ML20073F977
| ML20073F977 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/26/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073F970 | List: |
| References | |
| NUDOCS 9410030330 | |
| Download: ML20073F977 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20006-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.197 TO FACILITY OPERATING LICENSE NO. DPR-53 AND AMENDMENT NO. 174 TO FACILITY OPERATING LICENSE NO. DPR-69 BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUCLEAR POWER PLANT. UN~IT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318
1.0 INTRODUCTION
By letter dated June 8,1994, the Baltimore Gas and Electric Company (the licensee) submitted a request for changes to the Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2, Technical Specifications (TSs). The requested changes would revise Section 4.7.1.2.c to extend the Auxiliary Feedwater (AFW)
System surveillance frequency to accommodate the 24-month fuel cycles currently in use at Calvert Cliffs. As requested in Generic Letter (GL) 91-04, " Changes In Technical Specification Surveillance Intervals To Accommodate a 24-month Fuel Cycle," the licensee provided an evaluation in support of the change which concludes the effect on safety is small and does not invalidate any assumption in the plant licensing basis.
2.0 BACKGROUND
The AFW System is a safety-related system designed to provide an alternate supply of feedwater to the steam generators for the removal of decay heat and cooldown of the Reactor Coolant System if the Main Feedwater System, a nonsafety-related system, is unavailable. The AFW System can also be used for normal cooldown of the Reactor Coolant System and to fill the steam generators prior to normal operation.
The AFW System has two turbine-driven pumps and one motor-driven pump, drawing water from a condensate storage tank. The Auxiliary Feedwater Actuation Signal (AFAS) starts the motor-driven pump and opens the steam supply valves to the turbine-driven pumps when the level in either steam generator drops to a low level setpoint. Normal alignment of the turbine driven pumps has one pump start automatically and one remain in standby. Flow e.ontrol valves regulate flow to the steam generators for removing decay heat.
In the event of a high differential pressure between steam generators, such as a steam generator tube rupture or main steam line break, AFW flow to the affected steam generator is isolated when an AFAS block signal shuts the blocking valves in each AFW line to the affected steam generator.
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. The AFW surveillances with 18-month frequencies verify:
(1) cach automatic valve in the flowpath actuates to its correct position upon receipt of each AFAS test signal (4.7.1.2.c.1);
(2) each AFW pump automatically starts upon receipt of each AFAS test signal (4.7.1.2.c.1); and (3) the AFW System is capable of providing a minimum of 300 gallons per minute (gpm) nominal flow to each flow leg (4.7.1.2.c.2).
These surveillances ensure the AFW pumps, flow controi valves, blocking valves and the electrical signal paths function properly.
3.0 EVALUATION Subsequent to increasing the refueling interval from 18 months to 24 months, the licensee requested amendments to the TSs of both units which added the definition, " Refueling Interval - at least once per 24-months" to Table 1.2 of TS Definition 1.22, " Frequency Notation." The requested amendments adding the 24-month definition do not change the existing definition for, "R - at least once per 18-months." The 18-month frequency definition is necessary to assure the safety-related systems and components which have not yet been approved for 24-month surveillance intervals have their surveillances performed at the required 18-months intervals. This is accomplished during scheduled mid-cycle surveillance / maintenance outages until all the safety-related systems and components have been approved for the 24-month refueling interval. The Commission issued Amendment No. 133 to Facility Operating License No. DPR-53 and Amendment No. 114 to Facility Operating License No. DPR-69 for Unit Nos. I and 2, respectively, by letter dated December 21, 1988, which included the definition for a 24-month Refueling Interval.
The changes were consistent with the current guidance in GL 91-04 and, therefore, no other changes are necessary in relation to defining the existing surveillance intervals in the TSs to support the requested changes to the AFW system surveillance intervals.
GL 91-04 states that for cases where 18-month surveillances do not involve calibration of instruments that perform safety functions, licensees should evaluate the effect on safety of the change in surveillance intervals which supports a conclusion that the effect on safety is small.
Licensees should confirm that historical maintenance and surveillance data do not invalidate this conclusion.
The licensee's evaluation of monthly and 18-month AFW surveillances from January 1, 1989, to December 31, 1993, on the components effected by this change found no test failures during the performance of Surveillance 4.7.1.2.c.
Reliability data indicates that there has been only I turbine-driver AFW pump trip in over 70 starts during this period, 3 of which were demand starts. There have been no recorded failures of the motor-driven pump
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. to start during the period.
In addition, no instruments are calibrated by the 18-month surveillances. Monthly and 18-month surveillance test both verify proper operation of the valves and that the appropriate AFW pumps start. The 18-month surveillance differs from the monthly surveillance in that the 18-month surveillance is performed with the pump discharge valve open to allow AFW flow into the steam generator and verifies the minimum AFW flow rate of 300 gpm in each leg using AFW flow indicating controllers.
The NRC staff has determined that the increase in the surveillance interval from 18 months to 24 months for the AFW system surveillance as specified in TSs 4.7.1.2.c.1 and 4.7.1.2.c.2 is acceptable. This determination is based on the historical data which indicatas that extending the surveillt.nce interval will not adversely affect the ability to detect degradation in the AFW system and does not invalidate any assumption in the plant licensing basis.
4.0 ETATE CONSULTATION In accordance with the Comission's regulations, the Maryland State official was notified of the proposed issuance of the amendments.
The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public coment on such finding (59 FR 42334). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact staternent or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Comission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Comission's regulations, and (3) the issuance of the amt.ndments will not be inimical to the comon defense and security or to the health and safety of the public.
Principal Contributor:
Jefferey F. Harold Date:
september 26, 1994 l
4 September 26, 1994 y
Mr. Robert E. Denton Vice President - Nuclear Energy Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
ISSUANCE OF AMENDMENTS FOR CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 1 (TAC N0. M89921) AND UNIT NO. 2 (TAC N0. M89922)
Dear Mr. Denton:
The Commission has issued the enclosed Amendment No.197 to Facility Operating License No. DPR-53 and Amendment No.174 to Facility Operating License No.
DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2, respec-tively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated June 8, 1994.
j The amendments revise TS Section 4.7.1.2.c to extend the interval for three Auxiliary feedwater surveillance requirements from 18 to 24 months.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Reaister notice.
Sincerely, Original signed by:
Daniel G. Mcdonald, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-317
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and 50-318
Enclosures:
1.
Amendment No.197 to DPR-53 2.
Amendment No.174 to DPR-69 3.
Safety Evaluation cc w/encls:
See next page DOCUMENT NAME: G:\\CCl-2\\CC89921.AMD To recolve e copy of this document, Indicate in the box:
"C" = Copy without enclosures *E* = Copy with enclosures *N* = No copy 0FFICE LA:PDI-l lC PE:PDI-1 lE PM:PDI-l l
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8 DATE 08/S0/94 08/3D /94 08/W94 08/f,/94 r@# 08/ ' /94 OfflCIAL RECORD COPY tj yje
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