ML20042C173

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Tech Spec for Redundant Decay Heat Removal Capability, Calvert Cliffs Nuclear Power Plant,Units 1 & 2, Preliminary Technical Evaluation Rept for Feb 1982
ML20042C173
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 02/28/1982
From: Steverson J
EG&G, INC.
To: Donohew J
Office of Nuclear Reactor Regulation
References
CON-FIN-A-6429 EGG-EA-5763, NUDOCS 8203300311
Download: ML20042C173 (16)
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This is an informal report intended for use as a preliminary or working document Prepared for the U.S. Nuclear Regulatory Commission Under DOE Contract No. DE-AC07-761001570 FIN No. A6429 8203300311 020220 pQEGnG w.n.

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FORM EG&O 398 (n 1e ai)

INTERIM REPORT Accession No.

Report No. EGG-EA-5763

, Contract Program or Project

Title:

Selected Operating Reactor Issues Program (III)

Subject of this Document:

Technical Specifications for Redundant Decay Heat Removal Capability, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Type of Document:

Technical Evaluation Report Author (s):

J. A. Steverson Date of Document:

February 1982 Responsible NRCIDOE Individual and NRCIDOE Office or Division:

J. N. Donohew, Division of Licensing, NRC This document was prepared primarily for preliminary or internal use. it has not received full review and approval. Since there may be substantive changes, this document should not be considered final.

EG&G Idaho, Inc.

Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C.

Under DOE Contract No. DE-AC07 761D01570 NRC FIN No. A6429 INTERIM REPORT t-

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TECHNICAL SPECIFICATIONS FOR REDUNDANT DECAY HEAT REMOVAL CAPABILITY

'CALVERT CLIFFS NUCLEAR POWER' PLANT, UNIT NOS. 1 AND 2 4

Docket Nos. 50-317 and 50-318 i

i J. A. Steverson  :

Reliability and Statistics Branch Engineering Analysis Division. ,

j. EG&G Idaho, Inc.

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Draft 1-27-82 l TAC No. 42108 and 42109 1

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l ABSTRACT This report reviews the Calvert Cliffs Nuclear Power Plant, Unit  !

Nos. 1 and 2, technical specifications for redundancy in decay neat removal capability for all modes of operation.

FOREWORD This report is supplied as part of the " Selected Operating Reactor Issues Program (III)" being conducted for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Licensing, by EG&G Idano, Inc., Reliability and Statistics Branch.

The U.S. Nuclear Regulatory Commission funded the work under the authorization, B&R 20 19 01 06, FIN No. A6429.

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TECHNICAL EVALUATION REPORT TECHNICAL SPECIFICATIONS FOR REDUNDANT DECAY HEAT REMOVAL CAPABILITY CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2

1.0 INTRODUCTION

e A number of events have occurred at operating Pressurized Water Reactor

g (PWR) facilities where decay heat removal capability has been seriously degraded due to inadequate administrative controls during shutdown modes of operation. One of these ev'ents, described in IE Information Notice 80-20,I

, occurred at the Davis-Besse, Unit No. I plant on April 19, 1980. In IE Bul-letin 80-12,2 dated May 9, 1980, licensees were requested to immediately implement administrative controls which would ensure that proper means are available to provide redundant methods of decay heat removal. While the function of the bulletin was to effect immediate action with regard to this j problem, the NRC considered it necessary that an amendment of each license be made to provide for permanent long term assurance that redundancy in decay heat removal capability will be maintained. By letter dated June 11, 1980,3 all PWR licensees were requested to: 1) propose changed technical 3

specifications (TS) that provide for redundancy in decay heat removal l capability in all modes of operation, 2) use the NRC model TS (Appendix A) which provide an acceptable solution of the concern and include appropriate safety analyses as bases, and 3) submit the proposed TS with the bases by October 11, 1980. '

Baltimore Gas and Electrit Company submitted proposed revisions for ,

decay heat removal to their Calvert Cliffs TS on January 8, 1981.4 2.0 DISCUSSION

- Calvert Cliffs, Unit Nos. 1 and 2, are two loop Combustion Engineering (CE) PWR plants. The following discussion evaluates the proposed TS sub-  ;

. mitted by Baltimore Gas and Electric Company for redundant decay heat 1

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removal as requested by the NRC. The proposed TS are compared to the model

' TS during. equivalent operational modes. The following sections of the CE 5

Standard Technical Specifications apply to this task:

3/4.4 REACTOR COOLANT SYSTEM  !

3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION 3/4.9 REFUELING OPERATIONS 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION

- t During STARTUP and POWER OPERATION, the NRC model TS indicate that

with less than four pumps operating (two in each loop), the plant be in HOT l STANDBY within one hour. Calvert Ciffs proposed TS do not require the plant to be in HOT STANDBY when less than four pumps are operating. Rather, STARTUP and POWER OPERATION may proceed, as stated in proposed Specifica-1 tion 3.4.1.1, when

J a) one pump is not operating and THERMAL POWER is restricted to j 180% of RATED THERMAL POWER, or b) two pumps in opposite loops are not operating and THERMAL POWER is restricted to <51.1% of RATED THERMAL POWER, or

! c) two reactor coolant pumps in the same loop are not operating and i THERMAL POWER is restricted to 146.8% of RATED THERMAL POWER.

Also during STARTUP and POWER OPERATION, Calvert Cliffs proposed TS do not include Surveillance Requirement 4.4.1.1 of the NRC model TS; they require the coolant loops be verified to be in operation and circulating -

reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. .

With no coolant loop in operation during H0T STANDBY and SHUTOOWN, ,

Calvert Cliffs does not require all operations involving a reduction in

. boron concentration to be suspended, as in Specifications 3.4.1.2 ~and .

3.4.1.3 of the model TS.

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During SHUTOOWN, the NRC model TS require two of four coolant loops to be OPERABLE. The model TS include an associated steam generator with each of the two reactor coolant loops; Calvert Cliffs, however, does not specify that steam generators must be OPERABLE. Calvert Cliffs proposed TS omitted the three following Surveillance Requirements for SHU100WN:

9 4.4.1.3.1: The required shutdown cooling loop (s) shall be determined OPERABLE for Specification 4.0.S.

O 4.4.1.3.2: The required reactor coolant pump (s), if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.3.3: The required steam generator (s) shall be determined OPERABLE by verifying secondary side water level to be >_ at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

During REFUELING, the NRC model TS indicate, in Surveillance Require-ment 4.9.8.1, at least one shutdown cooling loop must be verified to be in operation and circulating reactor coolant at a flow rate of 13000 gpm at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; the proposed TS verify the flow rate of $3000 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3.0 CONCLUSION

The technical specifications proposed by Calvert Cliffs for redundant decay heat removal capability agree with the NRC model TS with the exception of the points noted above.

4.0 REFERENCES

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1. NRC IE Information Notice 80-20, May 8, 1980.

. 2. NRC IE Bulletin 80-12, May 9, 1980.

3. NRC letter, D. G. Eisenhut, To All Operating Pressurized Water Reactors (PWR's), dated June 11, 1980.

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4. Baltimore Gas and Electric Co. letter, A. E. Lundvall to NRC, H. Denton, dated January 8, 1981.

S. Standard Technical Specifications for Combustion Engineering Pressur-ized Water Reactors, NUREG-0212, Rev. 2, Fall 1980.

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p APPENDIX A MODEL TECHNICAL SPECIFICATIONS FOR REDUNDANT DECAY HEAT REMOVAL FOR COMBUSTION ENGINEERING PRESSURIZED WATER REACTORS (PWR's) 4 0

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3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION

,STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.4.1.1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation.

O APPLICABILITY: I and 2.*

ACTION:

With less than the above required reactor coolant pumps in operation, be in at least H0T STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

SURVEILLANCE REQUIREMENT 4.4.1.1 The above required reactor coolant loops shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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REACTOR COOLANT SYSTEM >

. HOT STANDBY l LIMITING CONDITION FOR OPERATION ,..

3.4.1.2 a. The reactor coolant loops listed below shali ..e OPERABLE:

a

1. Reactor Coolant Loop (A) and at least one associated reactor coolant pump,
2. Reactor Coolant Loop (B) and at least one associated

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b. At least one of the above Reactor Coolant loops shall be in operation.*

I APPLICABILITY: MODE 3 4 ACTION:

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a. With less than the above required reactor coolant loops OPERABLE, restore the required loops to OPERABLE status within 7E hours or

] be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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

4 SURVEILLANCE REQUIREMENT 4.4.1.2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.2.2 At least one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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  • All reactor coolant pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 100F below saturation temperature.

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REACTOR COOLANT SYSTEM

  • SHUTDOWN i LIMITING CONDITION FOR OPERATION i

3.4.1.3 a. At least two of the coolant loops listed below shall be

$ OPERABLE:

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. 1. Reactor Coolant Loop (A) and its associated steam gen-

.. eratpr and at least one associated reactor coolant pump, ,

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2. Reactor Coolant Loop (B) and its associated steam gen- f' erator and at least one associated reactor coolant pump,
3. Shutdown Cooling Loop (A)#  ;

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4. Shutdown Cooling Loop (B)#

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b. At least one of the above coolant loops shall be in '

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APPLICABILITY: MODES 4** and 5** j ACTION: (

a. With less than the above required loops OPERABLE, immediately  ;

initiate corrective action to return the required coolant '

loops to OPERABLE status as soon as possible; be in COLD  :

l SHUTDOWN within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />. I

b. With no conlant loop in operation, suspend all operations  !

involving a reduction in boron concentration of the Reactor  ;

Coolant System and immediately initiate corrective action to t return the required coolant loop to operation. l All reactor coolant pumps and decay heat removal pumps may be -

de-energized for up to I 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 100F below saturation  ;

temperature.

' ** A reactor coolant pump shall not be started with one or more of the RCS cold leg temperatures less than or equal to (275)0F unless (1) the ,

, pressurizer water volume is less than 900 cubic feet or (2) the secondary l water temperature of each steam generator is less than 46 0F above each

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of- the RCS cold leg temperatures.

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  1. The normal or emergency power source may be inoperable in MODE 5.

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENT 4.4.1.3.1 The required residual heat removal loop (s) shall be determined OPERABLE per Specification 4.0.5.

4.4.1.3.2 The required reactor coolant pump (s), if not in operation, shall e be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.3.3 The required steam generator (s) shall be determined OPERABLE by verifying secondary side water level to be greater than or equal to ( )%

at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.1.3.4 At least one coolant loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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) REFUELING OPERATION 5 i

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ALL WATER LEVELS 4

LIMITING CONDITION FOR OPERATION l .t 3.9.8.1 At least one shutdown loop shall be in operation.

i 0 APPLICABILITY: MODE 6 l

ACTION:

a. With less than one shutdown cooling loop in operation, except as provided in b. below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron
concentration of the Reactor Coolant System. Close all contain-f ment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b. The shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE
ALTERATIONS in the vicinity of the reactor pressure vessel hot j legs.
c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENT 4.9.8.1 At least one shutdown cooling loop shall be verified to be in -

operation and circulating reactor coolant at a flow rate of greater than or i equal to (3000)'gpm at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent shutdown cooling loops shall be OPERABLE.* ,

APPLICABILITY: MODE 6 when the water level above the_ top of the irradiated fuel assemblies seated within the reactor pre:sure vessel is less than 23 feet.

ACTION:

a. With less than the required shutdown cooling loops OPERABLE, immediately initiate corrective action to return loops to OPERABLE status as soon as possib'e.
b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENT

.4.9.8.2 The required shutdown cooling loops shall be determined OPERABLE per Specification 4.0.5.

r The normal or emergency power source may be inoperable for each shutdown cooling loop.

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3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION

, The plant is designed to operate with both reactor coolant loops and associated reactor coolant pumps in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients.

O In MODE 3, a single reactor coolant loop provides sufficient heat removal cap.-bility for removing decay heat; however, single failure con-siderations require that two loops be OPERABLE.

In MODES 4 and 5, a single reactor coolant loop or shutdown cooling loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops be OPERABLE. Thus, if the reactrr coolant loops are not OPERABLE, this specification requires two shtdown cooling loops to te OPERABLE.

The operation of one Reactor Coolant Pump or one shutdown cooling pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with boron reductions will, therefore, be within the capability of operator recognition and control.

The restrictions on starting a Reactor Coolant Pump during MODES 4 and 5 with one or more RCS cold legs less than or equal to (275)0F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to 10 CFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either (1) restricting the water volume in the pressurizer and thereby providing a volume for the primary coolant to expand into, or (2) by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than (46)0F above each of the RCS cold leg temperatures.

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REFUELING OPERATIONS BASES 3/4.9.8 COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in e operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 1400F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the '

effect of a boron dilution incident and prevent boron stratification.

The requirement to have two shutdown cooling loops OPERABLE when there is less than 23 feet of water above the core, ensures that a single failure of the operating chutdown cooling loop will not result in a complete loss of decay heat removal capability. With the reactor vessel head removed and 23 feet of water above the core, a large heat sink is available for core cooling, thus, in the event of a failure of the operating shutdown cooling loop, adequate time is provided to initiate emergency procedures to cool the core.

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