ML20206G614

Amend 55 to License DPR-45,changing Tech Specs to Add New Reporting Requirements of 10CFR50.73 & Details to Requirements of Repts Required for Diesel Generator Failures

ML20206G614
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	04/08/1987
From:	Grotenhuis M Office of Nuclear Reactor Regulation
To:
Shared Package
ML20206G548	List: ML20206G544 ML20206G614 ML20206G642
References
NUDOCS 8704150062
Download: ML20206G614 (25)

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/ o,, UNITED STATES

!T NUCLEAR REGULATORY COMMISSION

g([yj ;p, WASHINGTON. D. C. 20555 Q...../

DAIRYLAND POWER COOPERATIVE DOCKET NO. 50-409 LA CROSSE BOILING WATER REACTOR AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 55 License No. DPR-45

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

A. The application for amendment by Dairyland Power Cooperative (the licensee) dated March 20, 1984, as modified by letter dated August 24, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, the license is amended by changes to the Technical Specifications es indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Provisional Operating License No.- DPR-45 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A issued October 31, 1969, with Authorization No. DPRA-6, as revised through Amendment No.55 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THF NUCLEAR REGULATORY COWTSSION

~/fu.:4.u'( & %cda<

Marrhall Grotenhuis, Acting Director BWR Project Directorate #1 Division of BWR Licensing

Attachment:

Chances to the Technical Specifications  !

Date of issuance: April 8,1987

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ATTACHFENT TO LICENSE AMENDMENT NO 55 PROVISIONAL OPERATING LICENSE NO. DPR-45 DOCKET NO. 50-409 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 11 11 27h 27h 32all) 32a(1) 32b 32b 32k(2) 32k(2)-

37a 37a 37c 37c 379 379 371 371

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37.i(2) 37jf2) 37m 37m 37n 37n 6-6 6-6 6-9 6-9 6-11 6-11 6-12a 6-12a 6-la 6-14 6-15 6-15*

6-16 6-16 6-16a 6-17*

6-17 6-18*

6-18 6-19*

6-20 --

• Pagination change only .

TABLE OF CONTENTS (Cont'd)

Page 6.0 ADMINISTRATIVE CONTROLS . . . . . . . . . . . . . . . . . . . . . 6-0 6.1 RESPONSIBI LI TY . . . . . . . . . . . . . . . . . . . . . . . 6-0 6.2 ORGANIZATION . . . . . . . . . . . . . . . . . . . . . . . . 6-0 6.3 UNIT STAFF QUALIFICATIONS. . . . . . . . . . . . . . . . . . 6-5 6.4 TRAINING . . . . . . . . . . . . . . . . . . . . . . . . . . 6-5 6.5 REVI EW AND AUDIT . . . . . . . . . . . . . . . . . . . . . . 6-5 6.6 REPORTABLE EVENT ACTION. . . . . . . . . . . . . . . . . . . 6-11

] 6.7 SAFETY LIMIT VIOLATION . . . . . . . . . . . . . . . . . . . 6-11 6.8 PROCEDURES . . . . . . . . . . . . . . . . . . . . . . . . . 6-11

6.9 REPORTING REQUIREMENTS . . . . . . . . . . . . . . . . . . . 6-12a 6.10 RECORD RETENTION . . . . . . . . . . . . . . . . . . . . . . 6-16 i

6-11 RADIATION PROTECTION PROGRAM . . . . . . . . . . . . . . . . 6-17 6-12 HIGH RADIATION AREA . . . . . . . . . . . . . . . . . . . . 6-17 l 6-13 ENVIRONMENTAL QUALIFICATION. . . . . . . . . . . . . . . . . 6-18 6-14 POST-ACCIDENT SAMPLING PROGRAM . . . . . . . . . . . . . . . 6-19 i

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4 ii Amendment No. 23, 36, 55 l

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4.0 OPERATING LIMITATIONS 4.0.1 DEFINITIONS - (Cont'd)

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{ PARTIAL SCRAM i

A PARTIAL SCRAM signal shall cause the electric and hydraulic scram motors for

13 preselected control rod drive mechanisms to be actuated for control rod

] insertion.. Full insertion of PARTIAL SCRAM control rods during POWER t

OPERATION shall render the reactor suberitical.

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental j nuclear characteristics of the reactor core and related instrumentation and (1) described in Chapter 13 of the Safeguards Report, (2) authorized under the l provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission. <

j PRESSURE BOUNDARY LEAK &CE PRESSURE BOUNDARY LEAKAGE shall be leakage through a non-isolable fault in a j Reactor Coolant System component body, pipe wall or vessel vall. i j

l PROCESS CONTROL PROGRAM (PCP)

The PROCESS CONTROL PROGRAM shall contain the current formula, sampling,

analyses, tests, and determinations to be made to ensure that the processing 3 and packaging of solid radioactive wastes based on demonstrated processing

[ of actual or simulated solid wastes will be accomplished in such a way as 4 to assure compliance with 10 CFR Part 20, 10 CFR Part 71 and Federal and State regulations and other requirements governing the disposal of the radioactive 1 waste.

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RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant and reactor components of 165 MWt.

4 REPORTABLE EVENT A REPORTABLE EVENT shall be any of thosa conditions specified in Section 50.73 to 2

10 CFR Part 50. A Licensee Event Renort shall be submitted for REPORTABLE EVENTS.

RESTRICTED AREA

, A RESTRICTED AREA shall be any area within the exclusion boundary, access to which is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials. See Figure 4/5.3.

SHUTDOWN MARGIN SHUTDOWN MARGIN'shall be the amount of reactivity by which the reactor is l suberitical or would be suberitical from its present condition assuming all 4

control rods are fully inserted, except for the single control rod of highest reactivity worth which is assumed to be fully withdrawn, and the reactor is in

i. the shutdown condition, cold, i.e. f,80*F, and Xenon-free.

27h Amendment NO. - 25, 36, 55

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REACTO'R COOLANT SYSTEM LIMITING CONDIT[ON FOR OPERATION - (cont'd)

. 1 APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3 and 4. '

ACTION:

a. -In OPERATIONAL CONDITION 1, 2 or 3, with the activity of the reactor coolant:

1. > 0.2 pCi/ gram DOSE EQUIVALENT I-131 but i 4.0

)' pCi/ gram, entry to OPERATIONAL CONDITION 1, 2, 3 or 4 is permitted and operation may continue for up to 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />'s provided that operation under thesp conditions shall not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive 12-month period. Should the total operating time at a primary coolant specific activity > 0.2 pCi/ gram DOSE EQUIVALENT I-131 exceed 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in'any consecutive six-month period, the licensee shall report the_ number of hours of operation above this limit to the NRC within 30 days.

2. > 0.2 pCi/ gram DOSE EQUIVALENT I-131 for mor.e than 48 i

hours during one continuous time interval or > 4.0 pCi/ gram be'in at least HOT SHUTDOWN with the main j -

steam line isolation valve closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3. >

LOO /E pCi/ gram or > 5.0 x 10-6 pCi/ gram gross alpha activity, be in at least HOT SHUTDOWN with the main steam line isolation valve closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and

, in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i Amendment No. 19,.28, 55 32a(1) -

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REACTOR COOLANT SYSTEM . ,

LIMITING CONDITIO'N FOR OPERATION - (cont'd)

ACTION: (cont'd)

b. In OPERATIONAL CONDITION 1, with off-gas activity:

1. > 750 Ci/ day (P/P F ) +AT (1-0.018t) (P/Pp) but < 1000 Ci/ day (P/Pp) +AT (1-0.018t) (P/Pp). POWER OPERATION may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that opera-tion under these conditions shall not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive 12-month period. Should the total operating time at an'off-gas activity > 750 Ci/ day P/Pp + AT (1-0.018t) (P/P F) exceed 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in any consecutive six-month period, the licensee shall report the number of hours of operation above this limit to the NRC within 30 days.

2. > 750 Ci/ day (P/Pp) +AT (1-0.018t) (P/P F) for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or

> 1000 Ci/ day be in at least HOT SHUTDOWN with the main steam line. isolation valve closed within_12_ hours and in COLD SHUTDOWN within tne next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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c. With the reactor required to be shut down as a result of .

ACTION a.3 or b.2 above. obtain Commission approv.a1 prior to increasing reactor coolant system temperature above 212'F.

d. In OPERATIONAL CONDITION 1, with THERMAL POWER increased.

by more than 25% of RATED THERMAL POWER since th'e last performance of Table 4.2.2.22-1, Item 4, perform Table 4 . 2.' 2. 2 2-1, Items Ic and 4c.

e. In OPERATIONAL CONDITION 1 or 2, with off-gas activity increased by more than 1000 pCi/sec within one hour,

_ perform Table'4.2.2.22-1, Item Ic and-ic. Off-gas activity values'shall be norEalize'd" for corre'lation with previous cyples due to changes in monitoring, sampling

. and/or ana2fsis methods.

f. In OPERATIONAL CONDITION 1, 2, 3 or 4 with the activity of the primary coolant > 0.2 pCi/ gram DOSE EQUIVALENT I-131, or > 100/E pCi/ gram, or > 5.0 x 10-6 pCi/ gram gross alpha activity, or with the off-gas activity > 750 Ci/ day (P/Pp)

+AT(1-0.018t) (P/Pp), perform the sampling and analysis requirements.of Items,lb, ,.b,and 4 ,6b of Table 4.2.2.22-1.

A Licensee Event Report shall be prepared and submitted to

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.the Commission, if the activity is indicative of fuel cladding failure. This determination will be based on ad'ditional sample 'issialt's";ittfEf previous, concurrent and subsequent activity levels; operating experience; and/or recent or ongoing plant evolutions. This report shall contain the results of the activity analyses and the time duration when the activity exceeded each limit together with the following additional information.

- 32b - Amendment No. JJ, Jg,55

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' ELECTRICAL POWER SYSTEMS SURVEILL'ANCE REQUIREMENTS - (cont'd) 5.2.10.1.4 Reports - All diesel generator failures, valid or non-valid, shall be reported to the Commission pursuant to Specification 6.9.2. If the number of failures in the last 100 l valid tests, on a per nuclear unit basis, is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position c.3.b of Regulatory Guide 1.108, Revision 1, August 1977.

32k(2) - Amendment No. 55

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' INSTR'UMENTATION 4/S.2.17 FIRE DETECTION INSTRUMENTATION -

LIMITING CONDITION'FOR OPERATION 4.2.17.1 As a minimum, the fire detection instrumentation for each fire detection zon,e shown in Table 4.2.17 shall be OPERABLE.

APPLICABILITY: Whenev.er equipment in that fire detection zone is required to OPERABLE.

ACTION: '

With one or more of the fire detetion instrument (s) shown in Table 4.2.17 inoperable:

a. 'Within I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instruments:

. at least once per four hours in the reactor

-cont,ainment building and High Radiation areas;

. at least once per hour in any other area.

b. Restore the'inoperhble' instrument (s) to OPERABLE status within 14 days or, in lieu of a Licensee Event. Report,  ;

prepare and submit a Special Report to the Commission pursuant to Specificatio'n 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.

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SURVEILLANCE REOUIREMENTS 5.2.17.1.1 Each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.

5.2.17.1.2 The supervised circuits associated with the detector alarus of each of-the above , required fire.. detection instruments shall be demonstrated OPERABLE at least once per 6 months.

- 37a - Amendment No. 10,55

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• 1 PLANT SYSTEMS' I 4/5.2.18 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER S'YSTEM LIMITING CONDITION FOR O'PERATION 1

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4.2.18.1 The fire suppression water system shall be OPERABLE with:

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a. Two high pressure diese'l driven pumps, each with a capacity of 750 gal / min. with their discharge aligned to the fire suppression header.

b. An OPERABLE flow' path capable of taking suction from the Mississippi River and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves and the first valve ahead of the water flow alarm device on each sprinkler, hose standpipe or spray system riser required .tx) be OPERABLE per Specification 4.2.18.2. l APPLICABILITY: At all times. '

ACTION: .

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a. With one pump inoperable, restore the inoperab),e. equipment to OPERABLE status within 7 days or, in lieu'of a Licensae l Event Report, prepare and submit a Special Report to the l Commission pursuant to Specification 6.9.2 within the next l 30 days outlining the plans and procedures to be used to l provide for the loss of redundancy in this system.

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b._ With the fire , suppression water sys' ten-otherwise .

inoperable:  ;

1. Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and 1

2. Submit a Special Report in accordance with Specification 6.9.2: l l

a) By telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b) Confirmed by telegraph, mailgram or facsimile transmission JK) later than the first working day I following the event, and

- 37c - Amendment No. '10,55 m, _ . _ _ _ - . . . . _ _ _ --- --

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. PLANT ~ SYSTEMS '

SPRAY AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION

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4.2.18.2 The following spray and/or sprinkler systems shall be OPERABLE:

a. The turbine lube oil res~ervoir.

b. The turbine lube oil storage room.

c. The ACS valve area.

d. The main and auxiliary transformers,

e. lA diesel generator room.

f. Electrical Penetration area.

APPLICABILITY: Whenever equipment in the spray / sprinkler protected areas is required to be OPERABLE. ~

ACTION:

a. With the above required spray and/or sprinkler system inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected area (s) '

within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the system to OPERABLE status within 14 days or,-in lieu of a Licensee Event Report, prepare and submit a Special. Report to the Commission pursuant to Specification 6.9.2 within the next-30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status. .

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

StIRVEILLANCE REQUIREMENTS 5.2.18.2 The above required spray and/or sprinkler system shall be demonstrated OPERABLE:

a. At least once oar 12 months by cycling each testable valve in tha flow path through at least one complete cycle of full travel.

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b. At least once per 18 months:-

1. By performing,a system _ functional test which includes simulated autbihatic'EctMtibn of the system, and:

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a) verifying that the automatic valves in the flow path-actuate to their correct positions, and 379 - Amendment No. J0, # ,55

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PLANT' SYSTEMS' CHEMICAL EXTINGUISHING LIMITING CON 6ITIONS FOR OPERATION 4.2.18.3 The chemical extinguishing systems located in the following areas shall be OPERABLE:

a. 1B Emergency Di'esel Generator, with a minimum of 4 high pressure CO2 bottles weighing at least 190 pounds each,

b. Electrical equipment room, with a minimum of 1 Halon 1301 bottle weighing at least 270 pounds.

APPLICABILITY: Whenever equipment in the chemical extinguishing protected areas is required to be OPERABLE.

ACTION:

a. With either of the above required chemical extiriguishing systems inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected areas"within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the system to OPERABLE status within 14 days or, in lieu of a Licensee Event Report, prepare and submit a Spe'cial Report to.the Commission pursuant to~ Specification 6.9.2 within the next 30 days

. outlining the action taken, the cause of the inoperabi-lity and the plans and schedule for restoring the system to OPERABLE status.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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SURVEILLANCE REOUIREMENTS 5.2.18.3 Each of the above required chemical extinguishing systems shall be demonstrated OPERABLE:

a. At least once.per 6 months by verifying tank weigh *. of each of the required bottles, and pressure of Halon bottle,

b. At -least once per;18.. months. by:

1. Verifying each system, including associated ventilation dampers, actuates manually and

, automatically with the solenoid valve removed from the respective bottles, upon receipt of a simulated

, test signal, and

2. Performance of a flow test through headers and nozzles to assure no blockage.

- 371 - Amendment No. W,55

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PLAlff ' SYSTEMS 4

YARD FIRE 'HYDRAkfrS AND OUTSIDE HOSE HOUSES u

LIMITING COND'ITION YOR OPERATION 4.2.18.5 shall be OPERABLE. The five yard fire hydrants and four outside hose houses

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APPLICABILITY: Whenever equipment in the areas protected by the yard fire hydrants is required'to be OPERABLE.-

ACTION:

a.

With one or more of the yard fire hydrants oi~'outside hose

' houses inoperable, route sufficient additional lengths of 2-1/2 inch diameter hose located in an adjacent OPERABLE hydrant hose house to provide service to the unprotected area (s) within one hour if the inoperable fire hydrant or 1

[ associated hydrant hose house is the primary means of fire suppression; otherwise, route an additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> . , Restore the inoperable hydrant (s) and/or hose houses (s) to OPERABLE atatus within 14 days or, in lieu.

of a Licensee Event Report, prepare and submit a Special i

Report to the Commission' pursuant to Specification 6.9.2 within the next '30 da'ys outlining the action taken, the

] cause of the inoperability and the plans and schedule iPor i

restoring the system to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

! SURVEILLANCE REQUIREMENTS .-

5.2.18.5 Each of the yard fire hydrants and outside hose houses shall be demonstrated OPERABLE

a.

l At least once per 31 days by visual inspection of the outside hose house to assure all required equipment is at

,, the hose house.

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At least once per 6 months, during March, April or May and during September, .. October or November, by visually inspecting each yard fire hydrant and verifying that the hydrant barrel is dry.and that the hydrant is not dan ged.

c. At least once per.1R. months byt

1. . Conducting a hose hydrostatic test at a pressure at  ;

least 50 psig greater than the maximum pressure available at any yard fire hydrant.

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2. Replacement of all degraded gaskets in couplings.

- 37j(2) - Amendment No. M, 55 m- __ . - - _ _ _ . . . . . . _ . . . _ _ _ . . _ _ . . _

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, PIANT S'YSTEMS BASES --(cont'd) l

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4/5.2.l8 FIRE SUPPRESION SYSTEMS I

The OPERABILITY of the fire suppression systems ensures that i

adequate fire suppressiort capability is available to confine and extinguish fires occurring in any . portion of the facility where safety related equipment.is loca.ted. The fire suppression system j' consists of the water system, spray and/or sprinklers, CO 2, Halon, and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage to

- safety related equipment and is a major element in the. facility fire protection program. '

inoperable, In the event that portions of the fire suppression systems are alternate backup fire fighting equipment is required

! to be made available in the affected areas until the inoperable equipment is restored to service. - -

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' In the event,the fire suppression water system becomes in-operable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.

The requirement for a report to the Commission provides l for evaluation of the acceptability of the corrective measures to I provide adequate fire suppression capability for the continued j protection of the nuclear plant. ,

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4/5.2.19 PENETRATION FIRE BARRIERS

. l The functional integrity of.the penetration fire barriers l ensures that the fires.will be confined or ade_quately retarded .l i

from spreading to adjacent portions of the facility. -This. design feature minimizes the possibility of a single fir,e rapidly involving extinguishment.

several areas of the facility prior to detection and The penetration fire barriers are a passive element periodic inspections.

in the facility fire protiection program and are subject to I,

During periods of time when the barriers are not functional, ^

and fire detection instrumentation in safety related areas on i

f either side is not functional, a continuous fire watch is required to,be maintained in-the vicinity of the-affec.ted barrier until the, barrier is restored to functional status.

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- Amendment No. N, #, 55

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PLANT' SYSTEMS i .

4/5.2.21 EMERGENCY SERVICE WATER SUPPLY SYSTEM

[ LIMITING CONDITION FOR OPERATION i 4.2.21.1 The Emergency Service Water Supply System shall be OPERABLE, with:

a.

4 At least three.pertable gasoline engine-driven pumps which  !

can be connected in parallel and are capable of delivering I a combined f-low of 900 gym against a pressure of 50 psig i

within the reactor vessel.

j b. An operable flow path from the Mississippi River, consist-i i

ing of pump suction and discharge hoses, a three-way ball I valve distributor, and relay hoses capable of' transferring water to a valved inlet manifold into the High Pressure Service Water' piping system.

APPLICABILITY: Operational Conditions 1, 2 and 3

• ACTION:

a. With only 2 pumps OPERABLE, restore the inoperable I equipment to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i b.

With the ESWSS otherwise not OPERABLE:

1. Verify OPERABLE status of the High Pressure Service

. Water Fire Suppression Water System per Sections i

5.2.18.1.1.a and 5.2.18.1.2.a within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. -

2.

Restore the ESWSS to. OPERABLE status with at least three pumps within seven (7) days-or be in at least j

i HOT SHUTDOWN within the'next twelve (12)' hours'and in <

COLD SHUTDOWN within the following tyenty-four (24) hours, l j 3. Submit a Licensee Event neport. I 1

I 4. If 1. above'cannot be satisfied, place the reactor in at least ROT SHUTDOWN within the next twelve (12)

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hours and in COLD SHUTDOWN within the following

! twenty-fo,ur (24) hours.

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- 37n - Amendment No. E , 55 i

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ADMINISTRATIVE CONTROLS-MEETING FREQUENCY

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6.5.1.4 The ORC shal1 meet at least once per calendar month and as convened by the ORC Chairman or his designated alternate.

OUORUM 6.5.1.5 The minimum quorum of the ORC necessary for the per-formance of the ORC responsibility and authority provisions of the Technical Specifications shall consist of the Chairman, or his designated alternate, and four members, inc'ludin'g alternates.

. RESPONSIBILITIES 6.5.1.6 The Operations Review Committee shall be responsible for:

a. Review of (1) all procedures required by Specification 6.8 and changes thereto, (2) any other proposed pro-cedures or changes thereto as determined by the Plant Superintendent to affect nuclear safety.

b. Review of all proposed tests and experiments that affect nuclear safety.

c. Review of all proposed' changes to the Appendix "A" T.echnical Specifications.

d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.

e. Investigation of all violations of the Technical Specifi-cations including the p, reparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Assistant General-Manager-Power Group and to the Safety Review Committee (SRC).

f. Review of all REPORTABLE EVENTS. l

g. Review of unit ~ operations to detect potential nuclear safety hazards.

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Plant Sup5rintendent dr-SRC.

i. Review of the Contingency Plan, the Plant Security Plan, and imple-menting procedures and shall submit recommended changes to the SRC.

j. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the SRC.

6-6 Amendment No. 34, 36, 55

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', ADMINI'ST_RATIVE ' CONTROLS i

REVIEW - (cont'd) ,

c; Proposed tests or experiments which involve an unreviewed ,

safety question as defined in Section 50.59, 10 CFR.

d. Proposed change,s to Appendix "A" Technical Specifications or this Operating License.

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! e.

' Violations of codes, regulations,-orders, Technical specifications, license requirebents, or of internal pro-  ;

cedures or instructions having nuclear safety significance.

1 4

f.

Significant operating abnormalities or deviations from

~

normal and expected performance of unit aquipment that affect nuclear safety.

g. All REPORTABLE EVENTS.

1

h. i All recognized in'dications of an unanticipated deficiency in- som,e aspect of design or operation of safety related s tructures, systems, or components that could affect

• nuclear safety. -

1. Reports and meeting minutes of the Operations Review Committee.

AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the.SRC. These audits shall encompass:

a.

The conformance of unit operation to provisions contained i

within the Appendix "A" Technical Specifications and applicable license conditions at least once per 12 months.

i b.

The performance, training and qualifications of the I entire unit staff at least once per 12 months. i c.

The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or i

method of operation that affect nuclear safety at least once per 6 months.

2 i d.

' The performance of activities required by the Operational 1 Quality Assurance. Repgram to meat the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.

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e.

The Emergency Plan and implementing procedures at least j once per 12 months.

4 t 6-9 Amendment No. 23, 32, 55 I

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{. ADMINISTRATIVE CONTROLS-6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall 1be reviewed by the ORC and submitted to the SRC and the Assistant General Manager-Power Group.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The unit shall be placed in at least HOT SHUTDOWN within two hours,

b. The,NRC Operations Center shall be notified as soon as possible and in all cases within one hour. The Assistant General Manager-Power Group and the SRC shall be notifie'd within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. A. Safety Limit Violation Report shall be prepared. The report shall be reviewed by the ORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems or structures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the Commission, the SRC and the Assistant General '

Manager-Power Group within 14 days of the violation. i 6.8 PROCEDURES l

6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of t

Regulatory Guide 1.33, Revision 2, February 1978.

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

l 6-11 Amendment No. 3, 23,55 l

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ADMINISTRATIVE CONTROLS f

[. 6.8.4.2 0FFSITE DOSE CALCULATION MANUAL (ODCM)

(

The ODCM shall be maintsined bv the lice see. Changst to the 0D0.1 w121 oe outlined in the semi-annual report 6.9.3.a.

This submittal shall contain:

1. Detailed information to support the rationale for the change.

Information submitted should consist.of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s) and

2. A determination that the change will not reduce the accuracy of reliability of dose calculations or setpoint determinations.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performanceHof the unit.

6-12a Amendment NO. 36, 55

ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT i

6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Docume it Control Desk, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office, to arrive no later than the 15th of each j month following the calendar month covered by the report.

l SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regi.onal Administrator of the

Regional Office of the NRC within the time period specified for each report.

6.9.3 Unique Reporting Requirements

a. Semi' Annual Radioactive Effluent Release Report Paragraph (a)(2) of Part 50.36a, " Technical Specifications on Effluents from Nuclear Power Reactors," of 10 CFR Part 50 cequires that a report be made to the Commission within 60 days after January 1 and July 1 of each year. The report shall specify the quantity of each of the principal radionuclides released to unrestricted areas by liquids and gaseous effluents during the previous 6 months of operation. The information submitted shall be in accordance with Appendix B of Regulatory Guide 1.21 (Revision 1) dated June 1974 with data summarized on at least a quarterly basis.

, An annual summary of [ hourly] meteorological data collected over the previous year in accordance with Regulatory Guide 1.21 (Rev. 1) will be included with the semi-annual radioactive ef fluent release report, which is submitted 60 days after January 1 of each" year. This same report shall include an assessment of ra'diation doses to MEMBERS OF THE PUBLIC from radioactive liquid and gaseous effluents released beyond the EFFLUENT RELEASE BOUNDARY performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). This report will contain any changes made to the ODCM during the previous twelve months.

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6-14 A:.endmentNo. 23, 36, 55 l l

ADMINISTRATIVE CONTROLS 6.9.3 Unique Reporting Requirements (continued)

b. Annual Radiological Environmental Monitoring Report Routine radiological environmental monitoring reports during the previous calendar year shall be submitted within 60 days after January 1 as part of the Annual Radioactive Effluent Release Report.

The annual radiological environmental monitoring reports shall include summarized and tabulated results, including interpretations and analysis of data trends, of environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from the plant, the results of the Interlaboratory Comparison Program, and a discussion of all analyses in which the LLD was not achievable.

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6-15 Amendment No. 36, 55

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,o, ssa3a aa2as asa a 3as3ar3333a33333sst23s3333ssa3as2aas3a33333saa3ma3333312 4 6.10 RECORD RETENTION 1

In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least five years:

a. Records and logs of facility operation covering time interval at each power level.

! b. Records and logs of principal maintenance activities, inspections, i repair and replacement of principal items of equipment related to nuclear safety.

c. All REPORTABLE EVENTS submitted to the Commission.

d. Records of surveillance activities, inspections and calibrations 3

required by these Technical Specifications.

s

e. Records of changes made to the procedures required by Specification

, 6.8.1.

f. Records of radioactive shipments.

f

g. Records of sealed source and fission detector leak tests and results.

1

h. Records of annual physical inventory of all sealed source material

] of record.

i 6.10.2 The following records shall be retained for the duration of CNe LACBWR

Operating License

) a. Records and drawing changes reflecting facility design modifications

made to systems and equipment described in the Safeguards Report for j Operating Authorization.

b. Records of new and irradiated fuel inventory, fuel transfers and j assembly burnup histories.

c. Records of radiation exposure for all individuals entering radiation control areas.

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d. Records of gaseous and liquid radioactive material released to the

. environs, and records of analyses required by the Radiological

! Environmental Monitoring Program.

6-16 Amendment No. 23, 36, 55 l

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ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued)

e. Records of transient or operational cycles for those facility components identified in Table 5.7.1-1.

f. Records of reactor tests and experiments.

g. Records of training and qualification for current members of the unit staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications.

i. Records of Quality Assurance activities required by the Operational Quality Assurance Manual,

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the. ORC and the SRC.

1. Records of environmental qualification which are covered under the Provisions of Section 6.13.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent witn the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203 (c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mRe=/hr but less than 1000 cRem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Special WorkPermit (SWP).* Any individual or group of individuals permitted to enter such areas shall be provided with one or more of the following:

• Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the SWP issuance requirement during the performance of their assigned radiation protection duties, provided they are.follovi.ng plant' radiation protection procedures for entry into high radiation areas.

6-17 Amendment No. 23, 29, 55

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~ ADMINISTRATIVE CONTROLS

IGH RADIATION AREA (Continued)

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area. ,

! b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated

) dose is received. Entry into such areas with this monitoring device i may be made after.the dose rate levels in the area have been estab-

! lished and personnel have been made knowledgeable of them.

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c. 'A health physics qualified individual (i.e. , qualified in radiation l protection procedures) with a radiation dose rate monitoring de-i vice and who is responsible for providing positive exposure con-trol over the activities within the area and who will perform periodic radiation surveilance at the frequency which will be estab-3 lished by the Health and Safety Supervisor.

6.12.2 For each area with radiation levels greater than 1000 mrems/hr the co6trols of 6.12.1 shall be implemented and (1) Each entrance or access point to the area shall be maintained

- locked except during periods when access to the area is required, with positive control over each individual entry, or ,

(2) Each entrance or access point to the area shall be equipped with a control device which shall energize a conspicuous visible or audible alarm signal in such a manner that the -

l i individual entering the high radiation area and the licensee or a supervisor of the activity are made aware of the entry.

1 i 6.13 ENVIRONMENTAL QUALIFICATION

• A. By no later than June 30, 1982, all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of:

Division of Operating Reactors " Guidelines for Evaluating Environmental-Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR) Guidelines"; or, NUREG-0588, " Interim Staff Position on Environ-mental Qualification of Safety-Related Electrical Equipment", December t

1979. Copies of these documents are attached to order for Modification 1 of License DPR-45 dated October 24, 1980.

'l B. By no later than Dccember 1,1980, complete and auditable records must be available and maintained at a central location- which describe the j environmental qualification method used for all safety-related j electrical equipment in sufficient detail to document the degree of compliance with the DOR guidelines or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested,'or otherwise further qualified.

1 6-18 Amendment No. 23, 29, 55 l

*NRC Order dated 10/24/80 e

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6.14 post Accident Sampling program A post accident sampling program shall be defined in the plant procedures which will ensure the capability to obtain and analyze samples of:

reactor primary coolant containment building atmosphere stack effluent The program shall include:

personnel training procedures for sampling and analysis provisions for maintenance of equipment J

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6-19 Amendment No. 31, 55

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