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=Text=
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A DEC 2 71995 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
A DEC 2 71995 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:==
==SUBJECT:==
TMI-1 STATUS REPORT FOR THE PERIOD DECEMBER 20-27, 1985 The enclosure is the twelfth of a series of weekly status reports of the TMI-1 Restart Staff. These reports are intended to provide NRC management and the public with highlights from an NRC regulatory perspective of the TMI-1 restart activities for the previous week. Subsequent inspection reports will address most of these topics in more detail.
TMI-1 STATUS REPORT FOR THE PERIOD DECEMBER 20-27, 1985 The enclosure is the twelfth of a series of weekly status reports of the TMI-1 Restart Staff. These reports are intended to provide NRC management and the public with highlights from an NRC regulatory perspective of the TMI-1 restart activities for the previous week. Subsequent inspection reports will address most of these topics in more detail.
The enclosed report covers the period from 8:00 a.m., December 20 to 8:00 a.m., December 27, 1985. We will continue to issue weekly status reports for the duration of TMI-1 Restart Staff activities. An overview of the chronolog-ical status of the restart effort is shown on the figure which is attached to this report.
The enclosed report covers the period from 8:00 a.m., December 20 to 8:00 a.m., December 27, 1985. We will continue to issue weekly status reports for the duration of TMI-1 Restart Staff activities. An overview of the chronolog-ical status of the restart effort is shown on the figure which is attached to this report.
W         -
W William F. Kane, Director TMI-1 Restart Staff
William F. Kane, Director TMI-1 Restart Staff


==Enclosure:==
==Enclosure:==
As stated y n85!P45 yg 3r i
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As stated y n85!P45                                                          yg 3r      ,
T. Murley.
i i
2 DEC 2 71985 cc w/ enclosure:
 
T. Murley.                               2 DEC 2 71985 cc w/ enclosure:
V. Stello, DEDROGR H. Denton, NRR J. Taylor, IE N. Grace, Region II.
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 F. Miraglia, NRR W. Travers, NRR J. Thoma, NRR J. Partlow, IE F. Combs, CA R. Walker, Region II E. Johnson, Region IV C. Smyth, GPU Nuclear 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 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 A. Blough, RI R. Conte, RI (20 cys)
J. Keppler, Region III R. Martin, Region IV J. Martin, Region V F. Miraglia, NRR W. Travers, NRR J. Thoma, NRR J. Partlow, IE F. Combs, CA R. Walker, Region II E. Johnson, Region IV C. Smyth, GPU Nuclear 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 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 A. Blough, RI R. Conte, RI (20 cys)
F. Young, RI D. Haverkamp, RI Region I Docket Room (w/ concurrences)
F. Young, RI D. Haverkamp, RI Region I Docket Room (w/ concurrences)
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4 ENCLOSURE TMI-1 STATUS REPORT FOR THE PERIOD DECEMBER 20-27, 1985
4 ENCLOSURE TMI-1 STATUS REPORT FOR THE PERIOD DECEMBER 20-27, 1985 1.
: 1.       Plant Status As of 8:00 a.m. on December 27, 1985, TMI-1 was at 85.7% of rated power.
Plant Status As of 8:00 a.m. on December 27, 1985, TMI-1 was at 85.7% of rated power.
: 2.       Test Program Status The licensee's planned test program and current status for restart of THI-l are shown on the attached Figure 1.                                               On December 24, 1985, the licensee completed the required 30 days of operation at the 75% power testing plateau. However, the licensee deferred power escalation until after Christmas. After release from the 75% hold point was granted by the Region I Administrator, at 4:20 a.m. on December 27, 1985, the licensee slowly increased power until reaching 85.7% of rated power at 8:00 a.m.             Shortly after 8:00 a.m., the licensee reached the high steam i                         generator limit (92%) and reactor power was limited to approximately 88%.
2.
Test Program Status The licensee's planned test program and current status for restart of THI-l are shown on the attached Figure 1.
On December 24, 1985, the licensee completed the required 30 days of operation at the 75% power testing plateau. However, the licensee deferred power escalation until after Christmas. After release from the 75% hold point was granted by the Region I Administrator, at 4:20 a.m. on December 27, 1985, the licensee slowly increased power until reaching 85.7% of rated power at 8:00 a.m.
Shortly after 8:00 a.m.,
the licensee reached the high steam i
generator limit (92%) and reactor power was limited to approximately 88%.
No operational problems occurred during the power escalation.
No operational problems occurred during the power escalation.
I                         Initial testing at the maximum achievable power level will include l                       routine steady-state tests (facility performance data review, heat j                         balance calculation, and integrated control system tuning) and an 1                         automatic power reduction (runback) test to 68% of rated power on                                                                                                 !
I Initial testing at the maximum achievable power level will include l
December 27, 1985.                     Following that test, the plant will be returned to the maximum achievable power level. The licensee plans to maintain the plant at the maximum achievable power level until noon on January 2,
routine steady-state tests (facility performance data review, heat j
;                        1986, when a planned reactor trip test will be conducted.
balance calculation, and integrated control system tuning) and an 1
: 3.       Facility Operations Summary Steady-state operation at 75% power continued until the power escalation on December 27, 1985.
automatic power reduction (runback) test to 68% of rated power on December 27, 1985.
: 4.       Items of Special Interest i                         NRC Notifications There were no events during the period that required notification of NRC pursuant to 10 CFR 50.72.
Following that test, the plant will be returned to the maximum achievable power level. The licensee plans to maintain the plant at the maximum achievable power level until noon on January 2, 1986, when a planned reactor trip test will be conducted.
3.
Facility Operations Summary Steady-state operation at 75% power continued until the power escalation on December 27, 1985.
4.
Items of Special Interest i
NRC Notifications There were no events during the period that required notification of NRC pursuant to 10 CFR 50.72.
Steam Generator Level Limit A.4 described in previous reports, the limiting parameter for escalation to full power was steam generator level due to fouling of steam generator tubes on the secondary side. As of about 9:00 a.m. on December 27, 1985, the licensee reached the 92% level limit which corresponded to 88%
Steam Generator Level Limit A.4 described in previous reports, the limiting parameter for escalation to full power was steam generator level due to fouling of steam generator tubes on the secondary side. As of about 9:00 a.m. on December 27, 1985, the licensee reached the 92% level limit which corresponded to 88%
4 reactor power. Prior to the power escalation, the TMI-1 Restart Staff 1
reactor power. Prior to the power escalation, the TMI-1 Restart Staff 4
i
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completed'its review of the licensee's safety evaluation for raising the                                         [
completed'its review of the licensee's safety evaluation for raising the
i                                         steam generator high level limit to 92%. The licensee's evaluation considered the effect of increased water inventory in the steam generator i                                         with respect to a main steam line rupture design basis event. The
[
'                                          licensee also evaluated the inadvertent flooding of the downcomer l                                         aspirating ports and the increase in thermal stresses resulting from the 4                                          loss of additional feedwater heating at the feedwater nozzle. The licensee identified no unreviewed safety questions and the staff independently concurred with that determination.
i steam generator high level limit to 92%. The licensee's evaluation considered the effect of increased water inventory in the steam generator i
In the past, the staff has noticed a slight decrease in steam generator
with respect to a main steam line rupture design basis event. The licensee also evaluated the inadvertent flooding of the downcomer l
-l water level with time during steady-state conditions. This apparently is
aspirating ports and the increase in thermal stresses resulting from the loss of additional feedwater heating at the feedwater nozzle. The 4
;                                          due to release of some of the crud deposits at the tube-to-tube support l
licensee identified no unreviewed safety questions and the staff independently concurred with that determination.
plate junctions. It is possible that prior to the turbine trip on January 2, 1986, this could result in a small power increase. The staff
In the past, the staff has noticed a slight decrease in steam generator water level with time during steady-state conditions. This apparently is
.                                          will continue to monitor this condition.
-l due to release of some of the crud deposits at the tube-to-tube support l
: 5.       TMI-1 Restart Staff Status During the Period The TMI-1 Restart Staff continued 12-hour shift coverage except on J                                          Christmas Day when random inspections (4 hours) were made during resident inspector holiday coverage. At 3:00 a.m. on December 27, 1985, continu-                                         !
plate junctions. It is possible that prior to the turbine trip on January 2, 1986, this could result in a small power increase. The staff will continue to monitor this condition.
ous coverage was initiated for the escalation to maximum achievable                                             '
5.
i                                          power.      When the plant is operating at steady-state conditions, the staff will resume coverage of twelve hours a day. The shifts were manned by NRC personnel from Regions I and II. A Region I project engineer, a l
TMI-1 Restart Staff Status During the Period The TMI-1 Restart Staff continued 12-hour shift coverage except on Christmas Day when random inspections (4 hours) were made during resident J
l reactor' engineer, a startup inspector, and two personnel training
inspector holiday coverage. At 3:00 a.m. on December 27, 1985, continu-ous coverage was initiated for the escalation to maximum achievable When the plant is operating at steady-state conditions, the staff i
!                                          specialists were on site during portions of the period to augment the j                                           resident inspection staff.
power.
The staff's inspection plan for this period covered the primary function-l                                           al areas of operations, maintenance, surveillance, personnel training, and restart testing with the division of responsibility as noted in previous status reports. The staff continued to evaluate the performance of licensee personnel and the plant to determine whether the licensee                                           i' i                                          should be permitted to proceed beyond the next hold point at 75% power.
will resume coverage of twelve hours a day. The shifts were manned by l
i                                           At 4:20 a.m. on December 27, 1985, the licensee was released from that hold point. The decision was based in part on a recommendation from the                                         ;
NRC personnel from Regions I and II.
TMI-1 Restart Staff as documented in a memorandum, dated December 27, 1985,- f rom W. F. Kane to T. E. Murley.                                                                       p t
A Region I project engineer, a l
Contact from the press arid public was minimal throughout the period. We                                       ,
reactor' engineer, a startup inspector, and two personnel training specialists were on site during portions of the period to augment the j
resident inspection staff.
The staff's inspection plan for this period covered the primary function-l al areas of operations, maintenance, surveillance, personnel training, and restart testing with the division of responsibility as noted in previous status reports. The staff continued to evaluate the performance of licensee personnel and the plant to determine whether the licensee i
should be permitted to proceed beyond the next hold point at 75% power.
i i
At 4:20 a.m. on December 27, 1985, the licensee was released from that hold point. The decision was based in part on a recommendation from the TMI-1 Restart Staff as documented in a memorandum, dated December 27, 1985,- f rom W. F. Kane to T. E. Murley.
p t
Contact from the press arid public was minimal throughout the period. We
}
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continued to maintain c6ntact with representatives of the Commonwealth of                                       :
continued to maintain c6ntact with representatives of the Commonwealth of l
Pennsylvania during this period.                                                                               l The TMI-1 Restart Staff issued one daily highlight report for the Execu-tive Director for Operations on December 27, 1985, regarding the escala-j                                           tion to maximum achievable power. The eleventh weekly status report for i
Pennsylvania during this period.
The TMI-1 Restart Staff issued one daily highlight report for the Execu-tive Director for Operations on December 27, 1985, regarding the escala-j tion to maximum achievable power. The eleventh weekly status report for i
the period December 13-20, 1985, was issued on December 20, 1985.
the period December 13-20, 1985, was issued on December 20, 1985.
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3 Enclosurn 6.
3                       Enclosurn
THI-1 Restart Staff Csuposition During Period The.TMI-l Restart Staff was comprised of the following personnel during the period:
: 6.         THI-1 Restart Staff Csuposition During Period The.TMI-l Restart Staff was comprised of the following personnel during the period:
W.[.,Kane,TMI-1RestartDirector 7
W.[.,Kane,TMI-1RestartDirector           7 R.:J. Conte, TMI-1 Restart Manager e D.,.R. Haverkamp, Technical Assistant / Shift Inspector F.I I. Young, Resident Inspector, TMI-l W. H. Baunack, Project Engineer / Shift Inspector R. J. Urban, Reactor Engineer / Shift Inspector
R.:J. Conte, TMI-1 Restart Manager e D.,.R. Haverkamp, Technical Assistant / Shift Inspector F.I I. Young, Resident Inspector, TMI-l W. H. Baunack, Project Engineer / Shift Inspector R. J. Urban, Reactor Engineer / Shift Inspector N. J. Blumberg, Startup Inspector
                                ,                N. J. Blumberg, Startup Inspector 4                          . g' } ,           *P. K. Eapen, Chief, Quality Assurance Section
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                                              ' *W. Oliveira, Reactor Engineer J. C. Bryant, Shift Inspector, Region II C. P. Hix, Sec,retary               '
' *W. Oliveira, Reactor Engineer
L. M. Prough, Secretary
*P.
K. Eapen, Chief, Quality Assurance Section 4
J. C. Bryant, Shift Inspector, Region II C. P. Hix, Sec,retary L. M. Prough, Secretary
* Personnel Training Specialist s
* Personnel Training Specialist s
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Latest revision as of 05:41, 11 December 2024

Forwards TMI Status Rept for Wk of 851220-27.Overview of Chronological Status of Restart Effort Also Encl
ML20151N968
Person / Time
Site: Crane Constellation icon.png
Issue date: 12/27/1985
From: Kane W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8601030253
Download: ML20151N968 (6)


Text

,

A DEC 2 71995 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 DECEMBER 20-27, 1985 The enclosure is the twelfth of a series of weekly status reports of the TMI-1 Restart Staff. These reports are intended to provide NRC management and the public with highlights from an NRC regulatory perspective of the TMI-1 restart activities for the previous week. Subsequent inspection reports will address most of these topics in more detail.

The enclosed report covers the period from 8:00 a.m., December 20 to 8:00 a.m., December 27, 1985. We will continue to issue weekly status reports for the duration of TMI-1 Restart Staff activities. An overview of the chronolog-ical status of the restart effort is shown on the figure which is attached to this report.

W William F. Kane, Director TMI-1 Restart Staff

Enclosure:

As stated y n85!P45 yg 3r i

i

T. Murley.

2 DEC 2 71985 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 F. Miraglia, NRR W. Travers, NRR J. Thoma, NRR J. Partlow, IE F. Combs, CA R. Walker, Region II E. Johnson, Region IV C. Smyth, GPU Nuclear 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 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 A. Blough, RI R. Conte, RI (20 cys)

F. Young, RI D. Haverkamp, RI Region I Docket Room (w/ concurrences)

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4 ENCLOSURE TMI-1 STATUS REPORT FOR THE PERIOD DECEMBER 20-27, 1985 1.

Plant Status As of 8:00 a.m. on December 27, 1985, TMI-1 was at 85.7% of rated power.

2.

Test Program Status The licensee's planned test program and current status for restart of THI-l are shown on the attached Figure 1.

On December 24, 1985, the licensee completed the required 30 days of operation at the 75% power testing plateau. However, the licensee deferred power escalation until after Christmas. After release from the 75% hold point was granted by the Region I Administrator, at 4:20 a.m. on December 27, 1985, the licensee slowly increased power until reaching 85.7% of rated power at 8:00 a.m.

Shortly after 8:00 a.m.,

the licensee reached the high steam i

generator limit (92%) and reactor power was limited to approximately 88%.

No operational problems occurred during the power escalation.

I Initial testing at the maximum achievable power level will include l

routine steady-state tests (facility performance data review, heat j

balance calculation, and integrated control system tuning) and an 1

automatic power reduction (runback) test to 68% of rated power on December 27, 1985.

Following that test, the plant will be returned to the maximum achievable power level. The licensee plans to maintain the plant at the maximum achievable power level until noon on January 2, 1986, when a planned reactor trip test will be conducted.

3.

Facility Operations Summary Steady-state operation at 75% power continued until the power escalation on December 27, 1985.

4.

Items of Special Interest i

NRC Notifications There were no events during the period that required notification of NRC pursuant to 10 CFR 50.72.

Steam Generator Level Limit A.4 described in previous reports, the limiting parameter for escalation to full power was steam generator level due to fouling of steam generator tubes on the secondary side. As of about 9:00 a.m. on December 27, 1985, the licensee reached the 92% level limit which corresponded to 88%

reactor power. Prior to the power escalation, the TMI-1 Restart Staff 4

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completed'its review of the licensee's safety evaluation for raising the

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i steam generator high level limit to 92%. The licensee's evaluation considered the effect of increased water inventory in the steam generator i

with respect to a main steam line rupture design basis event. The licensee also evaluated the inadvertent flooding of the downcomer l

aspirating ports and the increase in thermal stresses resulting from the loss of additional feedwater heating at the feedwater nozzle. The 4

licensee identified no unreviewed safety questions and the staff independently concurred with that determination.

In the past, the staff has noticed a slight decrease in steam generator water level with time during steady-state conditions. This apparently is

-l due to release of some of the crud deposits at the tube-to-tube support l

plate junctions. It is possible that prior to the turbine trip on January 2, 1986, this could result in a small power increase. The staff will continue to monitor this condition.

5.

TMI-1 Restart Staff Status During the Period The TMI-1 Restart Staff continued 12-hour shift coverage except on Christmas Day when random inspections (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) were made during resident J

inspector holiday coverage. At 3:00 a.m. on December 27, 1985, continu-ous coverage was initiated for the escalation to maximum achievable When the plant is operating at steady-state conditions, the staff i

power.

will resume coverage of twelve hours a day. The shifts were manned by l

NRC personnel from Regions I and II.

A Region I project engineer, a l

reactor' engineer, a startup inspector, and two personnel training specialists were on site during portions of the period to augment the j

resident inspection staff.

The staff's inspection plan for this period covered the primary function-l al areas of operations, maintenance, surveillance, personnel training, and restart testing with the division of responsibility as noted in previous status reports. The staff continued to evaluate the performance of licensee personnel and the plant to determine whether the licensee i

should be permitted to proceed beyond the next hold point at 75% power.

i i

At 4:20 a.m. on December 27, 1985, the licensee was released from that hold point. The decision was based in part on a recommendation from the TMI-1 Restart Staff as documented in a memorandum, dated December 27, 1985,- f rom W. F. Kane to T. E. Murley.

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Contact from the press arid public was minimal throughout the period. We

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continued to maintain c6ntact with representatives of the Commonwealth of l

Pennsylvania during this period.

The TMI-1 Restart Staff issued one daily highlight report for the Execu-tive Director for Operations on December 27, 1985, regarding the escala-j tion to maximum achievable power. The eleventh weekly status report for i

the period December 13-20, 1985, was issued on December 20, 1985.

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3 Enclosurn 6.

THI-1 Restart Staff Csuposition During Period The.TMI-l Restart Staff was comprised of the following personnel during the period:

W.[.,Kane,TMI-1RestartDirector 7

R.:J. Conte, TMI-1 Restart Manager e D.,.R. Haverkamp, Technical Assistant / Shift Inspector F.I I. Young, Resident Inspector, TMI-l W. H. Baunack, Project Engineer / Shift Inspector R. J. Urban, Reactor Engineer / Shift Inspector N. J. Blumberg, Startup Inspector

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K. Eapen, Chief, Quality Assurance Section 4

J. C. Bryant, Shift Inspector, Region II C. P. Hix, Sec,retary L. M. Prough, Secretary

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