ML20030A499
| ML20030A499 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 05/23/1967 |
| From: | Haueter R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| References | |
| NUDOCS 8101090773 | |
| Download: ML20030A499 (11) | |
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.lm Report of Operation of Big Rock Point Nuclear Plant License No. DPR-6 Nove=ber 1, 1966 Through April 30, 1967 This report, submitted in accordance with Paragraph 3.D.(3) of Operating License No. DPR-6 (effective May 1, 196L), covers the sixth six-=cnth period of operation of the Big Rock Point Nuclear Plant (Plant) under this license.
I.
SUMMARY
OF OPERATIONS A.
Power Operation The reactor was shut down at the beginning of the period while completin6 the bolt replacement operation on the grid bar bea:
clamp asse=bly of the top guide (this subject is discussed in the fifth semiannual report of operations).
The Plant was returned to the line on Nove=ber 9; however, difficulty was experienced in atte=pting to adjust the seal pressures on the =echanical seals of the No. 2 reactor recirculating pu=p.
On November 10, the seals failed cc=pletely and the pu=p was isolated and plant load reduced to hD Mwe until the pu=p could be inspected on Nove=ter 12.
Ex-amination of the pu=p revealed extensive damage to the pu=p shaft frc=
the failed seal components. The pu=p was re=cved fro: the loep for re-pair, and operation resumed at approximately 50 Mwe on one loop.
Operation was continued on one loop while the pu=p was repaired and a three-day outage, beginning Dece=ber 15, was required for reinstr.11ation of the pu=p.
Power operation was resumed on December 19, and continued' until January 20, when the-reactor scra==ed from a pressure transient due to erratic-operation of the' turbine admission valves. Reactor totart-up
.following the scram was delayed when Control Rod Drive E-b could not be
[
vithdrawn during prestart-up checks. Subsequent re= oval of the vessel h
..r
2
- l head revealed a 1/2" hex head nut lodged between the drive index tube notch and the drive thimble. This nut was identified as a missing iten from the beam clamp bolt replacement progra= in October 1966.
The Plant was returned to the line for a short period on January 26, but continued erratic operation of the turbine admission valves forced another shutdown.
Investigation of this problem showed the turbine shaft-driven oil pump had failed. This failure was due to a defective static grounding syste= on the turbine shaft which had caused electrolytic deterioration of the oil pump bearing surfaces with sub-sequent failure of the pump. The pu=p was rebuilt and the turbine oil system thoroughly cleaned to remove foreign pr.rticles from the failed bearing. Some minor indications of these foreign particles reaching the main. turbine bearings were found, but no repairs were required.
The Plant was returned to service on February 9 follow-ing~the oil pu=p repair and shutdown the following day due to a leaking 0-ring on the D-1 control rod drive thimble flange. This was the first problem experienced with the drive flanges. The Plant was returned to the line.on February 11 and the turbine generator was separated from the Company system'for a few hours on February 12, 13, 14, 16 and 17 to make final adjustments to the turbine initial pressure reguletor controls.
Full power was again achieved on February 17 l
The~ Plant was removed from service on March 10 for ap--
proximat'ely 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />'to inspect the main generator exciter. An accu =u-lation;of_ copper and. arbon particles on the commutator brushes was investigated and no abnormalities found. The commutator was cleaned and the-unit returned to~ service.
On-March 27, a 13-hour shutdown vas required to replace a: blown packing on the butterfly valve'in the No. 2 reactor _ recirculating
.- loop..
A blevn valve packing:en1the' vater column for the drum level sensors forced a shutdown on April 14.. The Plant returned to service
~
the following day.
The Plant continued operation _at'rull power at the f
~end of,the repert period. 'A refueling outage is scheduled for approxi-mately.May 22.
E
3
- I B.
Statistics The reactor was brought critical 11 times and was critical for 3557 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> during this reporting period. Total heat produced by the reactor was 741,869 Mvh(t). The turbine generator was on the line for 3447.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with a gross electrical generation of 228,989 Mvh. Net plant electrical generation for this period was 216,26h Mvh.
C.
R&D Program No special R&D Program tests were performed during this reporting period.
There are 13 developmental bundles (2 Phase I, 11 Phase II) in the present core. Three of the Phase II bundles have an accumulated exposure in excess of 10,000 Mwd /T at the end of the reporting period.
These have pellet fuel in 30 mil Zircaloy-2 cladding.
Se_ cted rods from three of the de"elop= ental bundles were shipped to the'Vallecitos Nuclear Center for complete examination. A sum-mary of the rods shipped is shown below:
Fuel Nu=ber of 2
Cladding Statusf Assembly Rods Tyre Material of Assembly D-2 k
Pellet 30 mil Zircalcy-2 In-Core D-2 g
(Gadolinium Poison Rods)
D-12 2
Powder' 11 mil Incoloy-800 Failed D-12 2 Partial
- Rods Powder 11 mil Incoloy-800 Failed D-19 h
Powder 30 mil Zirealoy-2 Leaker-II.
ROUTINE RELEASES, DISCHARGES AND SHIPMENTS OF RADI0 ACTIVE MATERIALS-A.
The gaseous radioactivity released from the stack during power operation averaged approximately 10,000 pc/see of activation'and fission' gases. Based upon 3091 offective full power hours of operation during this reporting period, this results in a total release of approximately 5
1.11 x'10 curies of activation and-fission gases to the environs. Gas-eous release during periods of shutdown was negligible.
-The orf-gas activity has decrecsed from an average of approxi-mately 12,000 pe/sec in November and December to approximately 8,000
(
pc/sec-in April. This reflects the gradual cleaning of previous fuel failure tramp uranium from the primary system. The activity during the i
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k i
past six months indicates that all failed fuel was removed during the last outage and also that no new fsilures have been encountered during this period. The absence of further failures is attributed to the placement of the stainless steel clad fuel in the low power peripheral zone of the core.
B.
During this reporting period, the liquid radioactivity releases to Lake Michigan, by way of the circulating water discharge canal, num-
-bered 63 batches, with a total activity of 5 06 curies. Twelve of the batches were released on a partially. identified basis; wherein, at least 90 percent of all the activity was deter =ined to be a combination of Co, Zn 5, Zr95, Ba and La All other batches were released under unidentified limits.
C.
There were 18 off-site shipments of radioactive material during this. reporting period:
Ship-ment Transfer Transfer.
Type of No.
Date From To Radioactive Materia) 1
'11/ 1/66 DPR-6 GE-Val One Lead Case Containing a 3-1/k" x 0017-60 1/2" Bolt (0.h5 Curies)
(Calif)
-2 11/ 3/66 DPR-6 GE-Val One Wooden Box Containing 6 Lengths 0017-60 of HPH Tubing and Bag of Contami-(Calif) nated Scale (0.15 me).
3 11/16/66 DPR-6 GE-Val One Lead / Steel Cask Containing Crud nd Scale Samples From Fuel (85 me) 0017-60 a
k' 11/1h/66 DPR-6 Dresden One Electric Hoist Asse=bly in a No. :
55-Gallon Drum (0.25 me)
DNPS-I 12-5650-1 5
12/~5/66
.DPR-6 GE-Val One.5-Gallon Drum Containing 6
~
~
0017 60; Hook Tools and 1 Underwater Light (Calif)
(0.12 me) 6.
12/ 6/66 DPR-6 GE-Val
.One Lead / Steel' Cask Containing a 0017 -Grid Bar Locking Bolt and Assorted l
(Calif)
Failed Bolts and Nuts (0.1 Curie) l T.
12/19/66 DPR-6 GE-Val Three Bottles (1 Liter Each) of De-l 0017-60 mineralizer Resin From Graver Unit (Calif)
(117 me).
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1 L:
5 Ship-cent Transfer Transfer Type of No.
Date Frc=
To Radioactive Material 8
1/11/67 DPR-6 GE-Val Thrce Bcttles (1 Liter Each) of De-0017-60 mineralizer Resin From Graver Unit (Calif)
(Total Est 25 cc) 9 1/21/67 DPR-6 GE-Val Steel Centainer Containing Profil-0017-60 oneter Equipment and X-Y Plotter (Calif)
- ATCOR, One HPH Tube Bundle 23' Long x 2' Inc.
Dia=.
One HPH Tube Sheet 6' Long x 12L8-1kT1 3' Dia= (Total Est 150 cc)
(N. Y.)
'11 2/15/67 ~ DPR-6 PG&E One Graver Testing Unit Asse=bly Hu= bolt (0.33 cc)
Bay Ok67-12 3
12 1/13/67 DPR-6
- ATCOR, Approximately 58 Ft High Level Inc.
Solid Radvaste (Est 2,900 Curies)
AEC Lie
- 31-11640-2 13 2/ 7/67 DPR-6 ATCOR,-
Approximately kS.3 Ft High and Inc.
Low Level Solid Radvaste (Est 50 12k8-1471 Curies)
AEC Lic
- Puncture Fixture,' Shearing Fixture (Calif)-
and Gas From the Fuel Rods (31 me) 15
'2/16/67' -DPR GE-Val
'Two Bottles (1 Liter Each); One With C017-60 Powdex Resins, the Other With H O (Calif)
From the Radvaste System (0.6 =2) c 16 2/17/67-DPR-6
- Isotopes, Two Bottles; One_Containing Reactor Inc..
H 0, One Condensate H O (0 33 cc) 2 2
29-55-6 17 3/ 7/67L DPR GE-Val Outer Shell of TV Camera (3 me) 0017-60 (Calif)~
J18.
-Lead / Steel Cask Containing Spent 0017-60
. Fuel Rods, Three Strings-of In-(Calif)
Cores, Etc (2,100 Curies)'
- (
6 III. RADIOACTIVITY LEVELS IN PRINCIPAL FLUID SYSTEFS (FOR SIX MONTHS)
A.
Primary Coolant Minimum Average Maximum Reactor Water Filtrate (a)
~h pc/cc 7 3 x 10 1.2 10.0
- Reactor Water Crud
_g
_y pc/ce/ Turbidity k.9 x 10 h.5 x 10 h.9 Iodine Activity (b)
+
-6 pc/cc 3 0 x 10 0.20 1.6 B.
Reactor Cooling Water System Beactor Cooling Water (a.)
-3
-2
-2 pc/cc 2.3 x 10 2 3 x 10 5 1 x 10 e
The principal radionuclides in the reactor cooling water system were K and Cr'..These resulted from the activation of the po-
'tassium-chromate inhibitor.
C.
Spent Fuel Pool Radioactivity in the spent fuel pool is principally activated corrosion products going to solution from fuel core components. During
- the last six months, some contribution was made from failed fuel bundles
-being stored.in the pool.
Minimum Average Maximum
? Spent Fuel: Pool (a)
-3:
-2
-2 pc/cc h.h x 10 1 5 x 10 8.7 x 10
_ Iodine Activity (b)
~g
~5
-5
.pe/cc
- 1 5 x 10 1.0 x 10 9.0 x 10
- Based on APHA turbidity units and 500 ml of filtered samples.
(a)A counter efficiency based on a gamma energy of 0.662 Mev and one gamma photon per disintegration decay scheme is assumed to. convert c.ount rate to microcuries. All count rates were taken at two hours after sampling.
(b) Based on efficiency of Iodine-131, two hours after sampling.
4'
I 4
t IV.
PRINCIPAL MAINTENANCE PERFORED Some of the primary maintenance ite=s perforced during the period are listed below:
A.
The No. 2 reactor recirculating pu=p was removed and repaired following the seal failure. Major rework was required due to the galling of the pump shaft and seal asse=bly from the failed seal ec=ponents. In addition, considerable time has been spent in modifying the spare pu=p shaft to acco==odate a new design cartridge seal which will be installed in the No. 1 recirculating pump during the next outage.
B.
The reactor clean-up pu=p and motor were replaced due to failure of the thrust bearing which allowed the impeller to interfere with the pump casing.
C.
The drive gears on the circulating water inlet traveling screens were replaced following their failure due to blockage by ice which had entered the screens. The gears were equipped with shear pins, but these vere improperly sized which allowed da= age to the geers.
D.
The turbine main oil pu=p was rebuilt following the failure of the thrust bearing. This failure allowed babbitt, steel and bronze par-ticles to circulate through the lube oil systes. The pu=p was repaired and the oil system thoroughly filtered to remove the foreign particles.
Additional grounding brushes were installed on the turbine shaft to pre-vent further electrolytic action on the bearing surfaces.
E.
Concrete block shielding was placed around the spent fuel pool filter to lover radiation levels in the surroundings and also to lessen personnel exposures while changing the filter socks.
F.
New bearings were installed in the Plant exhaust fans. This was acco=plished while the Plant was on the line by placing temporary lead shielding over the off-gas line.
V.
CHANGES. TESTS AND EXPERIMENTS PERFORKED PURSUANT TO 10 CFR 50.59(a)
This section describes the changes made to the facility within the six-month period without prior Commission approval pursuant to Section 50 59(a) of Title 10, Code of Federal Regulations, to the
. extent that such changes constitute changes in the facility as described
(
in the' Final Hazards Summary Report (FHSR). It also includes tests and L
8 f-experiments carried out at the Plant without prior Co= mission approval pursuant to Section 50.59(a).
Each change, test or experiment described was authorized only after a finding by Consumers Power Company that it did not involve a change in the Technical Specifications incorporated in Operating License DFB-6 (effective May 1, 1964) or an unreviewed safety question.
A.
Facility Changes 1.
Valve position lights (open or closed) vere installed in the control roo= for Valves NC-lh and NC-15 which are associated with the pressure equalizing line on the seras du=p tank.
2.
The valve located in the lower steam leak off drain
-line for the main turbine stop valve was removed and replaced with a blank spool. This was an unnecessary valve in regard to Plant operation and removal eliminazed any possibility of the drain line being closed.
3.
A turbine trip circuit was installed to automatically close the turbine stop valve on the occurrence of a reactor scram. The relays to the sphere ventilation valves were used to provide the trip rignal.
h.
The scintillation type detectors used for off-gas monitoring were replaced with ion-chamber detectors (this change was authorized by Change No.11 to the Technical Specifications).
.B.
Tests and/or Experiments 1.
Load Rejection Test -
A load rejection test at approximately 10 Mwe was cen-ducted to gather data on the response and operation of the turbine bypass valve control system. The test was successful'vith the bypass valve func-tioning to dump steam to the condenser. EPuture tests are planned at pro-gessively higher power levels to detencine the parametecs and proper settings for the bypass valve control system.
VI.
PERIODIC TESTING PERFORMED A3 REQUIRED BY THE TECHNICAL SPECIFICATIONS The following tabulation shows the required frequency of-testing,- plus the testing dates of the systems or functions which must be
~
_ periodically tested ~as required by the Technical Specifications:
e r
9 f
System or Function Frequency of Dates Undergoing Test Routine Tests Tested Control Rod Drives Continuous withdrawal and insertion Each major refueling and 11/ 5/66 of each drive over its stroke with at least once every six normal hydraulic system pressure.
months during periods of Minimum withdrawal time shall be 23 power operation, seconds.
Withdrawal of each drive, stopping Each major refueling and 11/ 5/66 at each locking position to check at least once every six latching and unlatching operations months during periods of and the functioning of the position power operation.
indication system.
Scram of each drive: from the fully Each major refueling and 11/ 5/66 withdrawn position. Maximum scram at least once every six time from system trip to 90 percent months during periods of of insertion shall'not exceed 2 5 power operation.
' seconds.
Insertion of each drive over its Each major refueling but 10/ 8/66
. entire stroke with reduced hydraulic not less frequently than
- system pressure to determine-that once a year.
drive friction is normal.
Control Rod Interlocks Rod withdrawal blocked when any two Each major refueling but 10/.4/66 accumulators are at a pressure be-
'not less frequently than lov 700 psig.
once every 12 months.
Rod withdrawal blocked when two of-Each major refueling but 10/ 8/66 three power. range channels read be-not less frequently +har
- low 5 percent.on-0 percent - 125 once every 12 montha.
percent.seales-(or below 2 percent on their 0 percent - k0 percent scales) when reactor power is above
. the minimum' operating range of these channels.
Rod. withdrawal blocked when scram Each major refueling but 10/ 8/66 du=p tank is bypassed.
not less frequently 1than once every 12 months.
Rod. withdrawal blocked when mode-Each major refueling but
- 10/ 7/66 selector switch is in shutdown not_less frequently than
(
- position, once every 12 months.
e 4
+
10 f
Syste= or Function Frequency of Dates Undergoing Test Routine Tests Tested Other Liquid poison system component Two months or less.
10/ 8/66 check.
2/15/66 h/18/66 Post-incident spray system automatic At each major refueling 10/ 8/66 control operation.
shutdown but not less frequently than once a year.
Core spray system trip circuit.
Not less frequently than 10/ 5/66 once every 12 months.
Emergency condenser trip circuits.
Not less frequently than 10/ 8/66 cnce every 12 months.
Containment Containment sphere access air locks Once every six months or 2/ 5/67 and vent valves, leakage rate.
less.
Isolation valve operability _and At_least once every 12 10/11/66 leak tests.
months.
Isolation valve controls and in -
Approximately quarterly.
2/ 7/67 strumentation tests.
-Penetration inspection.
At least once every 12 10/12/66 months.
l Integrated leak test'.
Once every two years.
h/30/66 i
The following instrument checks and calibrations were l-performed at least once a month: Reactor safety.systen checks on cir-I
.cuits not' requiring plant shutdown to check; air ejector off-gas monitor I
calibration;_ stack-gas monitor-calibration; emergency. condenser _ vent mon-itor calibration; process monitor calibration; and the area monitoring I
system calibration.
'VII.. PERSONNEL TRAINING Three additional engineersLhave been added io the Plant Technical Staff in recent months;to acquire nuclear trainin6 This is I
part of a program.to broaden our Company depth in nuclear-trained per-i sonnel'in preparation for the. staffing of our Palisades Plant. It is 6
L
11 anticipated that additional personnel vill receive training at the Plant over the next two years for this purpose.
By Robert L. Haueter (Signed)
Robert L. Haueter Assistant Electric Production Superintendent - Nuclear Consumers Power Company Jackson, Michigan Date:
May 23, 1967 Sworn and suberibed to before me this 23rd day of May 1967 (SEAL)
Grace Warner (Signed)
Notary Public, Jackson County, Michigan My commission expires February 16, 1968 4
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