86-21.
Results of this inspection will follow in a subsequent report.
Inspection Report No. 50-289/86-20 was issued on December 1, 1986. This report evaluated the licensee's performance in conducting their annual emergency preparedness exercise, which was completed on November 5, 1986.
The licensee was evaluated as adequately prepared to provide protective measures for the health and safety of the public.
The NRC staff at TMI-1 was comprised of the following personnel during the period. The region-based inspector was on site part time.
C. Hix, Secretary D. Johnson, Resident Inspector A. Lodewyk, Reactor Engineer, Region I (RI), Part Time J. Rogers, Resident Inspector F. Young, Senior Resident Inspector l
OFFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
f 11/29/80
, _..__.. _ _,- _ _ _. _ __ __-._ _.__. _ _,