ML20092C059

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Amend 86 to License DPR-46,ensuring Compliance W/New Regulations Re LER Reporting Sys
ML20092C059
Person / Time
Site: Cooper Entergy icon.png
Issue date: 06/01/1984
From: Vassallo D
Office of Nuclear Reactor Regulation
To:
Nebraska Public Power District (NPPD)
Shared Package
ML20092C060 List:
References
DPR-46-A-086, TAC 54247 NUDOCS 8406200552
Download: ML20092C059 (14)


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k UNITED STATES L

NUCLEAR REGULATORY COMMISSION

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'j WASHING TON, D. C. 20553

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NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298-i COOPER NUCLEAR STATION i

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 License No. DPR-46 1.

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

L A.

The application for amendment'by Nebraska Public Power District dated February 14, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the j

Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; 4-1 B.

The facility will operate in confonnity with the application, the i

provisians of the Act, and the rules and regulations of the Ccmission; C.

There is reasonable assurance (i) that the activities authorized 1

1 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; 1

D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; i

and E.

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

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

2.

Accordingly, the licensee is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility Operating License.No. DPR-46 is hereby amended'to read as follows:

~

t (2). Technical Specification j

The' Technical Specifications, contained in Appendices A~and B, as, j

revised through Amendment No. 86, are hereby incorporated in the:

1 license. The licensee shall operate the facility in accordance with the Technical Specifications.

1 8406200552 840601 PDR ADOCK 05000298 P,

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3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

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Domenic B. Vass llo, Chief Operating. Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 1, 1984 1

1

A TACHMENT TO LICENSE AMENDPENT NO. 86 FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 Revise the Appendix A Technical Specifications as follows. The revised areas are indicated by marginal lines.

Remove Insert iv iv 216b 216b 216c 216c 216f 216f 216g 216g 4

2161 216i 221 221 224 224 228 228 231 231 232 232 Intentionally left blank 233 233 Intentionally left-blank 234 234 Intentionally left blank

TABLE OF CONTENTS (Cont'd.)'

s s

P, nee No.

SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REOUIREMENTS 6.2.1.3 NPPD Safety Review and' Audit Board (SRAB) 222 B.1 Membership 223 B.2 Meeting Frequency 223 B.3 Quorum 223 B.4 Review 223 B.5 Authority 224 B.6 Records 225 B.7 Audits 225 c

225 6.3 Procedures and Programs 6.3.1 Introduction

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226 6.3.2 Procedures 226 6.3.3 Maintenance and Test Procedures 226 6.3.4 Radiation Control Procedures 226

.A High Radiation Areas 226a 6.3.5 Temporary Changes 226a 6.3.6 Exercise of Procedures 226a 6.3.7 Programs 226a

.A Systems Integrity Monitoring Progran 226a

.B Iodine Monitoring Program 226a

.C Environmental Qualification Program 226a 6.4 Record Retention 228 6.4.1 5 year retention 228 6.4.2 Life retention 228 6.4.3 2 year retention 229 6.5 Station Reporting Requirements 230 6.5.1 Routine Reports 230

.A Introduction 230

.3 Starrup Report 230

.C Annual Reports 230-

.D Monthly Operating Report 231 6.5.2 Reportable Events 231 l

6.5.3 Unique Reporting Requirements 235 6.6 Station Operating Records 228 6.6.1 (5 year retention) 228 6.6.2 (life retention) 228 6.6.3 (2 year retention) 229 Amen:cen-he.,d,,3I,35,86

-iv-

A LIMITING. CONDITIONS FOR OFERATION ISUR7EILLANCE REQU2REMENTS

- 3.14 FIRE DETECTION SYSTEM 4.14 FIRE DETECTION SYSTEM i

APPLICABILITY APPLICABILITY Applies to the operational status of the Applies to the operational status of the Fire Detection System.

Fire Detection System.

OBJECTIVE.

To assure continuous automatic surveillance throughout the Main Plant.

SPECIFICATIONS SPECIFICATIONS

- A.

The Fire Detection System instumen-A.

Each detector on Table 3.14 shall be demonstrated operable every 6 months tation fot each fire detection zone shown in Table 3.14 shall be operable.

by performance of a channel functional cest.

B.

With one or more of the fire detection B.

The NFPA Code 72.D Class 3 supervised instrument (s) shown in Table 3.14 circuits supervision associated with inoperable:

the detector alarms of each of the above required fire detection

1. Within I hour establish a fire instruments shall be demonstrated a

watch patrol te inspect the OPERABLE at least once per 6 months.

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=ene(s) with the inoperable instru-ment (s) at least once per hour, and

2. Restore the inoperable instgument(s) to OPERABLE status within 14 days or prepare and submit a Special l

Report to the Commission within the next 30 days outlining the action taken, the cause of the inoperability I

and the plans and schedule for re-storing the instrument (s) to OPERA 3LE status.

}

i 3.15 FIRE SUPPRESSION WATER SYSTEM 4.15 FIRE SUPPRESSION WATER SYSTEM APPLICABILITY APPLICABILITY Applies to the availability of water for fire fighting purposes.

applies to the availability of water for fire fighting purposes.

OBJECTIVE To assure a continuous operable water supply for fire fighting syste'ms from 2 fire pumps.

/cendment flo.

, 86

-216b-

e

?.IMITING C0N'DITIONS FOR OPERATION

'SURVEIf. LANCE REQUfREMENTS

3. S (cont'd) 4.15 (cont'd)

SPECIFICATIONS SPECIFICATIONS A.

The' fire suppression water system shall A.. The Fire Suppression Water Supply be OPERABLE with:

System shall be demonstrated operable:

1.

Two fire pumps, each with a capacity 1.

At least once per 31 days by of at least 2000 gym, with their starting each pump on a stag-discharge aligned to the fire gered start-up basis and operating suppression header, it for:

2.

An OPERABLE flow path capable of a)

A minimum of 15 minutes taking suction from either of two for a diesel engine-driven 500,000 gallon water storage tanks fire pump, and or the Missouri River and transferring the water through b)

~A minimum of 7 minutes for distribdtion piping with OPERABLE an electrical motor-driven sectionalizing control or isola ~ tion fire pump.

valves to the yard hydrant valves and the front valve ahead of the 1.

At least once per 31 days by water flow alarm device on each verifying that.each valve sprinkler, hose standpipe or spray (manual, power operated or system riser.

automatic) in the flow path 4

l that is not locked, sealed or 9.

If the requirement of 3.15.A cannot be otherwise secured in position, met, restore the inoperable equipment is in its correct position.

q to OPERA 3LE status within 74.ays or prepare and submit a Special Report to 3.

At least once per 12 months by l

the Commission within the next 30 days cycling each testable valve in outlining the plans and procedures to the flow path through at least be used to provide for the loss of one complete cycle of full redundancy in this system.

travel.

C.

With the fire suppression system in-

4. -At least once per 18 months by i

operable:

perforning a system functional i

test which includes simulated l

1.

Establish a backup fire suppression automatic actuation of the water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and system throughout its operating sequence, ands j

l 2.

Submit a Special Report:

a) Verifying that each auto-a) 3y telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and matic valve in the flow path j

actuates to its correct 1

b)

In writing no later than the position on a test signal, first working day following the event, outlining the action taken, b) Verifying that each pump the cause of the inoperability and developes at least 2000 spm with.

the plans and sch.edule for restor-at least 110 psi, ing the' system to' OPERABLE status.

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Amendment No.

.f, 86

-216c-

LIMITING CONDITIONS FOR OPERATION bCRVEILLANCEREQUIREMENTS 4.16 (cont'd) 3.16 (cont'd) v S?ECIFICATIONS SPECIFICATIONS A.

The Automatic Sprinkler Systems protect-A.

The Automatic Sprinkler Systems protect-ing the Cable Spreading Room, Cable ing the Cable Spreading Room, Cable Expansion Room, and Northeast Corner -

Expansion Room, and Northeast Corner -

903 Ft. Elev. of Reactor Building shall 903 Ft. Elev. of Reactor Building shall be operable.

be demonstarted to be operable by:

B.

If the requirement of 3.16.A cannot be 1.

At least once per 12 months by met, establish a continuous fire watch cycling each testable valve in the with backup fire suppression equipment flow Path through at least one for the unprotected area within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; complete cycle of full travel.

restore the system to OPERA 3LE status within 14 days or prepare and submit a 2.

At least once per 18 months:

j Special Report to the Co= mission within the next 30 days outlining a)

By performing a system fune-the action taken, the cause of the tional test which includes inoperability and the plans and.

simulated automatic actua-schedule for restoring the system tion of the system, and to OPERABLE status.

1)

Verifying that the auto-matic valves in the flow path actuate to their correct positions on a test signal, and 2)

Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, b)

By inspection of the spray headers to verify their integrity.

s 3.17 CAR 3ON DIOXIDE SYSTEM 4.17 CARBON DIOXIDE SYSTEM APPLICABILITY APPLICA3ILITY Applies to the operational status of the High Applies to the operational status of the Hig Pressure Carbon Dioxide Extinguishing System Pressure Carbon Dioxide Extinguishing System protecting the Diesel Generator Rooms, protecting the Diesel Generator Rooms.

OBJECTIVE 1

To assure continuous Automatic Fire Protection for the Diesel Generator Rooms.

SPECIFICATIONS SPECIFICATIONS A.

The High Pressure Carbon Dioxide Ex;in-A.

The High Pressure Carbon Dioxide Extin-guishing System protecting the Diesel guishing System protecting the. Diesel Generator Rooms shall be operable.

Generator Rooms shall be demonstrated operable by:

Mnendment No.[,

, 86

-216f-

s tIMITING CONDITIONS FOR OPERATION

' SURVEILLANCE REOUIREMENTS 3.17 (cont'd) 4.17 (cont'd)

B.

If the requirement of 3.17.A cannot 1.

At least once per 6 months, be met:

the High Pressure Carbon Dioxide storage cylinders should be 1.

Establish a continuous fire watch weighed.

with backup fire suppression equip-ment for the unprotected area (s) 2.

At reast once per 18 months by 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 verifying the system valves, to OPERA 3LE status within 14 days alarms, and associated venti-or prepare and submit a Special lation motor interlocks and l

Report to the Commission within dampers actuate to a simulated 4

the next 30 days outlining the automatic and manual actuation action taken, the cause of the signal.

A brief air flow test inoperability and the plans and

(" Puff Test") shall be made to schedule for restoring the verify flow from each nozzle.

system to OPERABLE status.

3.18 FIRE HOSE STATIONS 4.18, FIRE HOSE STATIONS APPLICA3ILITY APPLICABILITY Applies to the operational status of the Fire Hose Stations in the Control and Applies to the operational' status of the Reactor Buildings.

Fire Hose Stations in the Control and Reactor Buildings.

OBJECTIVE To assure continuous manual fire fighting capability provided by existing Fire Hose Stations.

SPECIFICATIONS SPECIFICATIONS A.

The Fire Hose Stations shown in Table 3.18 shall be operable.

A.

The Fire Hose Stations in the Control Building and Reactor-3.

If the requirement of 3.18.A cannot Building shall be demonstrated be met, route an additional hose to to be operable by:

the area protected by the inoperable Fire Hose Station from an operable 1.

At.least once per 31 days by:

4 Fire Hose Station of equivalent capacity within I hour.

a)

Visual inspection to assure all required equipment is

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at the station.

2.

At least once per 18 months by:

a)

Removing the hose for inspection and re-racking, an.

b)

Replacement of all degraded gaskets in couplings.

3.

At least once per 3 years by:

a)

Partially opening each hose

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Amendment No*

  • 86 DPERABILITY and no flow

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blockage, and 3

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LXMITXNG' CONDITIONS TOR OPERATION

'SURUEILLANCE REOUIREMENTS 3.20 YARD FIRE HYDRANT AND HYDRANT HOSE 4.20 YARD FIRE HYDRANT AND HYDRANT HOSE HOUSE '

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-APPLICABILITY APPLICABILITY Applies to the operational status of the Applies to the operational status of the yard

-yard fire hydrant, HT-1 and associated fire hydrant, HT-1, and associated hydrant hydrant. hose house located near the north-hose house located near the northwest corner l

west corner of the Intake Structure.

of the Intake Structure.

1 OBJECTIVE To assure continuous manual fire fighting capability for the fire water pumps and service water pumps in the Intake Structure provided by the existing yard fire hydrant.

j HT-1, and the associated hydrant hose house.

1-SPECIFICATIONS SPECIFICATIONS A.

Yard fire hydrant HT-1 and its associ-A.

Yard fire hydrant HT-1 and associated

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ated hydrant hose house shall be hydrant hose house shall be demonstrated operable.

operable:

B.

If the requirement of 3.20A.cannot be 1.

At least once per 31 days by:

met, provide sufficient additional lengths of 2h inch diameter hose a)

Visually inspecting the hydrant hose

. located in an adjacent operable hydrant house to assure all required equipment-hose house to provide service to the is at the hose house.

unprotected area within one hour,' if the inoperable fire hydrant or associated 2.

At least once per six months (once during hydrant hose house is the primary means March, April or May and once during l

of fire suppression; otherwise provide September, October or November) by:

^

the additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

j Restore the hydrant or hoes house to a) Visually inspecting the yard fire j

operable status with*n 14 days or hydrant and verifying that the' hydran:

prepare and submit a Special Report to barrel is dry and that the hydrant is j-l the Commission within the next 30 days not damaged.

outlining the action taken, the cause of the inoperability and the plans and 3.

At least once per 12 months by:

schedule for restoring.che hydrant or hose house to operable status, a) Conducting a hose hydrostatic test at a pressure at least 50 psig greater i

chan the maximum pressure available p

at the yard fire hydrant.

b)

Inspecting all the gaskets and j

' replacing any degraded gaskets in the couplings.

c)

Performing-a flow check of the hydrant to verify its operability.

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J LAmendment No.

. : 86

-2161 -

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4 6;2 (cpnt'd) f.

Investigate all violations of Technical Specifications, including reporting evaluation and recosamendations to prevent recurrence, to the Assistant General Manager - Nuclear and to the Chairman of the NPPD Safety Review and. Audit Board.

3 i

i g.

Perform special reviews and investigations and render reports i

thereon as requested by the Chairman of the Safety Review and Audit Board.

h.

Review all reportable events specified in Section 50.73 to 10CPR I

Part 50.

{

i.

Review drills on emergency procedures (including plant evacuation) and adequacy of communication with off site groups.

I j.

Periodically review procedures required by Specifications 6.3.1, j

6.3.2, 6.3.3, and 6.3.4 as set forth in administrative procedures, i

5.

Authority i

1, The Station Operations Review Committee shall be advisory.

a.

b.

The Station Operations Review Conusittee shall recommend to the Division Manager of Nuclear Operations approval or disapproval of proposals under items 4, a through e and j above.

In case of 1

disagreement between the recommendations of the Station operations j

Review Committee and the Division Manager of Nuclear Operations, the course determined by the Division Manager of Nuclear Operations to be the more conservative will be followed. A written summary of the l

disagreement will.be sent to the Assistant General Manager - Nuclear 1

and to the NPPD Safety Review and Audit Board.

{

t c.

The Station Operations Review Committee shall report to the l

Chairman of the NPPD Safety Review and Audit Board on all re-views and investigations conducted under items 4.f. 4 3, 4.h.

l and 4.1.

d.

The Station Operation. Review Committee shall make determinations j

j regarding whether or not proposals considered by the' Committee involve unreviewed safety questions.

This determination shall i

be subject to review by the NFPD Safety Review and Audit Board.

6.

Records:

Minutes shall be 1 cept for all meetings of the Station Operations Review Cosetittee and shall include identification of all 'documen- -

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I Amendment No.

, 86

-221-l

6. 2, (cont'd) c.

Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CyR.

d.

Proposed changes to Appendix A Technical Specifications or the CNS Operating License.

e.

Violations of applicable codes, regulations, orders, Technical Specifications, license requirements, or of internal ~ procedures or instructions having nuclear safety significance.

f.

Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.

g.

All reportable events specified in Section 50.73 to ICCFR Part 50.

h.

Any indication of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.

1.

Minutes of meetings of the Station Operations Review Committee.

j.

Disagreement between the recommendations of the Station Operations Review Committee and the Division Manager of Nuclear Operations.

k.

Review of events covered under e,f g. and h above include reporting to appropriate members of management on the results of investiga-tions and recommendations to prevent or reduce the probability of recurrence.

5.

Authority: The NPPD Safety Review and Audit Board shall report to and -

be advisory to the Assistant General Manager - Nuclear on those areas of responsibility specified in Specifications 6.2.1.3.4 and 6.2.1.3.7, e

Amendment No.

, 86 4

a 6.4

. RECORD RETENTION 6.4.1 S Year Retention Records and/or legs relative-to the following items shall be kept in a manner convenient for review and shall be retained for at least 5 years

'unless a longer period is required by applicable regulations.

A.

Records of normal station,oteration, including power levels and periods of operation at each power level.

B.

Records of periodic checks, inspection and/or calibrations performed

-to verify that Surveillance Requirements are being met.

l C.

Records of principal maintenance activities, including inspection, t

repair, substitution or replacement.of principal items of equipment pertaining to nuclear safety.

l D.

Records of reportable events as specified in' 6.5.2.

F F

l E.

Record of changes to plant procedures.

F.

Records of special tests and experiments.

G.

Records of wind speed and direction.

6.4.2 Life Retention Records and logs relating to the following items shall be kept for the life of the plant.

A.

Records of changes made to the station as described in the Safety Analysis Report and amendments and reflected in updated, corrected and as-built drawings and records.

3.

Records of new and spent fuel inventory and assembly histories.

C.

Records of station radiation and contamination surveys.

D.

Records of off-site environmental monitoring surveys.

E.

Records of radiation exposure for-all station personnel, including all contractors and visitors to the station in accordance with 10 CFR 20.

F.

Records of radioactivity.in liquid and gaseous vastes released to the environment.

t G.

Design Fatigue Usage Evaluation i

1.

Monitoring, recording, and evaluation will be met for various portions of the-reactor coolant pressure boundary

[

(RCPB) for which detailed fatigue l

l t-Amendmen t 'No.[.

, 86

-228-

'1.

A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) re-ceiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions, 1/ e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special main-tenance (describe maintenance), waste processing, and refueling.

The dose assignment to various duty functions may be. estimates based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totaling less than 20%

of the individual total dose need not be accounted for.

In the aggregate,'at least 80% of the' total whole body dose received from external sources shall be assigned to specific major work functions.

t 2.

A summary description of facility changes, tests or experi-ments in accordance with the requirements of 10CFR50.59(b).

3.

Pursuant to 3.8.A. a report of ra'dioactive source leak L

testing. This repor*t is required only if the tests reveal l

the presence of 0.005 microcuries or more of removable i

contamination.

D.

Monthlv Operating Report l

Routine reports of operating statistics, shutdown experience, and a narrative summary of operating experience relac'ing to safe operation of the facility, shall be submitted on a mopchly basis to the individual designated in the current revision of Reg.

i Guide 10.1 no later than the centh of each month'following the calendar month covered by the report.

6.5.2 Reportable Events A Reportable Event shall be any of those conditions specited in Section 50.73 to 10CTR Part 50.

The NRC shall be notified and a report submitted pursuant to the requirements of Section 50.73.

Each Reportable Event shall-be reviewed by SORC and the results of this review shall be submitted to SRAB and the Assistant General Manager - Nuclear.

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This tabulation supplements the requirements of $20.407 of 10CTR Part 20.

Amendment No.

, 86

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