ML20198A869
| ML20198A869 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/22/1985 |
| From: | Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8511060205 | |
| Download: ML20198A869 (16) | |
Text
. _.
OCT 2 21985 Docket No. 50-289 MEMORANDUM FOR: Thomas E. Murley, Regional Administrator Region I THRU:
Richard W. Starostecki, Director Division of Reactor Projects FROM:
William F. Kane, Director TMI-1 Restart Staff
SUBJECT:
TMI-1 STATUS REPORT FOR THE PERIOD OCTOBER 11-18, 1985 The enclosure is the second of a series of weekly status reports of the TMI-l Restart Staff. These reports are intended to provide NRC management and the public with highlights from an NRC regulatory perspective of the THI-1 restart activities for the previous week. Subsequent inspection reports will address these topics in more detail.
The eaclosed report covers the period from 8:00 a.m.,
October 11 to 8:00 a.m.,
October 18, 1985. We will continue to !ssue weekly status reports for the duration of THI-l Restart Staff activities. An overview of the chronological status of the restart effort is shown on the figure which is attached to this report.
I W
\\
William F. Kane, Director TMI-1 Restart Staff
Enclosure:
As stated i
0511060205 851022 PDR ADOCK 050 29 l
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T. Murley OCT 2 2 1985 cc w/ enclosure:
V. Stello, DEDROGR H. Denton, NRR J. Taylor, IE N. Grace, Region II J. Keppler, Region III R. Martin, Region IV J. Martin, Region V H. Thompson, NRR W. Travers, NRR J. Thoma, NRR J. Partlow, IE F. Combs, CA R. Walker, Region II R. Denise, Region IV C. Smyth, GPU Nuclear T. Gerusky, BRP/ DER, Commonwealth of Pennsylvania R. Benko, Governor's Office of Policy, Commonwealth of Pennsylvania Public Document Room Local Public Document Room bec w/ enclosure:
J. Allan, RI K. Abraham, RI P. Lohaus, RI R. Starostecki, RI T. Martin, RI S. Ebneter, RI H. Kister, RI R. Conte, RI (5 cys)
F. Young, RI D. Haverkamp, RI Region I Docket Room (w/ concurrences)
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tarostecki 10/21/85 410/2i/85 10/7g/85 10 85 l-
ENCLOSURE TMI-1 STATUS REPORT FOR THE PERIOD OCTOBER 11-18, 1985 1.
Plant Status As of 8:00 A.M. on October 18, 1985, THI-1 was at 7% reactor power and steaming the secondary plant to the main condenser using the turbine bypass valves. Weld failures in two drain lines from the main turbine control valve headers were delaying continued testing at the 40% power plateau.
2.
Test Program Status The licensee's planned test program and current status for restart of TMI-1 are shown on the attached figure. Subsequent to the repair of the auxiliary boiler tubes, the overspeed test of the main turbine generator was satisfactorily completed. Also, data taking and related surveillance and operational checkout of equipment were completed and evaluated by the licensee at the 15% and 25% power plateaus. Activities scheduled for the next week include testing at the 40% power plateau which is to conclude with a test involving loss of main feedwater, followed by a reactor trip and turbine trip and additional natural circulation testing. Following that, there is another NRC hold point. If released from the next NRC hold point, the licensee's program calls for operation at the 48% power plateau for approximately one month. The licensee informed the TMI-1 Restart Staff that it did not plan to escalate reactor power above the 48% plateau until after the annual emergency exercise on November 20, 1985.
3.
Facilitv Operations Summary As noted above, testing has progressed up to the 40% power plateau.
Throughout this period, there were several power reductions to 5-10%
reactor power during which steam was bypassed to the condenser using the turbine bypass valves while repairs were made to the weld failures in two of the drain lines from the four main turbine control valve headers (see section 4).
On October 16, 1985, the licensee replaced one of the two alternating current breakers in the reactor protection system. The breaker had been sent to the manufacturer for inspection as a followup action to the failure of a similar breaker that occurred on September 23, 1985. The breaker was inspected by the manufacturer and determined to be acceptable.
Unrelated to the above activities, the licensee continued to receive new fuel assemblies for subsequent refuelings. On October 15, 1985, twelve new fuel assemblies were received.
2 4.
Items of Special Interest NRC Notifications During the period, there were no events that required notification of NRC by the licensee. There were, however, a number of other events of interest and they are discussed.
Emergency Feedwater System Safetv Valves In followup to the discovery that safety valves on the steam supply line to the turbine-driven emergency feedwater (EFW) pump were lifting during startup of the system, the licensee issued interim guidance to operators on what to do in the event that a safety valve sticks open. The THI-1 Restart Staff is evaluating the adequacy of this guidance. A proposed final resolution by the licensee to minimize challenges to these valves will be provided prior to startup following the planned trip from 100%
power scheduled to occur in about three months.
Main Turbine Control Valve Drain Line Weld Failures As discussed earlier, the licensee's test program was delayed due to weld failures in drain lines associated with the main turbine control valves.
The piping between turbine control valves and the high pressure turbine contains moisture drain lines which are one-inch in diameter. The drain lines from two of these lines contained a strainer and an orifice which were installed during initial construction in the early 1970's. The other two drain lines consisted of straight pipe and contained no such strainer or orifice.
Based on problems at other plants in 1983, General Electric recommended changing the method 'f admitting steam to the high pressure end of the o
turbine. This involved some modifications in turbine controls and the removal of the strainer and orifice from the two drain lines. This was accomplished prior to the current startup; however, the strainer housings were left in place. On October 9, 1985, a steam leak developed in a weld in one of the drain lines upstream of its strainer housing. The leak became progressively worse necessitating a turbine shutdown. The leak was repaired on October 12 by welding a " clam shell" cover over the defective weld. During the remainder of the period, there were three additional weld failures in this line including two field repair welds and a shop weld.
In addition, there was one weld failure in the other drain line that contained a strainer housing. Each of these failures necessitated removal of the turbine generator from the grid and a reduction of reactor power to about 5-10% of rated power. The licensee has identified the failure mechanism as high cycle fatigue with no
'i evidence of corrosion. At the conclusion of the period, the licensee in i
conjunction with General Electric, was developing a design modification to attempt to correct the problem.
3 NRC Thermoluminescent Dosimeter (TLD) Monitoring Program The NRC Region I staff implemented a special monitoring program in the vicinity of the TMI site on June 11, 1985, following the Commission's decision on TMI-1 restart. The TLD device is used to measure the radiation levels in the environment. There are 29 TLD stations used in this special monitoring program, which is supplemental to the 50 TLD stations used for the NRC's routine quarterly monitoring program. The supplemental TLDs are exchanged with a new set of TLDs every two weeks.
The biweekly TLDs for the period October 2 - October 18, 1985, were collected on October 18 and will be processed at the Region I TLD laboratory. The monitoring results will be included in the next weekly status report.
Gaseous Radioactive Releases from Main Condenser Offgas System The licensee's program for quantifying and controlling gaseous radioactive releases that have occurred via the condenser offgas system during the startup of Unit I was reviewed during this period. Currently, primary to secondary leakage is occuring at the rate of approximately 0.2 gallons per hour, which results in detectable activity in the condenser offgas system. The measured concentration is -5.0 E-7 uCi/ml, consisting primarily of Xe-133, Xe-135 and non-condensible gases. These gases are concentrated in the condenser and discharged to the environment via the condenser offgas system. The condenser offgas is continuously monitored and recorded.
Technical Specifications limit the air dose due to noble gases released in gaseous effluents during any calendar year to 1 10 mrad for gamma radiation and 1 20 mrad for beta radiation. The following is a summary of the total activity released via this pathway between October 8 and
)
October 16, 1985:
Total Activity Released: -3279 uCi, Xe-133; ~5624 uCi, Xe-135 Cumulative Air Dose at the Site Boundary:
-2.2 E-5 mrad, gamma; -3.2 E-5 mrad, beta Fraction of Yearly Technical Specification Limits:
-0.00022% of the gamma air dose limit t
-0.00016% of the beta air dose limit Other Items The Commonwealth of Pennsylvania's Bureau of Radiation Protection terminated their 24-hour coverage at the plant on October 11, 1985.
However, it has continued to provide coverage on the day shift.
1 4
5.
TMI-1 Restart Staff Status Durina Period The TMI-l Restart Staff continued 24-hour shift coverage throughout the period.
The shifts were manned by personnel from Regions I, II and IV and by reactor operator examiners from Battelle Pacific Northwest
)
Laboratories, an NRC contractor. Also, Region I startup inspectors l
continued daily coverage consistent with the reduced testing activity.
Additional Region I personnel were on site during portions of the period to augment the resident inspection staff and included a reactor engineer, a senior radiation specialist, and an operator examiner.
The staff-developed inspection plans, which continue to be issued weekly, are sufficiently flexible to cover the unique activities conducted by the licensee. The inspection plan for this period covered the primary 4
functional areas of operations, maintenance, surveillance, startup testing, licensed operator requalification, and radioactive effluent monitoring. The shift inspectors assessed operator performance and organizational interfaces on each shift.
In addition, the resident and region-based inspectors followed the various off-normal events identified by the shift inspectors and assisted in the verification of proper procedural implementation during special test evolutions. The startup test inspectors monitored the program to assure that test procedures were properly implemented and that test data were in accordance with test acceptance criteria.
i i
The TMI-1 Restart Staff continued to evaluate the performance of licensee personnel and the plant to determine whether the licensee should be permitted to proceed beyond the next hold point.
That hold point is prior to startup following a reactor trip at 40% power. However, this evaluation was interrupted by the several secondary system steam header drain line leaks that occurred during the period.
It appears that the next hold point could be reached as early as October 22, 1985.
Contact with the press and public continued throughout the period. There have been several calls each day and these have been handled by THI-1 Restart Staff management. The Region I Public Affairs Officer (PAO) remained at the Region I office.
We have continued to maintain contact with the Commonwealth of Pennsylvania during this period. The Director of the Governor's Office 4
of Policy is briefed each morning by the TMI-l Restart Staff Director on j
the status of the plant and any problems that have been experienced. In addition, we have held frequent technical interchanges with the Commonwealth of Pennsylvania's Bureau of Radiation Protection engineers that are on site.
During the period, the TMI-l Restart Staff continued to issue daily highlights to the Executive Director for Operations. Also, Inspection Report 50-289/85-21 for the period August 2 - September 16, 1985 was issued on October 15, 1985. On October 16, 1985, Region I issued Preliminary Notification PNO-I-85-79 regarding interruption of the power escalation program due to the main turbine drain line leak. The first l
weekly status report for the period October 3-11, 1985, was issued by the TMI-1 Restart Staff on October 17, 1985.
i
5 6.
TMI-1 Restart Staff Composition During Period The TMI-1 Restart Staff was comprised of the following personnel during the period:
W. F. Kane, TMI-1 Restart Director R. J. Conte, TMI-1 Restart Manager D. R. Haverkamp, Technical Assistant F. I. Young, Resident Inspector, THI-1 N. F. Dudley, Lead Reactor Engineer (Examiner)
R. J. Urban, Reactor Engineer N. J. Blumberg, Startup Inspector P. C. Wen, Startup Inspector J. R. White, Senior Radiation Specialist J. E. Cummins, Shift Inspector, Region IV D. P. Falconer, Jr., Shift Inspector, Region II B. Gore, Shift Inspector, Battelle PNL J. Huenefeld, Shift Inspector, Battelle PNL W. D. Johnson, Shift Inspector, Region IV T. Peebles, Shift Inspector, Region II D. J. Vito, Shift Inspector 1
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OCT 2 2 1985 Docket No. 50-289 MEMORANDUM FOR: Thomas E. Murley, Regional Administrator Region I THRU:
Richard W. Starostecki, Director Division of Reactor Projects FROM:
William F. Kane, Director TMI-1 Restart Staff
SUBJECT:
TMI-l STATUS REPORT FOR THE PERIOD OCTOBER 11-18, 1985 The enclosure is the second of a series of weekly status reports of the TMI-l Restart Staff. These reports are intended to provide NRC management and the public with highlights from an NRC :egulatory perspective of the TM1-1 restart activities for the previous week. Subsequent inspection reports will address these topics in more detail.
The enclosed report covers the period from 8:00 a.m.,
October 11 to 8:00 a.m.,
October 18, 1985. We will continue to issue weekly status reports for the duration of TMI-l Restart Staff activities. An overview of the chronological status of the restart effort is shown on the figure which is attached to this report.
~
William F. Kane, Director TMI-l Restart Staff
Enclosure:
As stated 1
'Ie
$5 31
T. Murley DCT 2 2 1985 cc w/ enclosure:
V. Stello, DEDROGR H. Denton, NRR J. Taylor, IE N. Grace. Region II J. Keppler, Region III R. Martin, Region IV J. Martin, Region V H. Thompson, NRR W. Travers, NRR J. Thoma, NRR J. Partlow, IE F. Combs, CA R. Walker, Region II R. Denise, Region IV C. Smyth, GPU Nuclear T. Gerusky, BRP/ DER, Commonwealth of Pennsylvania R. Benko, Governor's Office of Policy, Commonwealth of Pennsylvania Public Document Room Local Public Document Room bec w/ enclosure:
J. Allan, RI K. Abraham, RI P. Lohaus, RI R. Starostecki, RI T. Martin, RI S. Ebneter, RI H. Kister, RI R. Conte, RI (5 cys)
F. Young, RI D. Haverkamp, RI Region I Docket Room (w/ concurrences)
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ENCLOSURE TMI-l STATUS REPORT FOR THE PERIOD OCTOBER 11-18, 1985 1.
Plant Status As of 8:00 A.M. on October 18, 1985, TMI-1 was at 7% reactor power and steaming the secondary plant to the main condenser using the turbine bypass valves. Weld failures in two drain lines from the main turbine control valve headers were delaying continued testing at the 40% power plateau.
2.
Test Program Status The licensee's planned test program and current status for restart of TMI-1 are shown on the attached figure. Subsequent to the repair of the-auxiliary boiler tubes, the overspeed test of the main turbine generator was satisfactorily completed. Also, data taking and related surveillance and operational checkout of equipment were completed and evaluated by the licensee at the 15% and 25% power plateaus. Activities scheduled for the next week include testing at the 40% power plateau which is to conclude with a test involving loss of main feedwater, followed by a reactor trip and turbine trip and additional natural circulation testing.
Following that, there is another NRC hold point. If released from the next NRC hold point, the licensee's program calls for operation at the 48% power plateau for approximately one month. The licensee informed the TMI-1 Restart Staff that it did not plan to escalate reactor power above the 48% plateau until after the annual emergency exercise on November 20, 1985.
3.
Facility Operations Summary As noted above, testing has progressed up to the 40% power plateau.
Throughout this period, there were several power reductions to 5-10%
reactor power during which steam was bypassed to the condenser using the turbine bypass valves while repairs were made to the weld failures in two of the drain lines from the four main turbine control valve headers (see section 4).
On October 16, 1985, the licensee replaced one of the two alternating current breakers in the reactor protection system. The breaker had been sent to the manufacturer for inspection as a followup action to the failure of a similar breaker that occurred on September 23, 1985. The breaker was inspected by the manufacturer and determined to be acceptable.
Unrelated to the above activities, the licensee continued to receive new fuel assemblies for subsequent refuelings. On October 15, 1985, twelve new fuel assemblies were received..
. _ - -. -.. _, -.-,~.
2 i
4.
Items of Special Interest I
NRC Notifications During the period, there were no events that required notification of NRC by the licensee. There were, however, a number of other events of l
interest and they are discussed.
Emergency Feedwater System Safety Valves In followup to the discovery that safety valves on the steam supply line to the turbine-driven emergency feedwater (EFW) pump ucre lifting during startup of the system, the licensee issued interim guidance to operators 1
on what to do in the event that a safety valve sticks open. The THI-1 Restart Staff is evaluating the adequacy of this guidance. A proposed final resolution by the licensee to minimize challenges to these valves will be provided prior to startup following the planned trip from 100%
power scheduled to occur in about three months.
Main Turbine Control Valve Drain Line Weld Failures
]
As discussed earlier, the licensee's test program was delayed due to weld failures in drain lines associated with the main turbine control valves.
The piping between turbine control valves and the high pressure turbine contains moisture drain lines which are one-inch in diameter. The drain i
liner from two of these lines contained a strainer and an orifice which j
were installed during initial construction in the early 1970's.
The other two drain lines consisted of straight pipe and contained no such strainer or orifice.
Based on problems at other plants in 1983, General Electric recommended changing the method ' f admitting steam to the high pressure end of the o
turbine. This involved some modifications in turbine controls and the removal of the strainer and orifice from the two drain lines. This was accomplished prior to the current startup; however, the strainer housings j
were left in place. On October 9, 1985, a steam leak developed in a weld in one of the drain lines upstream of its strainer housing. The leak became progressively worse necessitating a turbine shutdown. The leak was repaired on October 12 by welding a " clam shell" cover over the defective weld. During the remainder of the period, there were three 4
additional weld failures in this line including two field repair welds and a shop weld.
In addition, there was one weld failure in the other drain line that contained a strainer housing.
Each of these failures necessitated removal of the turbine generator from the grid and a reduction of reactor power to about 5-10% of rated power. The licensee has identified the failure mechanism as high cycle fatigue with no evidence of corrosion. At the cenclusion of the period, the licensee in conjunction with General Electric, was developing a design modification to attempt to correct the problem.
i i
I I
i
3 NRC Thermoluminescent Dosimeter (TI.D) Monitoring Program The NRC Region I 1taff implemented a special monitoring program in the vicinity of the TMI site on June 11, 1985, following the Commissior,'s decision on TM1-1 restart. The TLD device is used to measure the radiation levels in the environment.
There are 29 TLD stations used in this special monitoring program, which is supplemental to the 50 TLD stations used for the NRC's routine quarterly monitoring program. The supplemental TLDs are exchanged with a new set of TLDs every two weeks.
The biweekly TLDs for the period October 2 - October 18, 1985, were collected on October 18 and will be processed at the Region I TLD laboratory. The monitoring results will be included in the next weekly status report.
Gaseous Radioactive Releases from Main Condenser Offgas System The licensee's program for quantifying and controlling gaseous radioactive releases that have occurred via the condenser offgas system during the startup of Unit I was reviewed during this period. Currently, primary to secondary leakage is occuring at the rate of approximately 0.2 gallons per hour, which results in detectable activity in the condenser offgas system. The measured concentration is -5.0 E-7 uCi/ml, consisting primarily of Xe-133, Xe-135 and non-condensible gases. These gases are concentrated in the condenser and discharged to the environment via the condenser offgas system. The condenser offgas is continuously monitored and recorded.
Technical Specifications limit the air dose due to noble gases released in gaseous effluents during any calendar year to $ 10 mrad for gamma radiation and 1 20 mrad for beta radiation. The following is a summary of the total activity released via this pathway between October 8 and October 16, 1985:
Total Activity Released:
-3279 uCi, Xe-133; -5624 uCi, Xe-135 Cumulative Air Dose at the Site Boundarv:
-2.2 E-5 mrad, gamma; -3.2 E-5 mrad, beta Fraction of Yearly Technical Specification Limits:
-0.00022% of the gamma air dose limit
-0.00016% of the beta air dose limit Other Items The Commonwealth of Pennsylvania's Bureau of Radiation Protection terminated their 24-hour coverage at the plant on October 11, 1985.
Ilowever, it has continued to provide coverage on the day shift.
4 5.
THI-l Restart Staff Status During Period The TMI-1 Restart Staff continued 24-hour shift coverage throughout the period.
The shifts were manned by personnel from Regions I, II and IV and by reactor operator examiners from Battelle Pacific Northwest Laboratories, an NRC contractor. Also, Region I startup inspectors continued daily coverage consistent with the reduced testing activity.
Additional Region I personnel were on site during portions of the period to augment the resident inspection staff and included a reactor engineer, a senior radiation specialist, and an operator examiner.
The staff-da reloped inspection plans, which continue to be issued weekly, are sufficiently flexible to cover the unique activities conducted by the licensee. The inspection plan for this period covered the primary functional areas of operations, maintenance, surveillance, startup testing, licensed operator requalification, and radioactive effluent monitoring. The shift inspectors assessed operator performance and organizational interfaces on each shift.
In addition, the resident and region-based inspectors followed the various of f-normal events identified by the shift inspectors and assisted in the verification of proper procedural implementation during special test evolutions. The startup test inspectors monitored the program to assure that test procedures were properly implemented and that test data were in accordance with test acceptance criteria.
The TMI-1 Restart Staff continued to evaluate the performance of licensee personnel and the plant to determine whether the licensee should be permitted to proceed beyond the next hold point. That hold point is prior to startup following a reactor trip at 40% power. However, this evaluation was interrupted by the several secondary system steam header drain line leaks that occurred during the period.
It appears that the next hold point could be reached as early as October 22, 1985.
Contact with the press and public continued threughout the period. There have been several calls each day and these have been handled by THI-1 Restart Staff management. The Region I Public Affairs Officer (PAO) remained at the Region I office.
We have continued to maintain contact with the Commonwealth of Pennsylvania during this period. The Director of the Governor's Office of Policy is briefed each morning by the THI-1 Restart Staff Director on the status of the plant and any problems that have been experienced.
In addition, we have held frequent technical interchanges with the Commonwealth of Pennsylvania's Bureau of Radiation Protection engineers that are on site.
During the period, the TMI-1 Restart Staff continued to issue daily highlights to the Executive Director for Operations. Also, Inspection Report 50-289/85-21 for the period August 2 - September 16, 1985 was issued on October 15, 1985. On October 16, 1985, Region I issued Preliminary Notification PNO-I-85-79 regarding interruption of the power escalation program due to the main turbine drain line Icak. The first weekly status report for the period October 3-11, 1985, was issued by the TMI-l Restart Staff on October 17, 1985.
s
5 6.
TMI-l Restart Staff Composition During Period The TMI-l Restart Staff was ccmprised of the following personnel during the period:
W. F. Kane, TMI-1 Restart Director R. J. Conte, TMI-l Restart Manager D. R. Haverkamp, Technical Assistant F. I. Young, Resident Inspector, THI-l N. F. Dudley, Lead Reactor Engineer (Examiner)
R. J. Urban, Reactor Engineer N. J. Blumberg, Startup Inspector P. C. Wen, Startup Inspector J. R. White, Senior Radiation Specialist J. E. Cummins, Shift Inspector, Region IV D. P. Falconer, Jr., Shift Inspector, Region II B. Gore, Shift Inspector, battelle PNL J. Huenefeld, Shift Inspector, Battelle PNL W. D. Johnson, Shift Inspector, Region IV T. Peebles, Shift Inspector, Region II D. J. Vito, Shift Inspector 1,
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