Text

Amend 11 to License NPF-38,revising Tech Specs by Adding Power Reduction Curve for Use Following full- or part-length Control Element Assembly Misalignment
	ML20212G413
Person / Time
Site:	Waterford
Issue date:	01/09/1987
From:	Joshua Wilson; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20212G418	List: ML20212G413; ML20212G424;
References
	NUDOCS 8701200449
	Download: ML20212G413 (27)
	v • d • e

.

puay#

^

0 UNITED STATES f

g 5n g

NUCLEAR REGULATORY COMMISSION y

g

'7 l WASHINGTON, D. C. 20655 o

a

%....*f 4

LOUISIANA POWER AND LIGHT COMPANY DOCKET NO. 50-382 WATERFORD STEAK ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 11 License No. NPF-38 1.

The Nuclear Regulatory Comission (the Comission) has found that:

4 A.

The applications for amendment, dated August 29, and September 25, 1986, as supplementea by letters dated October 1, and October 23, 1986 by Louisiana Power and Light Company (licensee), comply with standards and requirements of the Atomic Energy Act of 1954, as

'I amended (the Act) and the Comission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the prosisions of the Act, and the regulations of the Comission; i

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 Comission's regulations; i

D.

The issuance of this amendment will not be inimical to the coman defense and security or to the health and safety of the public; E.

The issuance of this amendment is in accordance with 10 CFR Part 51 l

of the Connission's regulations and all applicable reruirements l

have been satisfied.

l 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. NPF-38 is hereby amended to read as follows:

l 8701200449 870109 DR ADOCK 05000382 PDR I

2-(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 11, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in this license.

LP&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective as of the date of issuance.

FORTHENUCLEARREGULATORYCOMMISSIOk OwJ.A JadsH. Wilson,ProjectManager PWR Project Directorate No. 7 Division of PWR Licensing-B

Attachment:

Changes to the Technicel Specifications Date of Issuance: January 9,1987 e

/

3

,. - _ _ _. -. - _..., _, _. _ ~

January 9, 1987 ATTACHMENT TO LICEFSE AMENDMENT NO. 11 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 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 area of change. Also to be replaced are the following overleaf pages to the amended pages.

Amendment Pages Overleaf Paces IV III XIX XX 3/4 1-1 3/4 1-2 3/4 1-3 3/4 1-3a 3/4 1-9 3/4 1-10 3/4 1-11 3/4 1-12 3/4 1-18 3/4 1-17 3/4 1-19 3/4 1-20 3/4 1-20a 3/4 10-1 3/4 10-2 3/4 10-3 3/4 10-4 B 3/4 1-1 B 3/4 1-2 Page 3/4 1-4 is being reissued without change.

INDEX SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PAGE 2.1 SAFETY LIMITS 2.1.1. REACTOR C0RE.............................................

2-1 2.1.1.1 DNBR.....................................................

2-1 2.1.1.2 PEAK LINEAR HEAT RATE....................................

2-1 1

2.1.2 REACTOR COOLANT SYSTEM PRESSURE..........................

2-1 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SETP0INTS.....................................

2-2 t

BASES SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 REACTOR C0RE...............................................

B 2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE............................

B 2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SETP0INTS.....................................

B 2-2 k

o a

WATERFORD - UNIT 3 III AMENDMENT NO. 5 au

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY..............................................

3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - ANY CEA WITHDRAWN..................

3/4 1-1

(

SHUTDOWN MARGIN - ALL CEAS FULLY INSERTED............

3/4 1-3 MODERATOR TEMPERATURE COEFFICIENT....................

3/4 1-4 MINIMUM TEMPERATURE FOR CRITICALITY..................

3/4 1-5 3/4.1.2 BORATION SYSTEMS FLOW PATHS - SHUTD0WN................................

3/4 1-6 FLOW PATHS - 0PERATING...............................

3/4 1-7 CHARGING PUMPS - SHUTD0WN............................

3/4 1-8 CHARGING PUMPS - 0PERATING...........................

3/4 1-9 BORIC ACID MAKEUP PUMPS - SHUTD0WN...................

3/4 1-10 BORIC ACID MAKEUP PUMPS - OPERATING..................

3/4 1-11 BORATED WATER SOURCES - SHUTD0WN.....................

3/4 1-12 BORATED WATER SOURCES - OPERATING....................

3/4 1-14 BORON DILUTION.......................................

3/4 1-15 3/4.1.3 MOVABLE CONTROL ASSEMBLIES CEA POSITION...........

3/4 1-18 POSITION INDICATOR CHANNELS - OPERATING..............

3/4 1-21 POSITION INDICATOR CHANNELS - SHUTDOWN...............

3/4 1-22 CEA DROP TIME........................................

3/4 1-23 SHUTDOWN CEA INSERTION LIMIT.........................

3/4 1-24 REGULATING CEA INSERTION LIMITS......................

3/4 1-25 PART-LENGTH CEA INSERTION LIMITS.....................

3/4 1-28 WATERFORD - UNIT 3 IV AMENDMENT NO.11

e INDEX LIST OF FIGURES FIGURE PAGE 3.1-0 SHUTDOWN MARGIN AS A FUNCTION OF COLD LEG TEMPERATURE............................

3/4 1-3a 3.1-1 REQUIRED STORED BORIC ACID VOLUME AS A FUNCTION OF CONCENTRATION......................................

3/4 1-13 3.1-1A REQUIRED POWER REDUCTION AFTER SINGLE CEA DEVIATION 3/4 1-20a l

3.1-2 CEA INSERTION LIMITS VS THERMAL P0WER..............

3/4 1-27 3.1-3 PART LENGTH CEA INSERTION LIMIT VS THERMAL POWER...

3/4 1-28a 3.2-1 ALLOWABLE PEAK LINEAR HEAT RATE VS BURNUP..........

3/4 2-2 3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON C0LSS.........

3/4 2-8 3.2-3 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE)......

3/4 2-9 3.4-1 DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY >1.0 pCi/ GRAM DOSE EQUIVALENT I-131.......

3/4 4-27 3.4-2 REACTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS (HEATUP)...........................................

3/4 4-30 1

3.4-3 REACTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS (C00LDOWN).......................................

3/4 4-31 l

3.6-1 CONTAINMENT PRESSURE VS TEMPERATURE...............

3/4 6-12 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST..........

3/4 7-26 5.1-1 EXCLUSION AREA.....................................

5-2 5.1-2 LOW POPULATION Z0NE................................

5-3 5.1-3 SITE BOUNDARY FOR RADI0 ACTIVE GASE0US AND LIQUID EFFLUENTS...................................

5-4 6.2-1 0FFSITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPP0RT.................................

6-3 6.2-2 PLANT OPERATIONS ORGANIZATION......................

6-4 l

WATERFORD - UNIT 3 XIX AMENDMENT NO. 11

INDEX

LIST OF TABLES TABLE E

1.1 FREQUENCY N0TATION......................................

1-9 1.2 OPERATIONAL M00ES.......................................

1-10 2.2-1.-

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETP0 INT LIMITS..................................................

2-3 2.2-2 CORE PROTECTION CALCULATOR ADDRESSABLE CONSTANTS........

2-5 MONITORING FREQUENCIES FOR BORON DILUTION DETECTION 3.1-1 K,ff > 0.98.............................................

3/4 1-17 3.1-2 0. 98 > K, f f > 0. 9 7...................................... 3/4 1-17a 3.1-3

0. 9 7 > K, f f > 0. 9 6......................................

3/4 1-17b 3.1-4 0.96 > K,ff > 0.95m.m.....~ ~... ~.~.- ~ ~......... 3/4 1-17c 3.1-5 K,ff < 0.95.............................................

3/4 1-17d 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION......................

3/4 3-3 3.3-2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES.......

3/4 3-8 4.3-1 REACTOR PROTECTIVE INSTRUMENTATIO REQUIREMENTS.....................N SURVEILLANCE

....................... 3/4 3-10 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM I N ST RUMENT AT ION............ '.............................

3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES.............................

3/4 3-19 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES...............

3/4 3-22 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............

3/4 3-25 3.3-6 RADIATION MONITORING INSTRUMENTATION....................

3/4 3-29 t

4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................... 3/4 3-32 3.3-7 SEISMIC MONITORING INSTRUMENTATION......................

3/4 3-36 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................

3/4 3-37 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION...............

3/4 3-39 WATERFORD - UNIT 3 XX AMENDMENT NO. 9

~

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - ANY CEA WITHDRAWN LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 5.15%

delta k/k when T,yg is greater than 200*F or 2.0% delta k/k when T,yg is less-than or equal to 200*F.

APPLICABILITY: MODES 1, 2*, 3, 4, and 5 with any full length CEA fully or partially withdrawn.

l ACTION:

With the SHUTDOWN MARGIN less thar. that required above, immediately initiate l

and continue boration at greater than or equal to 40 gpm of a solution con-taining greater than or equal to 1720 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS l

4 4.1.1.1.1 With any full length CEA fully or partially withdrawn, the SHUTDOWN MARGIN shall be determined to be greater than or equal to that required above:

i a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after detection of an inoperable CEA(s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the CEA(s) is inoperable.

If the inoperable CE.\\ is immovable or untrippable, the above required SHUTDOWN MARGIN shall be verified acceptable with an increased dllowance for the withdrawn worth of the immovable or untrippable CEA(c),

i l

b.

When in MODE 1 or MODE 2 with K,ff greater than or equal to 1.0, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that CEA group withdrawal is j

within the Transient Insertion Limits of Specification 3.1.3.6.

When in MODE 2 with K,ff less than 1.0, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to c.

i achieving reactor criticality by verifying that the predicted critical CEA position is within the limits of Specification 3.1.3.6.

l i

l See Special Test Exception 3.10.1.

f i

WATERFORD - UNIT 3 3/4 1-1 AMENDMENT NO. 11 i

REACTIVITY CONTPOL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.

Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of e. below, with the CEA groups at the Trans,ient Insertion Limits of Specification 3.1.3.6.

When in MODE 3, 4, or 5, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration e.

of at least 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 to demonstrate agreement within + 1.0% delta k/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.le., above.

The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 EFPDs after each fuel loading.

WATERFORD - UNIT 3 3/4 1-2 AMENDMENT NO. 11

~

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - ALL CCAS FULLY INSERTED LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to that shown in Figure 3.1-0.

APPLICABILITY:

MODE 2*#, 3, 4 and 5 with all CEAs fully inserted.

l ACTION:

With the SHUTDOWN MARGIN less than that shown in Figure 3.1-0, immediately initiate and continue boration at greater than or equal to 40 gpm of a solu-tion containing greater than or equal to 1720 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.2.1 With all full length CEAs fully inserted, the SHUTDOWN MARGIN shall be determined to be greater than or equal to that shown in Figure 3.1-0.

When in MODE 2 with k,ff less than 1.0, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to a.

achieving reactor criticality by verifying that the predicted critical CEA position is within the limits of Specification 3.1.3.6.

b.

When in MODES 3, 4, or 5, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by considera-tion of the following factors:

1.

Reactor Coolant System boron concentration, 2.

Ct A position, 3.

Reactor Coolant System average temperature, l

4.

Fuel burnup based on gross thermal energy generation, 5.

Xenon concentration,and 6.

Samariun concentration.

4.1.1.2.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within i 1.0% delta k/k at least once per 31 Effective Full Power Days (EFPD). This comparison shall consider at least those factors stated in Specification 4.1.1.2.lb, above.

The predicted reac-tivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 EFPD after each fuel loading.

With k,7f less than 1.0

See Special Test Exception 3.10.1 WATERFORD - UNIT 3 3/4 1-3 AMENDMENT NO. 11

6:

g i

y i

i 5.

i M

(500 F,4.15%)

4 h

d i

O 6

Ej3 E

2 3:o O

I

$2 3

l 1!

(400 F,1.00%)

l l

1 1

I O

100 200' 300 400' 500' 600' COLD LEG TEMPERATURE (*F)

Figure 3.1-0 SHUTDOWN PARGIN AS A FUNCTION OF COLD LEG TEMPERATURE WATERFORD - UNIT 3 3/4 1-3a AMENDMENT NO. 11

l REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be:

~4 a.

Less positive than 0.2 x 10 delta k/k/*F whenever THERMAL POWER is < 70% RATED THERMAL POWER, and

~4 b.

Less positive than 0.0 x 10 delta k/k/*F whenever THERMAL POWER is > 70% RATED THERMAL POWER, and

~4 c.

Less negative than -2.5 x 10 delta k/k/*F at RATED THERMAL POWER.

APPLICABILITY:

MODES 1 and 2*#

ACTION:

With the moderator temperature coefficient outside any one of the above limits, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS i

4.1.1.3.1 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.

4.1.1.3.2 The HTC 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 greater than 15% of RATED THERMAL POWER, prior to reaching 40 EEPC core burnup.

c.

At any THERMAL POWER, within 7 EFPD of reaching two-thirds of I

expected core burnup.

"With Keff greater than or equal to 1.0.

See Special Test Exception 3.10.2.

i l

WATERFORD - UNIT 3 3/4 1-4 AMENDMENT NO. 5 I

-____________-_7 8

e i

e 8

h.

.m memm a mmmmmmma

REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two independent charging pumps shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With only one charging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANOBY and borated to a SHUTOOWN MARGIN equivalent to the requirements of Specification 3.1.1.1 or 3.1.1.2, whichever is applicable, within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging pumps to OPERABLE status within the next 7 days or be in COLD SHUTOOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS l

4.1.2.4 Each required charging pump shall be demonstrated OPERABLE at least once every 18 months by verifying that each charging pump starts in response to an SIAS test signal.

I WATERFORD - UNIT 3 3/4 1-9 AMENDMENT NO. 11

REACTIVITY CONTROL SYSTEMS BORIC ACID MAKEUP PUMPS - SHUTOOWN LIMITING CONDITION FOR OPERATION 3.1.2.5 At least one boric acid makeup pump shall be OPERABLE and capable of being powered from an OPERABLE emergency bus if only the flow path through the boric acid pump in Specification 3.1.2.la. is OPERABLE.

APPLICABILITY:

MODES 5 and 6.

ACTION:

With no boric acid makeup pump OPERABLE as required to complete the flow path of Specification 3.1.2.la., suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE REQUIREMENTS 4.1.2.5 No additional Surveillance Requirements other than those required by Specification 4.0.5.

I WATERFORD - UNIT 3 3/4 1-10

REACTIVITY CONTROL SYSTEMS BORIC ACID MAKEUP PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 At least the boric acid makeup pump (s) in the boron injection flow 1

path (s) required OPERABLE pursuant to Specification 3.1.2.2a. shall be OPERABLE and capable of being powered from an OPERABLE emergency bus if the flow path through the boric acid pump (s) in Specification 3.1.2.2a. is OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With one boric acid makeup pump required for the bcron injection flow path (s) pursuant to Specification 3.1.2.2a. inoperable, restore the boric acid makeup pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and borated to a SHUTDOWN MARGIN equivalent to the require-ments of Specification 3.1.1.1 or 3.1.1.2, whichever is applicable, restore the above required boric acid makeup pump (s) to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.6 Each required boric acid makeup pump shall be demonstrated OPERABLE at least once every 18 months by verifying that each boric acid makeup pump start's in response to an SIAS test signal.

WATERFORD - UNIT 3 3/4 1-11 AMENDMENT NO. 11

REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE:

One boric acid makeup tank with a boron concentration between 2.25 a.

and 3.50 weight percent and a minimum borated water volume of 4150 gallons (36% indicated level).

b.

The refueling water storage pool (RWSP) with:

1.

A minimum contained borated water volume of 65,465 gallons (12%

indicated level), and 2.

A minimum boron concentration of 1720 ppm.

APPLICABILITY: MODES 5 and 6.

ACTION:

With no borated water sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE REQUIREMENTS 4.1.2.7 The above required borated water source shall be demonstrated OPERABLE:

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the Reactor Auxiliary Building air a.

temperature is less than 55'F by verifying the boric acid makeup tank solution is greater than 55'F (when it is the source of borated water).

b.

At least once per 7 days by:

1.

Verifying the boron concentration of the water, and 2.

Verifying the contained borated water volume of the tank.

WATERFORD - UNIT 3 3/4 1-12 AMENDMENT NO. 10

TABLE 3.1-1 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR K,ff GREATER-THAN 0.98 K,ff >0.98 OPERATIONAL Number of Operatina Charaina Pumps

MODE O

1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months Operation not allowed **

4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months Operation not allowed **

5 RCS filled 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months Operation not allowed **

5 RCS partially 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Operation not allowed **

drained 6

Operation not allowed **

Charging pump OPERABILITY for any period of time shall constitute OPERABILITY for the entire monitoring frequency.

- The required charging pumps shall be verified to be inoperable by racking out their motor circuit breakers.

l i

l l

WATERFORD - UNIT 3 3/4 1-17 AMENDMENT NO. 9 l

REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES CEA POSITION LIMITING CONDITION FOR OPERATION 3.1.3.1 All full-length (shutdown and regulating) CEAs, and all part-length CEAs which are inserted in the core, shall be OPERABLE with each CEA of a given group positioned within 7 inches (indicated position) of all other CEAs in its group.

APPLICABILITY:

MODES 1* and 2*.

ACTION:

With one or more full-length CEAs inoperable due to being immovable a.

as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With more than one full-length or part-length CEA inoperable or misaligned from any other CEA in its group by more than 19 inches (indicated position), be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With one full-length or part-length CEA misaligned from any other c.

CEA in its group by more than 19 inches, operation in MODES 1 and 2 may continue, provided that core power is reauced in accordance with Figure 3.1-1A and that within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the misaligned CEA is either:

1.

Restored to OPERABLE status within its above specified alignment requirements, or 2.

Declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

After declaring the CEA inoperable, operation in MODES 1 and 2 may continue pursuant to the requirements of Specification 3.1.3.6 provided:

a)

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the remainder of the CEAs in the group i

I with the inoperable CEA shall be aligned to within 7 inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits shown on Figure 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.

b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Otherwise, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l

See Special Test Exceptions 3.10.2 and 3.10.4.

WATERFORD - UNIT 3 3/4 1-18 AMENDMENT NO.ll n

l REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued) d.

With one or more full-length or part-length CEAs misaligned from any other CEAs in its group by more than 7 inches but less than or equal to 19 inches, operation in MODES 1 and 2 may continue, provided that core power is reduced in accordance with Figure 3.1-1A and that within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the misaligned CEA(s) is either:

1.

Restored to OPERABLE status within its above specified alignment requirements, or 2.

Declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

After declaring the CEA inoperable, operation in MODES 1 and 2 may continue pursuant to the requirements of Specification 3.1.3.6 provided:

a)

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the remainder of the CEAs in the group with the inoperable CEA shall be aligned to within 7 inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits shown on Figure 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.

b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Otherwise, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

e.

With one full-length CEA inoperable due to causes other than addressed by ACTION a., above, and inserted beyond the Long Term Steady State Insertion Limits but within its above specified alignment requirements, operation in MODES 1 and 2 may continue pursuant to the requirements of Specification 3.1.3.6.

f.

With one full-length CEA inoperable due to causes other than addressed by ACTION a., above, but within its above specified alignment require-ments and either greater than or equal to 145 inches withdrawn or within the Long Term Steady State Insertion Limits if in full-length CEA group 6, operation in MODES 1 and 2 may continue.

g.

With one part-length CEA inoperable and inserted in the core, operation may continue provided the alignment of the inoperable part-length CEA is maintained within 7 inches (indicated position) of all other part-length CEAs in its group and the CEA is maintained pursuant to the requirements of Specification 3.1.3.7.

WATERFORD - UNIT 3 3/4 1-19 AMENDMENT NO. 11

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each full-length and part-length CEA shall be determined to be within 7 inches (indicated position) of all other CEAs in its group at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when one CEAC is inoperable or when both CEACs are inoperable, then verify the individual CEA positions.et least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.'3.1.2 Each full-length CEA not fully inserted and each part-length CEA which is inserted in the core below 145 inches shall be determined to be OPERABLE by movement of at least 5 inches in any one direction at least once per 31 days.

WATERFORD - UNIT 3 3/4 1-20

Required Power Reduction after Single CEA Deviation

I I

e u.

W3go zs owz Q. g w -

ow0C E $ E h 30 (60 MIN,30%)

52 O

E o < "u O

g$P 20 2U*2 4

DDbE 10; 2,oe U

2m2 2

0.

I i

i 0

15 30 45 60 l

TIME AFTER CEA DEVIATION (MINUTES) 4' hen core power is reduced to 60% of rated power per this limit curve, further reduction is not required by this specification.

Figure 3.1 - 1A AMENDMENT NO. 11 WATERFORD UNIT 3 3/41-20a

3/4.10 SPECIAL TEST' EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 or 3.1.1.2 may be suspended for measurement of CEA worth and SHUTDOWN MARGIN provided reactivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s).

APPLICABILITY: MODES 2 AND 3*.

ACTION:

a.

With any full-length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, immedi-ately initiate and continue boration at greater than or equal to 40 gpm of a solution containing greater than or equal to 1720 ppm boron or its equivalent until the SHUIDOWN MARGIN required by Specification 3.1.1.1 is restored.

b.

With all full-length CEAs fully inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 40 gpm of a solution containing greater than or equal to 1720 ppm baron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.2 is restored.

SURVEILLANCE REQUIREMENTS l

l 4.10.1.1 The position of each full-length and part-length CEA required either l

partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position within 7 days l

prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.

" Operation in MODE 3 shall be limited to 6 consecutive hours.

WATERFORD - UNIT 3 3/4 10-1 AMENDMENT NO. 11

.+--.a-

-g fgyv.-mx

.w-

,,.--g.-

+.9 y_

-,.Fr- - ' ' '-

r-w wh=-

m-'7--'-'---m F-

"-e-F---

"'---" " * -~ * - ' "

SPECIAL TEST EXCFPTIONS 3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT, GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.1'0. 2 The moderator temperature coefficient, group height, insertion, and power distribution limits of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7, and the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 may be suspended during the performance of PHYdICS TESTS provided:

a.

The THERMAL POWER is restricted to the test power plateau which shall not exceed 85% of RATED THERMAL POWER, and b.

The limits of Specification 3.2.1 are maintained and determined as specified in Specification 4.10.2.2 below.

APPLICABILITY: MODES 1 and 2.

c ACTION:

With any of the limits of Specification 3.2.1 being exceeded while the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7, and the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended, either:

a.

Reduce THERMAL POWER sufficiently to satisfy the requirements of Specification 3.2.1, or b.

Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined at least once per hour during PHYSICS TESTS in which the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7, or the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended and shall be i

verified to be within the test power plateau.

4.10.2.2 The linear heat rate shall be determined to be within the limits of i

Specification 3.2.1 by monitoring it continuously with the Incore Detector Monitoring System pursuant to the requirements of Specifications 4.2.1.2 and 3.3.3.2 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7, or the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended.

WATERFORD - UNIT 3 3/4 10-2

SPECIAL TEST EXCEPTIONS 3/4.10.3 REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION 3.10.3 The noted requirements of Tables 2.2-1 and 3.3-1 may be suspended during the performance of startup and PHYSICS TESTS, provided:

a.

The THERMAL POWER does not exceed 5% of RATED THERMAL POWER, and either b.

The reactor trip setpoints of the OPERABLE power level channels are set at less than or equal to 20% of RATED THERMAL POWER, or c.

The core protection calculator operating bypass permissive setpoints are increased to greater than the logarithmic power-hi trip setpoint specified in Table 2.2-1 and less than 5% RATED THERMAL POWER.

APPLICABILITY: During startup and PHYSICS TESTS.

ACTION:

With the THERMAL POWER greater than 5% of RATED THERMAL. POWER, immediately trip the reactor.

SURVEILLANCE REQUIREMENTS qg 4.10.3.1

ha THERMAL POWER shall be determined to be less than or equal to 5%

of RATED THERMAL POWER at least once per hour during startup and PHYSICS TESTS.

4.10.3.2 Each wide range logarithmic and power level neutron flux monitoring channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating startup and PHYSICS TESTS.

4 WATERFORD - UNIT 3 3/4 10-3 AMENDMENT NO. 11

SPICIAL TEST EXCEPTIONS 3/4.10.4 CENTER CEA MISALIGNMENT LIMITING CONDITION FOR OPERATION 3.10.4 The requirements of Specifications 3.1.3.1 and 3.1.3.6 may be suspended-during the performance of PHYSICS TESTS to determine the isothermal temperature coefficient, moderator tamperature coefficient, and power coefficient provided:

a.

Only the center CEA (CEA #1) is misaligned, and b.

The limits of Specification 3.2.1 are maintained and determined as specified in Specification 4.10.4.2 below.

APPLICABILITY: MODES I aad ?.

ACTION:

With any of the limits of Specification 3.2.1 being exceeded while the requirements of Specifications 3.1.3.1 and 3.1.3.6 are suspended, either:

a.

Reduce THERMAL POWER sufficiently to satisfy the requirements of Specification 3.2.1, or b

Be in h0T STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS i

4.10.4.1 The THERMAL POWER shall be determined at least once per hour during PHYSICS TESTS in which the requirements of Specifications 3.1.3.1 and/or 3.1.3.6 are suspended and shall be verified to be within the test power plateau.

i 4.10.4.2 The linear heat rate shall be determined to te within the limits of i

Specification 3.2.1 by monitoring it continuously with the Incore Detector Monitoring System pursuant to the requirements of Specifications 4.2.1.2 and 3.3.3.2 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the requirements of Specifications 3.1.3.1 and/or 3.1'.3.6 are suspended.

WATERFORD - UNIT 3 3/4 10-4

3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN SHUTDOWN MARGIN is the amount by which the core is subcritical, or would be subcritical immediately following a reactor trip, considering a single malfunction resulting in the highest worth CEA failing to insert.

The function of SHUTDOWN MARGIN is to ensure that the reactor remains subcritical following a design basis accident or anticipated operational During operation in MODES 1 and 2, with k,ff greater than or occurrence.

equal to 1.0, the transient insertion limits of Specification 3.1.3.6 ensure that sufficient SHUTDOWN MARGIN is available.

i SHUTDOWN MARGIN requirements vary throughout the core life as a function of fuel depletion and reactor coolant system (RCS) cold leg temperature (Tcold)*

The most restrictive condition occurs at E0L, with (Tcold) at no-load operating temperature, and is associated with a postulated steam line break accident and the resulting uncontrolled RCS cooldown.

In the analysis of this accident, the specified SHUTDOWN MARGIN is required to control the reactivity transient and ensure that the fuel performance and offsite dose criteria are satisfied. As (initial) T decreases, the potential RCS cooldown and the resulting reactiv-cold ity transient are less severe and, therefore, the required SHUTDOWN MARGIN also decreases.

Below T f about 200 F, the inadvertent deboration event becomes cold limiting with respect to the SHUTDOWN MARGIN requirements.

Below 200'F, the specified SHUTDOWN MARGIN ensures that sufficient time for operator actions exists between the initial indication of the deboration and the total loss of SHUTDOWN MARGIN.

Accordingly, the SHUTDOWN MARGIN requirements are based upon these limiting conditions.

Additional events considered in establishing requirements on SHUTDOWN MAR-GIN are single CEA withdrawal and startup of an inactive reactor coolant pump.

Other technical specifications that reference the Specifications on SHUT-DOWN MARGIN are:

3/4.1.2, BORATION SYSTEMS, 3/4.1.3, MOVABLE CONTROL ASSEMBLIES, 3/4.9.1, REFUELING OPERATIONS - BORON CONCENTRATION, and 3/4.10.1, SHUTDOWN MARGIN.

3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the assumptions used in the accident and transient analysis remain valid through each fuel cycle. The Surveillance Requirements for measurement of the MTC during each fuel cycle are adequate to confirm the MTC value since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup. 'The confirmation that 1

the measured MTC value is within its limit provides assurances that the coef-ficient will be maintained within acceptable values throughout each fuel cycle.

WATERFORD - UNIT 3 B 3/4 1-1 AMENDMENT NO. 11

l REACTIVITY CONTROL SYSTEMS BASES

_3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This sp(cification ensures that the reactor will not be made critical with the Reactor Coolant System cold leg temperature less than 520*F. This limita-tion is required to ensure (1) the moderator temperature coefficient is within its analyzed temperature ran its normal operating range, ge (2) the protective instrumentation is within (3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, (4) the reactor pressure vessel is above its minimum RT temperature, and (5) the ECCS analysis remains valid for the NDT peak linear heat rate of Specification 3.2.1.

3/4.1.2 BORATION SYSTEMS The boron injection system ensuras 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 makeup pumps, (5) associated heat trac-ing systems, and (6) an emergency power supply from OPERABLE diesel generators.

4 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 inoper-able. 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 SHUT-DOWN MARGIN from expected operating conditions of 2.0% delta k/k after xenon decay and cooldown to 200'F. The maximum expected boration capability require-ment occurs at EOL from full power equilibrium xenon conditions assuming the l

most eeactive CEA stuck out of the core and requires boric acid solution from the boric acid makeup tanks in the ellowable concentrations and volumes of t

Specification 3.1.2.8 plus approximately 19,000 gallons of 1720 ppe borated water from the refueling water storage pool or approximately 58,000 gallons of 1720 ppa borated water from the refueling water stori'e pool alone. The higher limit of 447,100 gallons is specified to be consister alth Specification 3.5.4 in order to meet the ECCS requirements.

With the RCS temperature below 200*F one injectir ystem is acceptable without single failure consideration on the basis of t stable reactivity con-dition of the reactor and the additional restrictions sibiting CORE ALTERA-TIONS and positive reactivity changes in the event the...sgle injection system becomes inoperable.

The boron capability required below 200*F is based uptn providing a 2%

delta k/k SHUTDOWN MARGIN after xenon decay and cooldown from 200*F to 140'F.

This condition requires either 5,465 gallons of 1720 ppm borated water from the refueling water storage pool or boric acid solution from the boric acid makeup tanks in accordance with the requirements of Specification 3.1.2.7.

WATERFORD - UNIT 3 ts 3/4 1-2 AMENDMENT NO.10 F

ML20212G413

Text

Attachment:

Navigation menu

Search