ML19346A108
| ML19346A108 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 05/14/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19346A102 | List: |
| References | |
| NUDOCS 8106050090 | |
| Download: ML19346A108 (3) | |
Text
-
O p* "%q,
UNITED STATES 8 ',..,, l' ' i NUCLEAR REGULATORY COMMISSION C
W ASHINuTON, D. C. 20555 r 'ii l
%...<..,f J '
CAFETV EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION.
SUPPORTING AMENDMENT NO. 43TO FACILITY OPERATING LICENSE NO. OPR-6 4
4 CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET NO. 50-155
1.0 INTRODUCTION
By letter dated Febraury 4,1981, Consumers Power Company (the licensee) requested an amendment to Facility Operating License No. DPR-6 for the i
Big Rock Point Plant. This amendment would provide corrections and
]
clarifications for the Emergency Power Sources and Reactor Depressurization System sections of the Technical Specifications. This change would accurately reflect the "as-built" condition of the plant, and is con-i sidered to be administrative in nature, providing only corrections and i
clarifications which do not involve a significant safety consideration.
By letter dated March 6,1981, the licensee also requested a change to tha Technical Specification to permit the use of Thermoluminescent Dosin.9ter (TLD) as an alternate to film for environmental monitoring purposes.
1 2.0 DISCUSSION AND EVALUATION Section 11.3.5.3 of the Oyster Creek Technical Specifications, now requires an errergency diesel generator fuel storage capacity sufficient for one day operation. The licensee has recently performed a plant modification which increases the fuel tank capacity to a three-day supply. Considering the nature of the modification we conclude that plant safety is not adversely impacted and find that the change is acceptable.
The licensee has referenced NUREG-0737, iten II.B.2 with regard to " Dose Rate Criteria". The staff is presently reviewing NUREG-0737 and will provide the evaluation of radiation criteria in that review.
The licensee has requested changes in Table 3.5.2.H (Reactor Depressurization System) involving -set point values.
Before initiating RDS, assurance must be made that the pumps in the core spray system are running. Pressure switches provide a permissive signal if the f're pump elischarge pressure indicates that at least cne of the pumps is operating, The set point of the pressure switches must be above the shutoff pressure ot the jockey pump and below the' discharge pressure of the pumps for the rated core spray flow. The jockey pump shuts 8106050090s
6.4. 3 f ( Cont' d)
(c) One of the emergency condenser vent mor.itors shall be in service at all times during power operation. The monitors shall be set to alarm at approximately 10 mr above the maximum expected background during operation of the emer-gency condenser. The calibration shall be checked at least monthly.
(d)
The process liquid monitors shall normally be in service.
Adequate spare parts shall be on hand to allow necessary repairs to be made promptly. Alarms shall be set as speci-fied in 6.4.1 (d). Calibration of the " Radioactive Waste System Effluent to Canal" monitor shall be checked at least once a month. Calibration of the remaining monitors shall be checked at least once every three months. Each day an analysis shall be made of the previous 24-hour callection of discharge canal water.
(e) The area monitoring system shall normally be in operation; however, individual monitors may be taken out of service for maintenance and repairs. Adequate spare parts shall be on hand to allow necessary repairs to be made promptly. During monitor outages in normally accessible areas, temporary moni-toring shall be provided if the remaining area monitors do not provide adequate coverage. Calibration of monitors shall be checked at least monthly. Alarm trip points shall be set at a radiation level approximately twice the normal maximun indicated radiation level, but normally not less than one decade above the lowest scale reading.
Two films or TLDs, each with a sensitivity of 10mR, shall be l
provided at each site environmental monitoring station.
During operation at stack release rates of 0.1 curie per second or less, at least five monitoring stations shall be provi ded. The films or TLDs at each station shall be replaced l
and analyzed at least monthly.
Operation at stack release rates above 0.1 curie per second shall not exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> without at least fifteen film or TLD monitoring l
stations in service. Two of these stations shall be on-site near the stack. The remaining additional stations shall complement the permanent stations but shall be located at greater distances from the stack. One film or TLD at each l
station shall be replaced and analyzed at least every two weeks.
The second film or TLD shall be replaced and analyzed monthly.
Under all stack release conditions, the film or TLD processor shall be instructed to report within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. on all films or TLDs that l
might indicate abnormal exposures.
( f) Gamma dose-rate measuring instruments and neutron dose-rate measuring instruments shall be provided for establishing per-missible working linits. These instruments shall be calibrated at least once every three months.
P 6-14 Change No. 7, Amendment No. 43
1
. off at less than or equal to 90 psig. Therefore.the lower set point of 100 psig provides an adequate 10 psig margin. The pump head curve shows that with the required 400 gpm supplied by the fire system, the discharge pressure is above 130 psig resulting in a margin.of 20 psig provided by the proposed 1
upper setpoint of 110 psig. After further discussion with the licensee, f
agreement was made to change the Technical Specification to read, "105 psig 5 psig." Based on our review, we find that this change is acceptable.
Also requested were corrections / clarifications in the Bases for Emergency Power Sources section. We have reviewed these changes and find them to be administrative in nature. As a result, we conclude that these changes are acceptable.
By letter dated March 6,1981 the licensee has proposed a change to the Technical Specification, sections 6.4.2 and 6.4.3.
The proposed changes allow the use of TLDs as an alternate to film for radiation monitoring.
Ws have reviewed the request and find that it is in keeping with existing nuclear power plant standards, and therefore find the proposed change acceptable.
I'
3.0 ENVIRONMENTAL CONSIDERATION
We have determined that the amendment docs not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmenta' impact. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and pursuant to 10 CFR 551.5(d)(4) that an environmental impact statement or negative declaration and environment l
impact appraisal need not be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
S We have concluded, based on the considerations discussed above, that: (1) because the amendment does not involve a significant increase in the pro-bability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered i
by operation in the proposed manner, and (3) such activities will be con-ducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date:
May 14, 1981 l
l
.