ML20030A497
| ML20030A497 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 12/13/1967 |
| From: | Haueter R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| References | |
| NUDOCS 8101090769 | |
| Download: ML20030A497 (10) | |
Text
_
CONSUMERS POWER COMPANY Docket No. 50-155 Report of Operation of Big Rock Point Nuclear Plant License No. DPR-6 May 1, 1967 Through October 31, 1967 This report, submitted in accordance with Paragraph 3.D.(3) of Operating License No. DPR-6 (effective May 1, 196h), covers the seventh six-month operating period for the Big Rock Point Nuclear Plant (Plant).
I.
_SJMMARY OF OPERATIONS A.
Power Operation The Plant was on the line at the beginning of the period (May 1) but was shut down on May.19 for the third refueling outage.
The Plant was returned to J.c line-on June lh' following this refueling outage and operated continuously until September 7 It was removed from service for one day to allow operator training cn crit-
'ical approaches. The Plant was then returned to service and operated until-September 27, when it was'again shut down for approximately one day to conduct AEC operator license examinations.
Another shutdown was required for-one day (October 26)'
to repair a steam leak in the bonnet of the high-pressure bleeder trip.
..-valve.
The Plant was on line at the end.of the report period.
B.
Refueling Outage.
Prior to.the. refueling. shutdown, the off-gas activity had been steady at approximately 8,000 pc/sec which indicated no gross fuel failures in the. core. After shutdown, all standard and develop-mental bundles scheduled for the new core loading were examined by. the
' dry-sipping technique. One developmental bundle (D-4) gave a definite leaker signal. This bundle was visually examined with the periscope, but no evidence of the failure could be seen. This was a 19 mil, Incoloy-800 clad, pellet bundle with 9,911 Mvd/T exposure.
30fi5
2 A total of 13 fuel bundles was removed from the core as depleted fuel. These were replaced with 12 Zr-2 powder reload ("C")
bundles and one Zr-2 pellet reload ("B") bundle. This "B" bundle con-tained some experimental Zircaloy-chro=e alloy roda (see Technical Speci-fication Change No. 5).
The progra= for replacing the bolts in the upper grid strue-ture of.the reactor vessel was completed during this scheduled outage. The 50 bolts which had not been changed previously were replaced. None of
- these 50 bolts was found defective. The replaceme.it bolts hsve a known composition and heat-treatment history.
The ether' maintenance work perfor=ed during this outage is itemized in Section IV of this report.
C.
Statistics The reactor was brought critical 33 times and was critical for 3,772.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> during this. reporting period. Total heat produced by the reactor was 867,939 Mvht. The turbine generator was on the line for 3,720'.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> with a gross electrical generation of 267,311 Mvh.
Net plant electrical generation for this period was 25h,h68 Mvh.
[
D.
R&D Program-During the May and June 1967 refueling shutdown, several developmental assemblies were visually inspected and dimensional profiles taken on selected rods. All developmental assemblies were tested for clad l
integrity, via1the. dry-cipping method, with one asse=bly (D h) giving a
~
positive signal. The bundle was, therefore, eliminated fror the subse-7 quent core loading.
Eleven developmental assemblies were included in the core l
loading during this period. At the.end of this period, exposure ranged from 6,3T3 Mvd/T (PO h) to lk,33h Mvd/T (D-3).
Seven of the 11 assemblies have-exposures in ercess of 11,000 Mvd/T.
E.
Reactor Vessel Coupon Irradiation Program A second' set of Charpy, V-notch specimens, irradiated 'for a total of 3,407,655 Mvht at an accelerated. position on the inside of the thermal shield, were recently evaluated by the Naval Research Laboratory.
4
. The results are'of"censiderable interest, since the measured fluence of
'W
=
3
+
+e y-
.k
+
,t-.y.?
e wf-M M
a-
- -*N??-
W9*
3 these specimens was 1.33 x 10 n/c=2 >l Mev. This is well in excess of 20 the projected kO-year lifetime exposure of the vessel vall.
The base metal specimens showed an increase in nil duc-
.tility transition te=perature (NDT) of approximately 150 F.
The heat affected zone (HAZ) specimens showed an :'.ncrease of approximately 160 F.
Thus, the NRL'results to date indicate that the increase in transition temperature of the Big Rock Point reactor vessel should not be of concern for future operations.
II.
ROUTINE RELEASES, DISCHARGES AND SHIPME'iTS OF RADIOACTIVE MATERIALS 5
A.
A total of approximately 1.43 x 10 curies of activation and fission gases vas released to the environs via the stack. This is based on 3,616 EFFH of operation at an average release rate of 1.1 x 10 pc/sec.
B.
The total activ3',y et the liquid radioactive vaste released to Lake Michigan (93 batches' by way of the circulating water discharge canal) was 2.0 curies.
Twenty-nine of these batches were released on a partially identi-fled -basis; whereas at least 90% of the activity was deter =ined to be l
l1 65, l03, c,58, Zr95 + Nb95, Ce
, Ce and 2n
, g,lko, Ru l39, Bal0
.Ba C.
The-following is a tabulation of shipments of radioactive materials:
i Ship-Type of.
ment
~ Transfer-Transfer No.,
Date ~
Frc=
To' Radioactive Material
~
1 6/ 9/67 DPR-6 GE-Val Steel Drum Containing Celco Air Drill
'0017-60 (8 me)
(Calif)
-2 6/16/67 DPR-6
'GE-Val' Zn'5, Ru ', Zr95 - Nb95, Ce Con-0017-60 tained in 1 Liter Bottle of. Liquid
-= (Calif)
Radvaste and.1_Can Containing Six Petri Dishes.and 32 Plastic Packets
.(201 me) t 3
6/21/67' DPR-6
'US Naval-Reactor Vessel Surveillance Speci-Lab men #12k (20-Curies)'
8-1393-2 *
(A-66)
'k' 6/22/67.. DPR-6 GE-Val Containment Profilometer Handling
~0017-60
-Equipment'and Cables (1.0 me) q
-(Calif)
V
=
m
+-
m
/
.e
.g e
.,.,,,g
k Ship-ment Transfer Transfer Type of No.
.Date From To Radioactive Material 5
7/28/67 DPR-6 Isotopes, Two Plastic Bottles Containing Ap-Inc.
proxi=ately h00 ml Each of Radio-29-55-6 active Liquid. One Being Reactor Water; One Being Condensate Water (0.8 cc)-
6' 8/29/67 DPR-6 US-Nu--
Anticonta=ination Clothing With clear Fixed Fission and Activation Product Corp.
Contamination in Plastic Eag. Two h-52hl Fair Shoe Covers and Two Fair Over-alls (0.25 me) 0 7
9/22/67 DPR-6 Neutron Forty Rods of Co With Approximately Products, 7,500 Curies / Rod (300,000 Curies)
Inc.
8-12332-1 8
9/22/67 DPR-6 Westing-HandlingTools,.LeadggandOther
' house Tools for Handling Co in Cask Electric Corp.
SNM-770 9
11/ 3/67 DPR-6 GE-Val Box Containing Seven CIC Cha=bers 0017-60 (0.10 cc)
(Calif)
.III.
RADIOACTIVITY LEVELS IN PRINCIPAL FLUID SYSTEG (FOR SIX MONTHS)
'A.
. Primary Coolant Mini =um Average Maxi =u.
Reactor Wate'-Filtrate " '
r pc/cc 2.91x.lb-3 h.36 x 10 3.6h
-1 Reactor Water. Crud "
-3
-1
.pc/ce/ Turbidity 2.0h x 10 2.91 x 10 1.h5 Iodine Activity
~5 pc/cc, k x 10 0.30 15
.(a)A c'ounter efficiency based -on-a gamma energy of 0.662 Mev and one ga==a photon per disintegration' decay scheme is assumed to convert count rate-
- of microcuries. All count rates were taken at two hours after sa=pling.
(b) Based on efficiency of I-131',.tvo hours after sampling,
~
i
5 B.
Reactor Cooling Vater System The principal radionuclides in the reactor cooling water system were K h2 and Cr-51, which resulted from the activation of potassium-chromate inhibitor.
Minimum Average Maximum Reactor Cooling Water (b) 2.91 x 10 1,38 x 10
-2
-1 uc/cc 8.0 x 10
?'
C.
Spent Fuel Fool Radioactivity in the spent fuel pool is principally activated corrosion products going into solution from fuel core components.
Minimum Average Maximun Fuel Storage Pool (a)
-3
-2
-1 pc/cc 5.8 x 10 5.8 x 10 1.h x 10 Fuel Pool Iodine (b)
-6 h
-2 pc/cc 1.5 x 10 1 x 10 2.5 x 10 i
lV.
PRINCIPAL MAINTENANCE PERFORMED
. Some of the primary maintenance items perfor=ed during
~
the period are:
i A. -The No. 1 reactor recirculating pump was re=oved fro = its case during the ' refueling outage and modified for installation of a new car-tridge type shaft seal. This modification required extensive machining
- of the pump shaft and a major rework of the seal and cooling water piping systems. A special shield tank was fabricated and detailed procedures developed Cor_this work in order to minimize radiation exposures to per-sonnel.~ A total of 700 man-hours (over 17.vorkdays) was required for.the job.' The.old seals which were removed were-found in excellent condition, after approximately 6,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />' service.
i B.
The high-pressure turbine casing was removed to check and repair leak' age at the horizontal joint. No major problems vere encountered.
The joint was stoned and reassembled. No further leakage has been noted.
- A counter efficiency based on a gamma energy of 0.662 Mev and one ga=ma photon per disintegration decay scheme is assumed to convert count rate of microcuries..All count rates were taken at two hours after sampling.
-i (b) Based on efficiency cf I-131, two hours after sampling.
6 i
C.
The inspection cover was removed from the emergency condenser and the tubes visually inspected. No abnormalities were noted.
D.
The No. 1 reactor feed pump was disassembled and the spare barrel installed. A continuing problem has developed from the depo-sition of crud on the pump internals with a corresponding loss in pu=p e fficiency. ' Studies are undervty to determine methods of reducing this crud buildup.
E.
The stack-gas filter and demister were replaced and the drain line inspected for proper operation.
F.
An altrasonic inspection of various components in the reactor and primary syster2 was conducted. The items inspected included thermal shield support bolts, reactor head studs, 3" valve and tee, reactor re-circulating pump flange bolts, and reactor recirculating system valve body bolts'.
No indications of defects were observed.
G.
Eight pressure switches and two transducers were relocated out of the recirculating pump room to reduce personnel radiation exposure during calibration and maintenance.
V.
CHANGES, TESTS AND EXPERIMENTS PERFORMED PURSUANT TO 10 CFR 50.59(a)
-A.
Facility Changes 1.
Installed check valves in turbine high-pressure drain to high-pressure heater and drains to intermediate-pressure heater. This will prevent possible water backup'into the turbine.
2.
Added a 3-inch check valve to eliminate backflow of control rod drive excess cooling water to the radvaste system.
3.
Installed new cartridge type seals in Nc.1 recircu-lating pump. Modified instrumentation and piping accordingly.
h.
Relocated eight pressure switches (RE15-IGlls) from the recirculating pump room to the C30 panel area:
(a) ' Switches removed and lines capped off.
(b) Switches _ mounted on the vall adjacent to the C30 panel an'd connected to drum pressure sensor lines.
-(c)l Pulled new viring in fran penetration to C30
_r:
panel and booked up same.
.+,-w
7 5
Eliminated the 1-1/2" supply valve to the steam seal regulator and CV-kol3 Installed 1-1/2" pipe as replacement. Installed 3/h" backseat valve ahead of the steam seal regulator.
6.
Installed a 2h" square register in the tral. cite con-tainment skirt between the pipe tunnel and air shed. This is to break the flow of air between the pipe tunnel and air shed.
7 Replaced 3" rupture diaphrag= in off-gas pipe with new type diaphragm.
8.
Added toggle switch to common line in fuel pool hoist control circuit for. protection against uncontrolled movement of hoist.
9 Modified liquid radvaste system so that filtration can be accomplished on both the dirty radvaste receiver tank and the chemical vaste receiver tank.
B.
Tests-1.
Fuel Sipping Test -
Several individual. fuel bundles were tested for clad material integrity utilizing the " dry-sipping" technique. The procedure was exactly as described in the fifth six-month period report submitted
-in December 1966.
2.
Temperature Coefficient Test -
A temperature coefficient test was conducted in June prior to power operation with the newly loaded core. Test data indicated
- that the coefficient turned negative at 'approximately 105 F after adding approximately 1.3 cents of reactivity.
3.
Feed Pump Tests -
Performance tests were conducted before and after re-building the No. 1 reactor feed pump. Head vs capacity and efficiency curves were compared to determine the benefit from the rebuilding effort.
VI.
PERIODIC TESTING PERFORMED AS REQUIRED BY THE TEC3NICAL SPECIFICATIONS The following tabulation shows the required frequency of testing, plus the testing ~ dates of the systems or functions which must be periodienlly tested as required by the Technical Specifications:
-i T
8 System or Function Frequency of Dates Undergoing Test Routine Tests Tested Control Rod Drives
. Continuous withdrawal and insertion Each major refueling and 6/ 7/67 of each drive over its stroke with at least one.e every six normal hydraulic system pressure, months during periods of Minimum withdrawal ti=e shall be 23 power operation.
seconds.
Withdrawal of each drive, stopping Each major refueling and 6/ 7/67 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 6/ 7/67 withdrawn position. Maximu= 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 6/ 7/67 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 6/ 7/67 accumulators are at a pressure be-not less frequently than low 700 psig.
once every 12 months.-
Rod withdrawal blocked when two of Each major refueling but-6/ 7/67
'three pcVer range channels read be-not less frequently than low 5 percent on.0 percent - 125-once every 12 months.
' percent = scales (or below'2 percent-on their 0 percent - h0. percent scales)-when' reactor power is above.
the mini =um operating range of these channels.
> Rod withdrawal. blocked when scram
- EachLmajor refueling but 6/-7/67
~
dump tank is ' bypassed.
.not'less frequently than once every'12 months.
Rod withdrawal ~ blocked when mode Each major. refueling but 6/ 7/67 selector switch isiin. shutdown:
not less frequently than l4, position.
once every 12 months.
j 9
4 i l Syste= or Function Frequency of I:ates Undergoing Test Routine Tests Tested Other t
Liquid poison syste= cc=ponent Two conths or less.
6/13/67 cheek.-
6/1k/67 l
10/31/67
)
-Post-incident spray system autocati:: At each tajor refueling 6/ 6/67 control operation.
shutdevn but not less 3
+
frequently than once a year.
Core spray systec trip circuit.
Not less frequently than 6/ S/67 once every-12 tenths.
J Frergency condenser trip aircuits.
Not less frequently than 6/12/67 cnce very 12 =cnths.
Containment Contain=ent sphere access air locks Once every.six =enths or 8/lk/67 and vent valves, leakage r' ate.
less.
Isolation valve operability and At.least once every 12 6/13/67 leak tests.-
=cnths.
i
' Isolation valve: controls.and in-Approxi=ately quarterly.
6/12/67 4
strumentation tests.
Penetration inspection.
.At least ence every 12 6/10/67 months.
i
' Integrated leak -test.
.Once every two years.
L/30/66
!~
The following instrument checks'and calibrations were l
performed at least once a month: Reactor safety' system checks en cir-l
- cuits not requiring' plant shutdown to check; air ejector off-gas =onitor l
i calibration; stack-gas monitor calibration; emergency condenser vent =cn-
~ itor calibration; process monitor calibration;.and the area monitoring l
system ealibration.
VII.. PERSONNEL TRAINING p
Five engineers received-an AEC Senior Operator License
[g during September.
In' addition, one-man received a Reactor _ Operator r.
I l
t.
i-L:
..t
~
..__,-s
10
(
License. This is a continuation of our efforts to provide additional depth in anticipation of staffing the Palisades Plant.
By Robert L. Haueter (Signed)
Robert L. Haueter Ascistant Electric Production Superintendent - Nuclear Consumers Power Company Jackson, Michigan Date: December 13, 1967 Sworn and subscribed to before ce this 13th day of December 19CT.
(SEAL)
Grace Warner (Signed)
Notary Public, Jackson County, Michigan My commission expires February 16, 1963 i
_.