ML20205F589

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Amends 102 & 92 to Licenses DPR-39 & DPR-48,respectively, Revising Tech Specs to Allow Disabling of Rod Control Sys During Periods That Reactor in Mode 3 W/Less than Four Reactor Coolant Pumps Operating
ML20205F589
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 03/19/1987
From: Varga S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20205F536 List:
References
NUDOCS 8703310208
Download: ML20205F589 (11)
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Text

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,h. kg UNITED STATES NUCLEAR REGULATORY COMMISSION

$ WASHINGTON. D. C. 20555

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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. OPR-39

1. The Nuclear Pegulatory Comission (the Comission) has found that:

A. The application for amendment hy Commonwealth Edison Company (thelicensee)datedOctober 16, 1986, 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 CFP Chapter I; B. 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 (1) 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 Comission's regulations; D. The issuance of this amendment will 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

$1 of the Comission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license j

amendment, and paragraph 2.C.(2) of Facility Operating License No. DPP-39 is hereby amended to read as follows:

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,- (2) Technical Specifications l The Technical Specifications contained in Appendices A and B, as revised through Amendment No.102 , are hereby incorporated in the license. The licensee 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 NU EAR REGULATORY COMMISSION fi

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a'rh,D ctor PWR Project Direct r e #3 Division of PWR Lic ing-A, NRR

Attachment:

Chances to the Technical Specifications Date of Issuance: March 19, 1987

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COWONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 92 License No. DPR-48

1. The Nuclear Regulatory Comission (the Comissioni has found that:

A. The application for amendment by Comonwealth Edison Company (the licensee) dated October 16, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 regulations of the Comission; C. There is reasonable assurance (1) 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 Comission's regulations; D. The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

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 No. DPR-48 is hereby amended to read as follows:

-2 (2) Technical Specifications g The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 92 , are hereby incorporated in the license. The licensee 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 Ni

)h . a, re or PWR Pro,iect Direct ate #3 Division of PWR L nsing-A, NRR

Attachment:

Changes to the Technical Specifications Date of Issuance: March 19, 1987 i

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' ' WASHINGTON,0. C. 20555 3 ,I A,.....j ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 102 FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO. 92 FACILITY OPERATING LICENSE NO. DPR-48 DOCKET N05. 50-295 AND 50-304 Revise Appendix A as follows:

Remove Pages Insert Pages

  1. 73 73 73a 73a 73b 73b 73c 77b 77b 77c i

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i LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT l 3.3 REACTOR COOLANT SYSTEM (per unit) 4.3 REACTOR COOLANT SYSTEM (per unit) i

1. Operational Components 1. Operational Components l

A. 7eactor Coolant Loops and Coolant A. Reactor Coolant Loops and Coolant

circulation Circulation

! 1. a. All Reactor Coolant Loops shs11 1. The reactor coolant loops shall be be OPERATING. verified to be OPERATING and

b. Startup of one inactive circulating reactor coolant at

! unisolated loop will not be least once per shif t.

! performed at levels greater than j l 25%.*

l APPLICABILITY: Modes 1 and 2**

1 ACTION: With less than the above required reactor coolant loops OPERATING, be in at least j HOT SHUT 00WN within one hour.

2. All Reactor Coolant Loops shall be 2. The reactor coolant loops shall be j OPERATING. verified to be OPERATING and j

circulating reactor coolant at least APPLICABILITY: Mode 3*** once per shif t.

j ACTION: With less than the above required reactor i coolant loops OPERATING, immediately open i the reactor trip breakers or de-energize both rod drive M.G. sets. '

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  • This power level is contingent upon the results of inactive loop startup tests performed under carefully

, controlled conditions. If the results of these tests indicate that startup can only be safely performed from a lower power level, the value of 25% will be replaced with this new power level. Startup of an inactive j loop will not be performed on a robtine basis until the controlled startup tests are evaluated.

    • See Special Test Exception 3.23.1

]

      • With 1) reactor trip breakers closed, and 2) a rod drive M.G. set energized.

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. 861016 Amendment Nos. 102, 92 0824t/0874t ADOCK 0500 5 73 TSC 84-10

) hDR

l SURVEILLANCE REQUIREMENT

' LIMITING CON 0lilDN FOR OPERATIDN i

4.3.1.A. 3. a. The required reactor coolant pumps, if 3.3.1. A. 3. At least two of the Reactor Coolant Loops not in operation, shall be determined l OPERABLE once per week by verifying shall be OPERA 8LE with at least one of the OPERABLE loops OPERATING.# correct breaker alignments and l -- indicated power availability.

l APPLICA8ILITY: Mode 3* At least one cooling loop shall be b.

ACTION: verified to be OPERATING and j a. With less than the above circulating reactor coolant at least l

required reactor coolant loops once per shif t'.

)

OPERABLE, restore the required J loops to OPERATING status within c. Verify at least once per shif t that 1) i 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or be in NOT SHUTDOWN the reactor trip breakers are open, or with Tavg < 350*F, within the 2) both rod drive M.G. sets are next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. de-energized. s

b. With no reactor coolant loop in l operation suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to i

return the required coolant loop to operation.

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  • With 1) Reactor trip breakers open, or 2) both rod drive M.G. sets de-energized.1) no operations are permitted

! # All reactor coolant pumps may be de-energized for up to one hour provided:that woul

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i is maintained at least 10*F below saturation temperature.

i Amendment Nos. 102, 92 TSC B4-10 73a l 0824t/0874t i

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LINITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT I

At least two of the six heat removal loops 4.3.1.A. 4. a. The required reactor coolant pump (s), l l 3.3.1. A. 4. if not OPERATING, shall be determined

(four reactor coolant loops

and indicated power availability.

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b. The required steam generator (s) shall
APPLICA8ILITY
Mode 4 be determined OPERABLE by verifying i

secondary side wide range water level ACTION: to be greater than or equal to 17% at

a. With less than the above required loops OPERABLE, least once per shift.

immediately initiate corrective action to return two loops to c. At least one heat removal loop shall be verified to be in operation and OPERABLE status as soon as possible; be in COLD SHUTDOWN circulating reactor coolant at least within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. once per shift.

I With no heat removal loop in d. With no heat removal loop in operation l i

b. the core exit temperature shall be

- operation: monitored utilizing data from 2 or more

1) Suspend all operations involving a reduction in core exit thermocouples. The frequency boron concentration of the of temperature readings shall be i

Reactor Coolant System and; adequate to insure that the temperature will not increase above the 10*F Immediately initiate subcooling limit between temperature

2) readings.
! corrective action to return

! the required heat removal ,

loop to operation.

)

  • See section 3.3.2.G for low temperature overpressure protection considerations before starting a reactor

! coolant pump.

l # All reactor coolant pumps and residual heat removal loops may be de-energized for up to one hour provided:

1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and 2) core outlet temperature is maintained at least 10*F below saturation temperature.

73b Amendment Nos. 102, 92 TSC 84-10 1 0824t/0874t i

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 1

Two residual heat removal (RHR) loops 4.3.1.A. 5. a. The residual heat removal loop l

l 3.3.1. A. 5. shall be determined to be in j shall be OPERA 8LE.* At least one of these ' operation and circulatln'g' reactor i loops shall be OPERATING. However, the coolant at least once per shif t.  ;

rettuirement for an OPERATING RHR loop may be deleted provided a) no evolutions that With no RHR loop'in opdrition the would cause a reduction of the reactor b.

coolant system boron concentration are in core exit temperature shall be  !

monitored utilizing data from 2 or progress or initiated, and b) the core more core exit thermocouples. The ,

i outlet temperature as measured by the core exit thermocouples is kept at least 10*F frequency of temperature readings  ;

}

below saturation temperature.

shall be adequate to insure that j the temperature will not increase above the 10*F subcooling limit j APPLICABILITY: Mode 5 between temperature readings.

ACTION:

j a. With only one of the above J

required loops OPERA 8tE, 1mmediately initiate corrective 1

action to return the inoperable

! loop to OPERABLE status as soon as possible.

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b. With no RHR loop OPERABLE:
1) suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and; .
2) immediately initiate 3

corrective action to return both RHR loops to OPERABLE. status, or l

l operation if necessary, in order 1 to maintain core outlet temperature at least 10*F below saturation temperature.

l c. The provisions of Specification 3.0.3 are not applicable.

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  • One RC loop capable of natural circulation may be substituted for one OPERA 8LE RHR loop. A RHR loop may still be considered OPERABLE with only one of either the normal or emergency power sources OPERABLE.

l 73c Amendment Nos. 102, 92TSC 84-10 0924t/0874t l l . - - - . _ - _ _ _ _ . _ - -

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3.3.1 and 4.3.1

! Bases:

Doerationa1 Components t

Th2 plant is designed to operate with all reactor coolant loops in operation and maintain DNBR equal to or greater than the l

applicable design limit DNBR (1) during all normal operations and anticipated transients, in MODES I and 2 with one reactor coolant loop not in operation this specification requires that the plant be in at least HOT SHUTOOWN within I hour.

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Th2 maximum 25% power level stated for startup of an inactive reactor coolant loop is contingent upon the results of inactive loop startup tests perfora,ed under carefully controlled conditions. If the results of these tests indicate that '

startup can only be safely performed from a lower power level, the value of 25% will be replaced with this new power laval. Startup of an inactive loop will not be performed on a routine basis untti the controlled startup ' rts.are evaluated.

In MODE 3, a single reactor coolant loop provides sufficient heat removal capability to remove decay heat fru the recctor. However, for Hot Zero Power (NZP) conditions operation is bounded by the following three accidents: 1) steamline break 2) rod ejection, and 3) bank withdrawal from subcritical. These accidents all assume four reactor coolant pumps in operation. For the steamline break and the rod ejection accidents, the operation of only a single reactor coolant pump i

will not impact the conclusions presented in the FSAR. But with less than four reactor coolant pumps in operation, the i j margin of safety may be reduced during a bank withdrawal accident. (

Reference:

Westinghouse letter, W. J. Johnson to J. 5.

Ab21, dated June 6, 1984 (CWE-84-579)). To ensure that the plant is maintained in an analyzed condition it is necessary to eith2r maintain all four reactor coolant loops in operation, or prevent the bank withdrawal accident from occurring by ensuring the reactor trip breakers are open or the rod drive motor generator (M.G.) sets are de-energized. Single failure considerations require two reactor coolant loops OPERA 8LE for the purpose of decay heat removal.

In M00ES 4 and 5, a single reactor coolant loop or RHR loop provides sufficient heat removal capability for removing decay ,

hest; but single failure considerations require that at least two loops be OPERA 8LE. Thus, if the reactor coolant loops are not OPERA 8tE, this specification requires two RHR loops to be OPERABLE.

Th2 operation of one Reactor Coolant Pump or one RNR pump provides adequate flow to ensure mixing, preventThe stratification reactivity and produce gradual reactivity changes during boron concentration reduction in the Reactor Coolant System.

charge rate associated with boron reduction will, therefore, be within the ' capability of operator recognition and control.

l During MODE 5, one reactor coolant loop capable of providing natural circulation may also be substituted for an OPERA 8LE RHR loop. At least one RHR loop must be OPERABLE at all times.

Wh:n the Unit has been in MODE 5 for an extended period of time, decay heat addition to the reactor coolant is very slow.

) During these periods, the requirement for an operating RHR pump may be relaxed to require two RHR pumps to be OPERABLE.

j If it 1

Op2 ration with no forced coolant flow is considered to be an unusual and undesirable mode of plant operation.

5 becomes necessary to interrupt forced coolant flow for testing, maintenance, or any other reason, the Technical Amendment Nos. 102, 92 11b TSC 84-10 OA24t/0874t l ,

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l Specification will assure that the onset of potential bolling can This i occurs.

be detected and core cooling estimate is based on no natural i d y. 5*F per minute af ter 4 days, and 3*F per minute af ter 1 month of plant shutdown.

I circulation flow through the coolant loops and reactor vessel water level at the centerline of the nozzles.

l The r: actor vessel head vent system is provided to exhaust noncondensible gases from the reactor ves

+ nattral circulation core cooling.

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I Amendment Nos. 102, 92 l

IIC TSC 84-10 1 0824t/0874t  !

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