ML20088A834
| ML20088A834 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/27/1984 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20088A835 | List: |
| References | |
| NUDOCS 8404130189 | |
| Download: ML20088A834 (9) | |
Text
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UNITED STATES y
NUCLEAR REGULATORY COMMISSION g
g WASWNG TON, D. C. 20555 e
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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No, b License No. DPR-69 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licerisee) dated December 22, 1983 as supplemented by two letters dated January 27, 1984, complies with the standards and requironents of the Atonic Enerov Act of 1954, as amended (the Act) and the Comnission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission:
C.
There is reasonable assurance (i) that the activities authorized by this anendnent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this anendment will not be ininical to the corvor defense and security or to the health and safety of the nieblic:
and E.
The issuance of this anendment is in accordance-with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
e404130189 840327 DR ADOCK 05000318 p
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License flo. OPR-69 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 72, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifica-tions.
3.
This license amendnent is effective as of the date of its issuance.
FOR THE NUCLEAR GULATORY C0f411SSION
, smk James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Chances to the Technical Specifications Date of Issuance:
March 27, 1984 l
g_.
f ATTACHMENT TO LICENSE AMENDMENT NO. 72 FACILTIY OPERATING LICENSE NO. DPR-69 DOCKET N0. 50-318 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.
Pages 3/4 1-1 3/4 1-5 B 3/4 1-1
3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL SHUTOOWN MARGIN - T,yg > 200 F LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be ; 4.3%* ak/k.
l APPLICABILITY: MODES 1, 2**, 3 and 4.
ACTION:
With the SHUTOOWN MARGIN < 4 3%* ak/k, immediately initiate and continue l
baration at > 40 gpm of 2300 ppm boric acid solution or equivalent until the required SHUTOOWN MARGIN is restored.
SUP,VEILLANCE REQ'U,IREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be 1 4.3%* ak/k:
l a.
Within one hour after detection of an inoperable CEA(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the CEA(s) is inoperable.
If the inoperable CEA is immovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable CEA(s).
b.
When in MODES 1 or 2, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that CEA group withdrawal is within the Transient Insertion Limits of Specification 3.1.3.6.
c.
When in MODE 2
, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criticality by verifying that the predicted critical CEA position is within the limits of Specification 3.1.3.6.
d.
Prior to initial operation above 57; RATED THERMAL POWER after each fuel loading, by consideration of the factors of e below, with the CEA groups at the Transient Insertion Limits of S ecification 3.1.3.6.
P AdherencetoTech$icalSpecification3.1.3.6asspecifiedinSurveillance Requirements 41.1.1.1 assures that there is suf ficient available shut-down margin to match the shutdown margin requirements of the safety analyses.
- See Special Test Exception 3.10.1.
- With K 1 1.0.
eff
- 8 With K
< l.0.
eff CALVERT CLIFFS - UNIT 2 3/4 1-1 Amendment No. P. JE, U.9/y, 72 c
REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.
When in MODES 3 or 4, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by con-sideration of the following factors:
1.
Reactor coolant system boron concentration, 2.
CEA position, 3.
Reactor coolant system average temperature, 4.
Fuel burnup based on gross thermal energy generation, 5.
Xenon concentration, and 6.
Samarium concentration.
4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values t'o demonstrate agreement within + 1.0% Ak/k at least once per 31 Effective Full Power Days (EFPD). This comparison shall consider at least those factors stated in Specification 4.1.1.1.1.e, above. The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 Effective Full Power Days after each fuel loading.
CALVERT CLIFFS-UNIT 2-3/4 1,
~
1 r
REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.4 The moderator temperature coefficient (MTC) shall be:
Less positive than 0.5 x 10-4 Ak/k/*F whenever THERMAL a.
POWER is 1 70% of RATED THERMAL POWER, b.
Less positive than 0.2 x 10~4 Ak/k/*F whenever THERMAL 5
POWER is > 70% of RATED THERMAL POWER, and Less negative than -2.5 x 10~4 Ak/k/*F at RATED THERMAL l
c.
POWER.
APPLICABILITY: MdDES-1 and 2*#
1 ACTION:
4 With the moderator temperature coefficient outside any one of the above limits, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.1.4.1.The MTC shall be determined to be within its limits by confirmatory measurements. MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the above limits.
4
- With Keff >fl.0.
- See Special Test Exception'3.10.2.
CALVERT CLIFFS '- UNIT 2
'3/4 1-5 Amendment No. 78, AI' 72
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REACTIVITY CONTROL' SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.1.1.4.2 The MTC shall be determined at the following frequencies and THERMAL POWER conditions during each fuel cycle:
a.
Prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.
b.
At any THERMAL POWER.above 90% of RATED THERMAL POWER, within 7 EFPD after initially reaching.an equilibrium condition at or above 90% of RATED THERMAL POWER after each fuel loading.
At any THERPML Power,'within 7, EFPD after reaching a RATED c.
THERMAL, POWER equilibrium boron concentration of 300 ppm.
s i
CALVERT CLIFFS-UNIT 2 3/4 1-6 Amendment No.8 1 m
I 3__
3/4.1i REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 B0 RATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subtritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration and RCS T The minimum available SHUTDOWN MARGIN for no load operating conditions $E9beginning of life is 4.3%
ak/k and at end of life is 4.3% ak/k.
The SHUTDOWN MARGIN is based on the safety analyses performed for a steam line rupture event initiated at no load conditions.
The most restrictive steam line rupture event occurs at E0C conditions.
For the steam line rupture event at beginning of cycle conditions, a minimum SHUTDOWN MARGIN of less than 4.3% Ak/k is required to control the reactivity transient, and end of cycle conditions require 4.3% Ak/k. Accordingly, theSHUTDOWNMARGINrequirementisbaseduponthislimitingconditfonandis consistent with FSAR safety analysis assumptions.
With T
< 200 F, the reactivity transients resulting from any postulated accid 8N are minimal and a 3% Ak/k shutdown margin provides adequate protection. With the pressurizer level less than 90 inches, the sources of non-borated water are restricted to increase the time to criticality during a boron dilution event.
3/4.1.1.3 BORON DILUTION A minimum flow rate of at least 3000 GPM provides adequate mixing, prevents stratification and ensures that reactivity changes will be gradual during boron concentration reductions in the Reactor Coolant System. A flow rate of at least 3000 GPM will circulate an equivalent Reactor Coolant System volume of 9,601 cubic feet in approximately 24 minutes. The reactivity change rate associated with boron concen-tration reductions will therefore be within the capability of operator recognition and control.
3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC) l r,
1,w l hitations en MTC are provided to ensure.tfiat the assumptions
'jc H '1 the accident and transient analyses remain valid through each ifuel :icle. The surveillance requirements for measurement of the MTC
=daring each fuel cycle are adequate to confi.w the MTC value since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup. The confirmation that the measured MTC value is within its limit provides assurances that the coefficient will be maintained within acceptable values throughout each fuel cycle.
CALVERT CLIFFS - UNIT 2 B 3/4 1-1 Amendment No. 18,31,84/,
2
REACTlVITYCONTROLSYSTEMS BASES I
3/4.1.1.5 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will' not be made i
crigicalwiththeReactorCoolantSystemaveragetemperaturelessthan 515 F.
This limitation is required to ensure 1) the moderator temperature coefficient is within its analyzed temperature range, 2) the protective instrumentation is within its normal operating range, 3) the pressurizer is j
capable of being in an OPERABLE status with a steam bubble, and 4) the reactor pressure vessel is above its minimum RT temperature.
-3/4.1.2 B0 RATION SYSTEMS The boron injection system ensures that negative reactivity contsol is available during each mode of facility operation. The components required to perform this function include 1) borated water sources, 2) 1 charging pumps, 3) separate flow paths, 4) boric acid pumps, 5) associated heat tracing systems and 6) an emergency power supply from OPERABLE diesel generators.
With the RCS average temperature above 200 F, a minimum of two separate and redundant boron injection systems are provided to ensure single functional capability in the event an assumed failure renders one of the systems inoperable. Allowable out-of-service periods ensure that minor component repair or corrective action may be completed without i
_ undue risk to overall facility safety from injection system failures during the repair period.
The boration capaLility_ of either system is sufficient-to provide a SHUTDOWN MARGIN from all gperating conditions of 3.0% ak/k after xenon decay and cooldown to 200 F.
The maximum boration capability requirement occurs at E0L from full power equilibrium xenon conditions and requires 6500 gallons of 7.25% boric acid solution from the boric acid tanks or 55,627 gallons of 2300 ppm borated water from the refueling water
. tank. However,_to be consistent with the ECCS requirements, the RWT is L
required to have a minimum contained volume of 400,000 gallons during l
MODES 1, 2, 3 and B.
The maximum boron concentration of the refueling water tank shall Le limited to 2700 ppm and the maximum boron concentra-tion of the boric acid storage tanks shall be limited to_8%-to preclude the possibility of boron precipitation in the core during long term ECCS cooling. '
~
p With the RCS temperature below 200 F, one injection system is acceptable without single failure consideration on the basis of the i
stable reactivity condition of the reactor and the additional restric-tions~ prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.
+
h CALVERT CLIFFS - UNIT 2 8 3/4 1-2 Amendment'No[31 L
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