Text

Amend 9 to License NPF-38,changing Tech Specs to Redefine Senior Reactor Operator Responsibilities During Core Alterations & to Revise Boron Dilution Requirements While in Modes 5 & 6
	ML20207H558
Person / Time
Site:	Waterford
Issue date:	12/23/1986
From:	Joshua Wilson; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20207H563	List: ML20207H558; ML20207H603;
References
	NUDOCS 8701070559
	Download: ML20207H558 (19)
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UNITED STATES g

NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D. C. 20555 s

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LOUISIANA POWER AND LIGHT COMPANY DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. NPF-38 1.

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

A.

The applications for amendment, dated September 10 and October 1, 1960, as supplemented by letter dated October 6, 1986 by Louisiar.a Fower and Light Company (licensee), complies with standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations set forth in 10 CFR Chapter I; B.

The f acility will operate in confonnity with the application, the provisions of the Act, and the 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 Commission's regulations; D.

The issuance of this amendment will not be inimical to the comon defanse 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 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. NPF-38 is hereby amended to read as follows:

8701070559 861223 PDR ADOCK 05000382 p

PDR

-2 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications ccatained in Appendix A, as revised through Amendment No. 9, 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.

FOR THE NUCLEAR PEGULATOPY COMMISSION W

Jam H. Wilson, Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B

Attachment:

Ch6nges to the Technical Specifications Date of Issuance:

December 23, 1986 1

l l

December 23, 1986

ATTACHMENT TO LICENSE AMENDMENT NO. 9 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.

Amendirent Pages Overleaf Pages XX XIX XXI XXII 3/4 1-15 3/4 1-16 3/4 1-17 3/4 1-17a 3/4 1-17b 3/4 1-17c 3/4 1-17d 3/4 1-18 B 3/4 1-3 B 3/4 1-4 6-1 6-2

--v--s--

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INDEX LIST OF FIGURES FIGURE PAGE 3.1-1 MINIMUM BORIC ACID STORAGE TANK VOLUME AND TEMPERATURE AS A FUNCTION OF STORED BORIC ACID CONCENTRATION.........,.......................

3/4 1-13 3.1-2 CEA INSERTION LIMITS VS THERMAL POWER..............

3/4 1-27 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 O

LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS (HEATUP)...........................................

3/4 4-30 3.4-3 REACTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS (C00LDOWN).........................................

3/4 4-31 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 GASEOUS AND LIQUID EFFLUENTS...................................

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

6-3 l

6.2-2 PLANT OPERATIONS ORGANIZATION......................

6-4 i

{

WATERFORD - UNIT 3 XIX

INDEX LIST OF TABLES TABLE PAGE 1.1 FREQUENCY N0TATION......................................

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

1-10 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIM 1TS..................................................

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,ff > 0.97......................................

3/4 1-17a 3.1-3 0.97 > K,7f > 0.96......................................

3/4 1-17b 3.1-4 0.96 > K,ff > 0.95......................................

3/4 1-17c 3.1-5 Keff 0.95.............................................

3/4 1-17d 5

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 INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................

3/4 3-10 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.........................................

3/4 3-14 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 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

INDEX LIST OF TABLES (Continued)

TABLE PAGE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................

3/4 3-40 3.3-9 REMOTE SHUTDOWN INSTRUMENTATION.......................

3/4 3-42 4.3-6 REMOTE SHUTDOWN INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................

3/4 3-43 3.3-10 ACCIDENT MONITORING INSTRUMENTATION...................

3/4 3-45 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................

3/4 3-46 3.3-11 FIRE DETECTION INSTRUMENTS............................

3/4 3-51 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.......................................

3/4 3-56 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................

3/4 3-58 3.3-13 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION.......................................

3/4 3-61 4.3-9 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SU1VEILLANCE REQUIREMENTS.............

3/4 3-65 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION...........................

3/4 4-15 4.4-2 STEAM GENERATOR TUBE INSPECTION.......................

3/4 4-16 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES......

3/4 4-20 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY......................

3/4 4-22 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS.............................

3/4 4-23 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM..................'................

3/4 4-26 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - WITHDRAWAL SCHEDULE.........................

3/4 4-32 3.6-1 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS............

3/4 6-5 3.6-2 CONTAINMENT ISOLATION VALVES..........................

3/4 6-21 WATERFORD - UNIT 3 XXI AMENDMENT NO. 9

INDEX LIST OF TABLES (Continued)

TABLE PAGE 3.7-1 STEAM LINE SAFETY VALVES PER L00P.....................

3/4 7-2 l

3.7-2 MAXIMUM ALLOWABLE LINEAR POWER LEVEL - HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING OPERATION WITH BOTH STEAM GENERATORS..........

3/4 7-3 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY S AMPLE AND ANALYSIS PR0 GRAM..........................

3/4 7-8 3.7-3 ULTIMATE HEAT SINK MINIMUM FAN REQUIREMENTS..........

3/4 7-14 3.7-4 FIRE HOSE STATIONS...................................

3/4 7-37 3.7-5 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT H0SE H0USES..........................................

3/4 7-40 4.8-1 DIESEL GENERATOR TEST SCHEDULE.......................

3/4 8-7 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS....................

3/4 8-11 3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES...................................

3/4 8-18 3.8-2 MOTOR-0PERATED VALVES THERMAL OVERLOAD PROTECTION AND/0R BYPASS DEVICES.....................

3/4 8-53 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS P R 0 G R AM..............................................

3 /4 11-2 4.11-2 RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS P R 0 G R AM..............................................

3 /4 11-10 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM........

3/4 12-3 3.12-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES.............................

3/4 12-9 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS.............................................

3/4 12-10 WATERFORD - UNIT 3 XXII AMENDMENT NO. 9

REACTIVITY CONTROL SYSTEMS BORON DILUTION LIMITING CONDITION FOR OPERATION 3.1.2.9 Boron concentration shall be verified consistent with SHUTDOWN MARGIN requirements of Specifications 3.1.1.1, 3.1.1.2, and 3.9.1.

Boron dilution events shall be precluded by:

i a.

Either two boron dilution alarms (startup channel high neutron flux) shall be OPERABLE with the alarms set in accordance with Specifica-tion 4.1.2.9.5 or the primary makeup water flow path to the Reactor Coolant System shall be isolated, and b.

1.

When in Mode 5 with reactor coolant loops not filled and 0.98 tK,ff> 0.96 isolate and remove power to at least two charging pumps; or 2.

When in Mode 5 with reactor coolant loops not filled and 0.96 >K,ff) 0.94 isolate and remove power to at least one charging pump; or 3.

When in Mode 5 with reactor coolant loops not filled and three charging pumps are operable, maintain K,ff <0.94; and c.

When in Mode 6, isolate and remove power to at least two charging pumps.

APPLICABILITY: MODES 3, 4, 5, and 6.

ACTION:

a.

With the boron concentration not consistent with required SHUTDOWN MARGIN, initiate emergency boration.

b.

With one boron dilution alarm inoperable and the primary makeup water flow path to the Reactor Coolant System not isolated, determine Reactor Coolant System boron concentration within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least at the monitoring frequency specified in Tables 3.1-1 through 3.1-5.

Q c.

With both boron dilution alarms inoperable and the primary makeup water flow path to the Reactor Coolant System not isolated, determine the Reactor Coolant System boron concentration by two independent means within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least at the monitoring frequency specified in Tables 3.1-1 through 3.1-5; otherwise, immediately suspend all l

operations involving positive reactivity changes or CORE ALTERATIONS (if applicable).

WATERFORD - UNIT 3 3/4 1-15 AMEN 0f1ENT NO. 9

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued) d.

With the requirements of Specifications 3.1.2.9b and 3.1.2.9c not satisfied, immediately remove power from charging pumps to comply with the above requirement or isolate the primary makeup water flow path to the Reactor Coolant System.

e.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.1.2.9.1 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 from MODE 2.

4.1.2.9.2 Each required boron dilution alarm shall be demonstrated OPERABLE by the performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at least once per 18 months.

4.1.2.9.3 The required primary makeup water flow path to the Reactor Coolant System shall be verified to be isolated by either locked closed manual valves, deactivated automatic valves secured in the isolation position, or by power being removed from all charging pumps, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.1.2.9.4 The requirements of Specification 3.1.2.9b and 3.1.2.9c shall be verified at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when in Mode 5 with the reactor coolant loops not filled or when in Mode 6.

4.1.2.9.5 Each required boron dilution alarm setpoint shall be ad' justed to less than or equal to twice (2x) the existing neutron flux (cps) at the follow-ing frequencies:

a.

At least once per 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months if the reactor has been shut down less than 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months ; b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months if the reactor has been shut down greater than or equal to 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months but less than 7 days; c.

At least once per 7 days if the reactor has been shut down greater than or equal to 7 days.

WATERFORD - UNIT 3 3/4 1-16 AMENDMENT N0. 9

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 Operating Charging 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.

1 1

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

TABLE 3.1-2 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR K,ff GREATER THAN 0.97 AND LESS THAN OR EQUAL TO 0.98 0.98 > K,ff >0.97 OPERATIONAL Number of Operating Charaina Pumps

MODE O

1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-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 2.0 hours0 days 0 hours 0 weeks 0 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 5 RCS filled 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.0 hours0 days 0 hours 0 weeks 0 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 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.

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

TABLE 3.1-3 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR K,ff GREATER THAN 0.96 AND LESS THAN OR EQUAL TO 0.97

0. 97 > K,f f >0.96 OPERATIONAL Number of Operating Charging Pumps

MODE O

1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 4

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.0 hours0 days 0 hours 0 weeks 0 months 1.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 5 RCS filled 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.0 hours0 days 0 hours 0 weeks 0 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 5 RCS partially 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 **

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.

i WATERFORD - UNIT 3 3/4 1-17b AMEN 0 MENT N0. 9

~.

TABLE 3.1-4 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR K,ff GREATER THAN 0.95 AND LESS THAN OR EQUAL TO 0.96 0.96 > K,ff >0.95 OPERATIONAL Number of Operating Charging Pumps

MODE 0

1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.0 hours0 days 0 hours 0 weeks 0 months 4

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4.0 hours0 days 0 hours 0 weeks 0 months 2.0 hours0 days 0 hours 0 weeks 0 months 1.0 hours0 days 0 hours 0 weeks 0 months 5 RCS filled 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2.0 hours0 days 0 hours 0 weeks 0 months 1.0 hours0 days 0 hours 0 weeks 0 months 5 RCS partially 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.0 hours0 days 0 hours 0 weeks 0 months Operation 1not 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.

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

TABLE 3.1-5 REOUIRED MONITORING FREQUENCIES FOR BACKUP BORON OILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR t

K,ff LESS THAN OR EQUAL TO 0.95 K,ff 10.95 OPERATIONAL Number of Operating Chargina Pumps

MODE O

1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2.0 hours0 days 0 hours 0 weeks 0 months 1.0 hours0 days 0 hours 0 weeks 0 months 4

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 5.0 hours0 days 0 hours 0 weeks 0 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 5 RCS filled 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 5.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 5 RCS partially 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.0 hours0 days 0 hours 0 weeks 0 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Operation not allowed **

drained 6

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.0 hours0 days 0 hours 0 weeks 0 months 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.

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

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:

a.

With one or more full-length CEAs inoperable due to being immovable 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 STAND 8Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , c.

With one full-length or part-length CEA misaligned from any other CEA in its group by more than 19 inches, operation in MODES 1 and 2 may continue, provided 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 requireme~nt 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 Ifmits 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 SHUTOOWN 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 .

See Special Test Exceptions 3.10.2 and 3.10.4.

g WATERFORD - UNIT 3 3/4 1-18

l REACTIVITY CONTROL SYSTEMS BASES BORATION SYSTEMS (Continued)

The contained water volume limits include allowance for water not available because of discharge line location, instrument tolerances, and other physical characteristics.

The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in M00E 6.

The lower limit on the contained water volume, the specified boron concen-tration, and the physical size (approximately 600,000 gallons) of the RWSP also ensure a pH value of between 7.0 and 11.0 for the solution recirculated within containment after a LOCA.

This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

The maximum limit on the RWSP temperature ensures that the assumptions used in the containment pressure analysis under design base accident condi-tions remain valid and avoids the possibility of containment overpressure.

The minimum limit on the RWSP temperature is required to prevent freezing and/

or boron precipitation in the RWSP.

3/4.1.2.9 BORON DILUTION This specification is provided to prevent a boron dilution event, and to prevent a loss of SHUTDOWN MARGIN should an inadvertent boron dilution event occur.

Due to boron concentration requirements for the RWSP and boric acid makeup tanks, the only possible boron dilution that would remain undetected by the operator occurs from the primary makeup water through the CVCS system.

Isolating this potential dilution path or the OPERABILITY of the startup channel high neutron flux alarms, which alert the operator with sufficient time available to take corrective action, ensures that no loss of SHUTDOWN MARGIN and unanticipated criticality occur.

g The ACTION requirements specified in the event startup channel high neutron flux alarms are inoperable provide an alternate means to detect boron dilution by monitoring the RCS boron concentration to detect any changes.

The frequen-cies specified in Tables 3.1-1 through 3.1-5 provide the operator sufficient l

l time to recognize a decrease in boron concentration and take appropriate correc-tive action without loss of SHUTDOWN MARGIN. More frequent checks are required I

with more charging pumps in operation due to the higher potential boron dilution rate.

The surveillance requirements specified provide assurance that the startup channel high neutron flux alarms remain OPERABLE and that required valve and electrical lineups remain in effect.

(

3/4.1.3 MOVABLE CONTROL ASSEMBLIES l

The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is I

WATERFORD - UNIT 3 8 3/4 1-3 AMENDMENT NO. 9 i

i 4

a REACTIVITY CONTROL SYSTEMS 1.

BASES MOVA8LE CONTROL ASSEMBLIES (Continued) maintained, and (3) the potential effects of CEA misalignments are limited to l

}

acceptable levels.

}

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the l

original design criteria are met.

The ACTION statements applicable to a stuck or untrippable CEA, to two or l

more inoperable CEAs and to a large misalignment (greater than or equal to j

19 inches) of two or more CEAs, require a prompt shutdown of the reactor since i

either of these conditions may be indicative of 1 possible loss of mechanical i

functional capability of the CEAs and in the event of a stuck or untrippable CEA, the loss of SHUTDOWN MARGIN.

i i

For small misalignments (less than 19 inches) of the CEAs, there is (1) a j

small effect on the time dependent long-term power distributions relative to those used in generating LCOs and LSSS setpoints, (2) a small effect on the a

available SHUTOOWN MARGIN, and (3) a small effect on the ejected CEA worth used in the safety analysis.

Therefore, the ACTION statement associated with small l

l misalignments of CEAs. permits a 1-hour time interval during which attempts may be made to restore the CEA to within its alignment requirements.

The

[

1-hour time limit is sufficient to (1) identify causes of a misaligned CEA, (2) take appropriate corrective action to realign the CEAs, and (3) minimize j

the effects of xenon redistribution.

The CPCs provide protection to the core in the event of a large misalignment l

l (greater than or equal to 19 inches) of a CEA by applying appropriate penalty factors to the calculation to account for the misa11gned CEA.

However, this i

misalignment would cause distortion of the core power distribution.

This distribution may, in turn, have a significant effect on (1) the available SHUTDOWN MARGIN, (2) the time-dependent long-term power distributions relative

{

to those used in generating LCOs and LS$$'setpoints, and (3) the ejected CEA worth used in the safety analysis.

Therefore, the ACTION statement associated i

with the large misalignment of a CEA requires a prompt reali.gnment of the l

misa11gned CEA.

i l

The ACTION statements applicable to misaligned or inoperable CEAs include

~

I f

requirements to align the OPERABLE CEAs in a given group with the inoperable CEA.

Conformance with these alignment requirements bring the core, within a short period of time, to a configuration consistent with that assumed in generating LC0 and LS$$ setpoints.

However, extended operation with CEAs j

significantly inserted in the core may lead to perturbations in (1) local j

burnup (2) peaking factors, and (3) available SHUT 00WN MARGIN which are more r

j adverse than the conditions assumed to exist in the safety analyses and LC0 1

and LSSS setpoints determination.

Therefore, time limits have been imposed on j

operation with inoperable CEAs to preclude such adverse conditions from developing.

i Operability of at least two CEA position indicator channels is required to determine CEA positions and thereby ensure compliance with the CEA alignment and insertion limits.

The CEA " Full In" and " Full Out" limits provide an additional independent means for determining the CEA positions when the CEAs I

j are at either their fully inserted or fully withdrawn positions.

Therefore, l

)

the ACTION statements applicable to inoperable CEA position indicators permit WATERFORD - UNIT 3 8 3/4 1-4

~

- - - - - - - -. - - -. ~.

I ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager-Nuclear shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor, or during his absence from the control room, a designated individual shall be responsible for the control room command function.

A management directive to this effect, signed by the Vice President -

Nuclear Operations, shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown in Figure 6.2-1.

UNIT STAFF 6.2.2 The unit organization shall be as shown in Figure 6.2-2 and:

a.

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; b.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

In addition, while the reactor is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room.

c.

A Health Physics Technician

shall be on site when fuel is in the reactor; d.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

e.

A site fire brigade of at least five members shall be maintained on site at all times.* The fire brigade shall not include the Shift Supervisor the Shift Technical Advisor, nor the two other members oftheminImumshiftcrewnecessaryforsafeshutdownoftheunit and any personnel required for other essential functions during a fire emergency.

The Health Physics Technician and fire brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

WATERFORD - UNIT 3 6-1 AMENDMENT NO. 9

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) f.

Administrative procedures shall be developed and implemented to limit the working hours of individuals of the nuclear power plant operating staff who are responsible for manipulating plant controls or for adjusting on-line systems and equipment affecting plant safety which would have an immediate impact on public health and safety.

Adequate shift coverage shall be maintained without routine heavy use of overtime.

The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, the following guidelines shall be followed:

1.

An individual shall not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

2.

An individual shall not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding shift turnover time.

3.

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shall be allowed between work periods, including shift turnover time.

4.

Except during extended shutdown periods, the use of overtime shall be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Plant Manager, the assistant Plant Managers, the Operations Superintendent - Nuclear or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

Controls shall be included in the procedures such that individual overtime will be reviewed monthly by the Station Manager or his designee to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

I l

WATERFORD - UNIT 3 6-2

ML20207H558

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