ML19350C124
| ML19350C124 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/18/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19350C125 | List: |
| References | |
| NUDOCS 8103300554 | |
| Download: ML19350C124 (14) | |
Text
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paarcq UNITED STATES j',j NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 8
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VIRGINIA ELECTRIC AMD POWER COMPANY DDCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 24 License No. HPF-4 The Nuclear Regulatory Commission (the Commission) has found that:
1.
The application for amendment by Virginia Electric and Power A.
Company (the licensee) dated February 9,1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the appl cation, B.
the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the. activities authorized C.
by this amendment can be conducted without endangering the health and :afety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not.be inimical to the common D.
defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part E.
51 of the Commission's regulations and all applicable requirements have been satisfied.
810s3oo!gF];3g
2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating Lic*.nse No. NPF-4 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 24, are hereby incorporated in the license. The itcensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert A. Clark, Chief Operating Reactors Branch #3 M vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 18, 1981 O
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 24 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications i
with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain docume.nt completeness.
Pages t-3/4 1-11 B3/4 1-4 O
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REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 At least one charging pump in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE.
APPLICABILITY: MODES 5 and 6 ACTION:
a.
With no charging pump OPERABLE, suspend all opera tions involving CORE I
ALTERATIONS or positive reactivity changes until one charging pump is restored to OPERABLE status, b.
With no charging pump OPERABLE and the opposite unit in MODE 1, 2, 3 or 4, immediately initiate corrective action to restore at least one charging pump to OPERABLE status as soon as possible.
SURVEILLANCE REQUIREMENTS-i 4.1. 2. 3.1 At least-the above required charging pump shall be demonstrated OPERABLE by verifying that, on recirculation flow, the pump develops a discharge pressure of > 2410 psig when tested pursuant to Specification 4.0.5.
4.1.2.3.2 All charging pumps, except the above required OPERABLE pump, shall be demonstrated inoperable 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 the switches in the Control Room have been placed in the pull to l
lock position.
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NORTH ANNA -' UNIT 1 3/4 1-11 Amendment No. 16, 24
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REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITIGN FOR OPERATION 3.1.2.4 At least two charging pumps shall bc OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4*.
ACTION:
With only one charging pump OPERABLE, restore a second charging pump to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and bo' ated to a SHUTDOWN MARGIN equivalent to at least 1.77% ak/k at 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore a second charging pump to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. The pro-visions of Specification 3.0.4 are not applicable for one hour following heatup above 320*F or prior to.coldown below 320*F.
SURVEILLANCE REQUIREMENTS ~
1 4.1.2.4.1 The above required charging pumps shall be demonstrated OPERABLE by verifying, that on recirculation flow, each pump develops a discharge pressure of > 2410 psig when tested pursuant to Specification 4.0.5.
4.1.2.4.2 All charging pumps, except the above required OPERABLE pump, shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the tem?2rature of one or more of the RCS cold legs is less than or equal to 320*F by verifying that the switches in the Control Room have been placed in the pull to lock position.
A maximum of one centrifugal charging pump chall be OPERABLE whenever the temperature of-one or more of the RCS-cold legs is less _than er equal-to 320*F.
NORTH ANNA-UNIT 1 3/4 1-12 Amendment No. 3, 16 t
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6 REACTIVITY CONTROL SYSTEMS i
BASES i
3/4.1.2 B0 RATION SYSTEMS.(Continued)
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 undue risk to overall facility safety from injection system failures during the repair period.
The boration capability of either system is sufficient to provide a SHUTDOWN MARGIN from expected operating conditions of 1.77% ak/k after xenon decay and cooldown to 200 F.
This expected boration capability requirement occurs at E0L from full power equilibrium xenon conditions and requires 4450 gallons of 20,000 ppm borated water from the boric acid storage tanks or 70,000 gallons of 2000 ppm borated water from the refueling water storage tank.
The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable below 320 F provides assurance that a mass addition pressure transient can be relieved by the operat on of a single PORV.
With the RCS tenperature below 200 F, one injection system is acceptable without single failure consideration on the basis of the 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.
The boron capability required below 200 F is sufficient to provide a SHUTDOWN MARGIN of 1.77% ak/k after xenon decay and cooldown from 200*F to 140*F. This condition requires either 835 gallons of 20,000 ppm borated water from the boric acid storage tanks or 9690 gallons of 2000 ppm borated water from the refueling water storage tank.
The contaired water volume limits include allowance for water not available because of discharge line location and other physical character-istics.
The OPERABILITY of one boron injection system during REFUELING insures that this system is available for reactivity control while in MODE 6.
NORTH ANNA - UNIT 1 B 3/4 1-3 Amendment No. 5.16 e
REACTIVITY CONTROL SYSTEMS BASES 3/4.1.2 B0 RATION SYSTEMS (Continued)
The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within the containment after a LOCA.
This pH minimizes the evolution of iodine and minimizes the effect of chloride and caustic strass corrosion on mechanical systems and components.
At least one charging pump must remain operable at all times when the opposite unit is in MODE 1, 2, 3, or 4.
This is required to maintain the charging pump cross-connect system operational.
3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained. (2) the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effects of rod misalignment on associated accident analyses.
OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.
The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that'the original design criteria are met. Misalignment of a rod requires measurement cf peaking factors or a restriction in THERMAL POWER; either of these restrictions provides assurance of fuel rod integrity during continued operation.
In addition those accident analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.
Control rod positions and OPERABILITY of the rod position indicators are required t, be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable. These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.
The maximum rod drop time restriction'is consistant with the assumed rod dgop time used in the accident analyses. Measurement with T p_500 F and with all reactor coolant pumps operating ensures thafV9 the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.
NORTH ANNA UNIT 1 B 3/4 1-4 Amendment No. 75, 24
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o UNITED STATES s
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(3 NUCLEAR REGULATORY COMMISSION WASHING TON, D. C. 20555 g..v /y,/
VIRGINIA ELECTRIC AND POWER COMPANY
' DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 5 License No. NPF-7 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated February 9,1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulati.ons of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's ' regulations; D.
The issuaoce of this amendment wil' not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of-the Commission's regulatior.s and all applicable requirements have been satisfied.
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. 2.
Accordingly, the ifcense is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.0.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 5
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
The written procedures required by Technical Specification 6.8.1 for the Technical Specifications listed below shall be implemented within 30 days af ter the date of this license:
4.3.2.1.3 Items 10 and 11 of Table 3.3-5 4.3.3.6
- 4. 4. 3. 2.1 4.4.3.2.2 4.4.6.2.2 The required surveillance shall be completed before the end of the first surveillance interval.
3.
This license amendment is effective as of-the'date of its issuance.
FOR THE NUCLEAR REGULATORY C0HMISSION
~
o Robert A. Clark, Chief Operating Reactors Branch #3 Civision of Licensing
Attachment:
Changes to the Technical
-Specifications Date of Issuance:
March 18, 1981 J
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i 1
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 5 TO FACILITY OPERATING LICENSE NO. NPF.7
- DOCKET NO. 50-339 Replace.the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Pages t
3/4 1-11 B3/4 1-4 I
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REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN i
LIMITING CONDITION FOR OPERATION 1
3.1.2.3 One charging pump in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE.
j APPLICABILITY. MODES 5 and 6.
ACTION:
4 With no charging pump OPERABLE, suspend all operations involving CORE I
a.
ALTERATIONS or positive reactivity changes until one charging pump is restored to OPERABLE status, b.
With no charging pump OPERABLE and the opposite unit in MODE 1, 2, 3 or 4. immediately initiate corrective action to restore at least one charging pump to CPERABLE status as soon as possible.
SURVEILLANCE REQUIREMENTS 4.1. 2. 3.1 The above required charging pump shall be demonstrated OPERABLE by _ verifying that, on recirculation flow, the pump develops a discharge pressure of-preater than or equal to 2410 psig when tested pursuant to
. Specification 4.0.5.
. 4.1.2.3.2 All charging pumps, except the above required OPERABLE pump, shall be demonstrated inoperable at least once pe;' 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control switch is in the pull to lock position..
NORTH ANNA - UNIT 2
.3/4 1-11 Amendment No. 5
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REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two charging pumps shall be OPERABLE.
A>PLICABILITY;. MODES 1, 2, 3 and 4 ACTION:
With only one charging pump OPERABLE, restore a second charging pump to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and gorated to a SHUTOOWN MARGIN equivalent to at least 1.77% delta k/k at 200 F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore a second charging pump to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The provisions of Spgcification 3.0.4 are not applicagit for one hour following beatup above 340 F,or prior to cooldown below 340 F.
SURVEILLANCE REQUI'REMENTS 4.1.2.4.1 The above. required charging pumps shall be demonstrated OPERABLE by verifying that on recirculation flow each pump develops a discharge pressure of greater than or equal to 2410 psig when tested pursuant to Specification 4.0.5.
4.1.2.4.2 All charging pumps, except the above required OPERABLE pump, shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever tge temperature of one or more of the RCS cold legs is less than or equal to 340 F by verify-ing that the control switch is in the pull to lock position.
- A maximum of one centrifugal charging pump shall be OPERABLE whenever the temperatgre of one or more of the RCS cold legs is less than or equal to 340 F.
NORTH ANNA - UNIT.2 3/4 1-12
REACTIVITY CONTROL SYSTEMS BASES 3/4.1.2 80 RATION SYSTEMS The boron injection system ensures that negative reactivity control:is available during each mode of facility operation.
The components required to perform this function include 1) borated water sources, 2) charging pumps,
- 3) separate flow paths, 4) boric acid transfer 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 boron injection flow paths are required to ensure single functional capability in the event-an assumed failure renders one of the flow paths inoperable.
The boration capability of either flow path is sufficient to provide a SHUTDOWN MARGIN from expecteg operating conditions of 1.6% delta k/k after xenon decay and cooldown to 200 F.
The maximum expected boration capability requirement occurs at E0L from full power equilibrium xenon conditions and requires 4450 gallons of 20,000 ppm borated water from the boric acid storage tanks or 70,000 gallons of 2000 ppm borated water from the refueling water storage tank.
With the RCS temperature below 200 F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.
The limitation.for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to v'erify afl charging pumps except the required OPERABLE pump to be inoperable below 340 F provides assurance that a mass additipn pres,sure transient can be relieved by the operation of a single PORV.
The boron capability.' required below 200 F is sufficient to provide a 7
SHUTD0gN MARGIN of 1.77 delta k/k after xenon decay and cooldown from 200 F to 140 F.
This condition requires either 835 gallons of 20,000 ppm borated water from the boric acid storage tanks or 9690 gallons of 2000 ppm borated water from the refueling water storage tank.
NORTH ANNA - UNIT.2 B 3/4 1-3 4
REACTIVITY CONTROL SYSTEMS BASES 3/4.1.2 B0 RATION SYSTEMS (Continued)
The contained water volume limits include allowance for water not avail-able because of discharge line location and other physical characteristics.
The OPERABILITY of one boron injection system during REFUELING insures that this system is available for reactivity control while in MODE 6.
The limits on contained wcter volume and boror concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution re-circulated within the containment after a LOCA.
This pH minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corresion on mechanical systems and components.
At least one charging pump must remain operable at all times when the opposite unit is in MODE 1, 2, 3 or 4.
This is required to maintain the charging pump cross-connect system operational.
3/4.1. 3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the min mum SHUTDOWN MARGIN is maintained, and (3) limit the potential-effects of rod misalignment on associated accident analyses.
OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and inse'rtion limits.
The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met. Misalignment of a rod requires measurement of peaking factors or a restriction in. THERMAL POWER; either of these restrictions provides assurance of fuel rod integrity during continued operation.
In addition those accident analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.
(
Control rod I,ositions and OPERABILITY of the rod position indicators
.are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperabl e.
These verification frequencies are adequate for assuring that the applicable LC0's are satisfied.
The maximum rod drop time restriction is consistent with the assumed Measurement with T rod drop time used-ig the accident analyses.than or equal to 500 F and wit ensures that the measured drop times'will be representative of insertion times experienced during' a reactor trip at operating conditions.
NORTH ANNA - UNIT 2 B '3/4 l'-4 Amendment No. 5