ML20002C952
| ML20002C952 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 11/13/1964 |
| From: | Haueter R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Doan R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8101150326 | |
| Download: ML20002C952 (5) | |
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C O N S U M '4 R S POWER C.O M P A N Dd hD
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AU W BIG ROCK POINT NUCLEAR PLANT
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Dr. R. L. Doan, Director
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Division of Reactor Licensing
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Dear Dr. Doan:
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Enclosed are one signed and 20 conformed copies of Consumers Power Company's second Report of Changes, Tests or Experi-ments at the Big Rock Point Nuclear Plant.
In accordance with the provisions of Section 50 59 of 10 CFB, Part 50, the Report, which covers the period from August 31, 1963 through August 30,196, contains brief descriptions of (1) changes made in the facility without prior Commission approval, to the extent that such changes constitute changes in the facility as described in the Final Hazards Su= mary Report, and (2) tests or experiments carried out at the Plant without prior Commission ap-proval. There have been no changes in procedures required to be reported to or approved by the Commission under Section 50 59 Each change, test or experiment described in the Report was authorized only after a finding by Consumers Power Company that it did not involve a change in the Techr.ical Specifications in-corporated in License No. DPR-6, or an unreviewed safety question.
Succeeding Reports of Changes, Tests or Experiments v111 appear in the periodic reports required under Paragraph 3.D.(3)d.
of License No. DPR-6.
Yours very truly, R. L. Haueter (Signed)
RLH/vf/vl R. L. Haueter-Enc Assistant Electric Production Superintendent - Nuclear f#//D3M sac
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CONSUMERS. POWER COMPANY-
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This report is submitted in accordance with the requirements of Section 50 59(b) of 10 CFR, Part 50, and Paragraph 3.D.(3)d. of Operating License No. DPR-6, issued to Consumers Power Company on May 1, 1964, and covers the-period from August 31, 1963 through August 30, 1964. Part A briefly describes the changes made in the Big Rock Point Nuclear Plant facility during that period without prior Commission approval pursuant to 10 CFR, Section 50 59, to the extent that such changes constitut char.ges in the facility as described in the Final Hazards Summary Report (dated November 14, 1961, submitted as part of Amendment No. 3, dated December 1, 1961, as amended, to Consumers' Application for Reactor Con-struction Permit and Operating License). Part B briefly describes the tests or experiments carried out at the Plant during that period without prior Commission approval pursuant to Section 50 59 There have been no changes in procedures required to be reported to or approved by the Commission under Section 50 59 A.
Facility Changes 1.
During' December 1963, the. steam drum level sensors (RE 06 A and B, and RE 20 A and B) and the steam drum pressure sensors (RE 07 A, B, C and D), all as shown on Drawing No. M-121, Final Hazards Summary Report, Volume II, Tab D, were removed from the C-30 instrument panel and mounted on the concrete steam drum enclosure vall. This' change was made ta reduce
2 the possib'ility cf spurious contact operation from vibration or bumping of the panel. For_ background and further detail, see Special-Report No. 6, submitted December 20, 1963 2.
The main steam bypass valve ecntrol system v s modified in April 1964 by the addition of a second servo amplifier and servo pilot valve, proviaing two independent control paths. In addition, the hydraulic system was modified to provide a means of ranote manual closure of the bypass valve. This manual system bypasses both the automatic control and the servo pilot valve.
3 A further modification to the seal system of the reactor recirculating pumps was made in April 1964 by removing the solenoid-operated valve at the outletofthe3/h-inchheatexchanger. The motor-cperated valve, installed upstream of the heat exchanger, (see first annual Report of Changes, Tests or Experiments, dated October 9,1963, Item A.T. ) provides the necessary j
remote isolation in the event of heat exchanger failure.
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The high-pressure nitrogen system for the liquid poison system was modified ia September 1963 by the addition of a 6000 psig nitrogen bottle, a 6000 psig regulator and relief valve. This bottle can be used, if necessary, to top off the nominal 2000 psig bank of nitrogen bottles to maintain the desired pressure.
5 The annunciation for safety system operations has been modified.
'The vent valve and back-up scram valve bus relay conisets, previously con-nected into Channel No. 1 and Channel No. 2 scram annunciators, have been reconnected so that Channel No. 1 scram annunciation vill occur only if both scram valve solenoid buses on Channel-No. 1 have been de-energized.
Similarly, Channel No. 2 scram annunciation will occur only if both
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c solenoid buses on Channel No. 2:have isen de-energized. The loss of power to Channel No. 1 and' Channel No. 2 " vent valve and back-up scram valve" buses-will now actuate a separate alarm. For background and further detail, see Special Report No. 6, submitted December 20, 1963
'6. ' A new off-gas monitoring system was installed in June 1964 and is 4
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- operating.in parallel with the original aff-gas monitoring system for pur-poses.of evaluating performance. The new system consists of an ion chamber strapped to a vertical section of off-gas sample line and connected to a l
1 six-decade log ar.plifier, with appropriate readout in the control room.
.7 In April 1964 the top fission chamber on one of_the standard in-core assemblies was replaced with a'high-sensitivity fission chamber capable of use.with a high-gain amplifier and counting squipment. This special chamber
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I-was installed to evaluate performance of miniature in-core counting equip-ment in monitoring the start-up and low power operation of the reactor.
8.- Protective relaying was installed in April 1964 to protect against overvoltage and undervoltage in the output of the reactor protection M-G sets; I
- With an increase in generator output voltage to 140 5 volts on
~either reactor protection M-G set, indicative of failure of the voltage regulator, the generator voltage vill drop to zero and the reactor pro-
.tective channel connected to that M-G set will trip. The electronic components supplied from the defective M-G set are thus protected.
A loss of 480-volt power to the motor of eithcr reactor protection t
M-G set -initiates an alarm in the control room and, after a ten-second delay,-the-generator voltage drops to zero and the reactor protective
. channel-connected to that M-G set will trip. This relaying action, upon loss of motor power, provides for a more positive and faster actuation of the undervoltage scram breaker.
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- 9.. In June 1964 the area monitor in the radwaste. area was moved about.
five feet to afford better measurement of the general radiation field in the operating gallery and to simplify calibration procedures. The monitor was moved from Room 7 to Room 1 of the radvaste area (see Drawing No. A-52, Final Hazards Summary Report, Volume.II, Tab A).
B. ' Tests or Experiments 1.
Nonpe*1fication tests were performed on the primary system and feed-
~ water system on :mveral occasions by bypassing either the condensate I.
demineralizer, reactor clean-up demineralizer, or both. These tests,
'together with detailed feed-vater chemical analyses, have shown that the corrosion products being fed into the reactor come predominantly from the feed-wate'r system. The feed-water heater tubes are the principal contribu-tors. The condensate demineralizer appears to have very little influence on the absolute amounts of corrosion products entering the primary system from the feed-weier system.
By R. L. Haueter (Signed)
Assistant Electric Production Superintendent - Nuclear Consumers Power Company Jackson, Michigan Date: November 13, 196h Sworn and subscribed to before me this 13th day of November 1964.
(SEAL)
Grace Warner (Signed)
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Notary Public, Jackson County, Michigan My commission expires February 16, 1968 1
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