ML20024G331

Proposed Tech Specs Re Interim Limiting Conditions for Operation & Surveillance Requirements for Plant Fire Detection & Protection Sys

ML20024G331
Person / Time
Site:	Monticello
Issue date:	01/31/1977
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20024G326	List: ML20024G325 ML20024G328 ML20024G331
References
NUDOCS 9102110310
Download: ML20024G331 (17)

Text

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, $" 3.13 and 4.13 FIRE DETECTION AND PROTECTION SYLTEC 189R ou.

os 70 A. Fire Detection Instruments 189R i og B. Fire Suppression Water System 189S C. Ilose Stations 189T 8o" j

.ng D. Fire Barrier Penetration Fire Seals 189U C PJ u T 3.13 Bases 4.13 Bases 189V 189Wl 5.0 DESIGN FEATURES 190 6.0 ADMINISTRATIVE CohTROLS 192 6.1 Organization 192 6.2 Review and Audit 195 ,

6.3 Special Inspections and Audits 201 '

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6.4 Action to be taken if a Safety Limit is Dtceeded 201 i 4

6.5 Plant Operating Procedures 202 6.6 Plant Operating Records 209 l

6.7 Reporting Requirements 211 i

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LIST OF TABLES 30 3.1.1 Reactor Protection System (Scram) Instrument Requirements 4.1.1 Scram Instrument Functional Tests - Minimum Functional Test Frequencies 34 for Safety Instrumentation and Control Circuits 4.1.2 Scram Instrument Calibration Minimum Calibration Frequencies for 36 Reactor Protection Instrument Diannels 50 3.2.1 Instrumentation that Initiates Primary Containment Isolation Functions 53 3.2.2 Instrumentation that Initiates Emergency Core Cooling Systems 57 3.2.3 Instrumentation that Initiates Rod Block 3.2.4 Instrumentation that Initiates Reactor Building Ventilation Isolation and 60 ',

Standby Gas Treatment System Initiation 69 ,

3.2.5 Trip Functions and Deviations 4.2.1 Minimum Test and Calibration Frequency For Core Cooling, Rod Block and 61 Isolation Instrumentation 121B 3.6.1 Safety Related Ilydraulic Snubbers 124 4.6.1 In-Service Inspection Requirements for Monticello 153 3.7.1 Primary Containment isolation

- Environmental 4.8.1 Sample Collection and Analysis Monticello Nuclear Plant 174 Monitoring Program 19M 6.1.1 Minimum Shif t Crew Composition 206 6.5.1 Protection Factors for Respirators ix RDI

I}frRODilCTION .

These Technical Specifications are prepared in accordance with the requirements of 10 CFR 50.36 and apply to the Monticello Nuclear Generating 'riant, Unit No. 1. The bases for these Specifications are included for information and understandability purposes.

1.0 DEFINITIONS The , succeeding frequently used terms are explicitly defined so that a uniform interpretation of the Specifications may be achieved.

O A. Alteration of the Reactor Core l

The act of. moving any component in the region above the core support plate, below the upper grid and within the shroud. (Normal operating functions such as control rod movement using the normal drive mechanism, tip scans, SRM arid IRH detector movements, etc., are not to be considered core alterations.)

B. Hot Srandby l

Hot Standby means operation with the reactor criticai in the startup mode at a power level just aufficient to maintain reactor pressure and temperature. i i

C. Fire Suppression Water System ,

The fire suppression water system consists of: vater sources; pu=ps; and distribution piping with associated sectionalizing isolation valves. Such valves include yard hydrant valves, and the first valve ahead of the water flow alam device on each sprinkler, hose standpipe, or spray system riser.

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30 LIMITING CONDITIOfE FOR OPERATION h.O SURVEILIANCE REQUIREMENTS 3 13 FIRE DETECfION AND PROTECfION SYSTEMS h.13 FIRE DETECTION AND PROTECTION SISTD4S Applicability: Applicability:

Applies to instrument stion and plant systems Applies to the periodic testing of instnamentatiog used for fire detection and pmtection arx1 plant systems used for fire detection W of the nuclear safety-related structures, systems, and protection of the nuclear safety related and components of the plant, structures, systems, and components.

Objective: Objective:

Tb insure that the structures, systems, and components To verify the opembility of instnzmentation and of the plant important to nuclear safety am plant systems used for fire detection and pmtected from fire damage. protection of nuclear safety related structures, systems, and components.

Specification: Specification:

A. Fire Detection Instrumentation A. Fire Detection Instmmentation

1. Whenever irmdiated fuel is in the reactor J. Fire detectors located in the cable spreadi '

vessel and reactor water tempemture is greater room, standby gas treatment systen room, than 2120F, at least ( N-1) of the fire detec- 4.16 KV switchgear area, and intake stnicture tors located in the following areas shall be shall be tested in accordance with the operable, where N is the number installed in following schedule:

each area: cable spreading room, standby gas treatment system mom, 4.16KV switchgear areas, a. At least once each six months each and the intake stnicture. detector shall be inspected and

2. If specification 3.13. A.1 cannot be met, a patrolling fire watch shall be established to b. At least once each 12 months ensure that each protected area with more than each detector shall be functionally one inoperable detector is checked at intervals tested.

no greater than once each hour.

3.13/4.13 189R REV  ;

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r- -A 3.O LIMITIm CONDITIONS FOR OPERATION h.O SURVEILLMCE REQUIRD4E!rIE B. Fire Suppression Water System B. Fire Suppression Water System

1. Except as specified in 313.B.2 or 313.B.3 1. The fire suppression water system shall belov, the system shall be operable whenever be demonstrated operable as follows:

irradiated fuel is in the reactor vessel and reactor water temperatum is greater a. Fire pu=ps ahall be started at least than 2120F vith: once each month and zun for at least 5 minutes on recirculation flov.

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a. At least two of the following pumps opernble and capable of delivering b. A simulated autocntic actuation of each at least 1500 gpm at a discharge fire pu=p and the screen wash p ep, pressure of 90 psig: including verification of pump capability, shall be conducted at least once every

1. Diesel-driven fire pump j 12 months.

2. Fbtor-driven fire pump c. The yani main and the reactor building header shall be flushed at least once

3. screen vash pump every 12 ennths.

b. Piping and correctly positioned valves to d. Valves in flow paths supplying fire supply fire suppression water to all safety suppressior. water to safety related related structures, systems, and components. structures, systems, and co=ponents shall be verified to be correctly positioned at least once every 12 months.

2. From and after the date that one of the two 2. When it is determined that one of the two pumps required by specification 3 13.B.1.a pu=ps required by specification 3 13.B.1.a is made or found inopersble for any reason, is inopemble, the remaining operable pu=p reactor operation is pemissible during the shall be started daily and run for at least succeeding lh days provided that the remaining 5 minutes on recirculation flow until pump is operable. specification 3 13.B.1.a can be met.

3 13/h.13 1893 REV

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30 LDilTING CONDITIOIS FOR OPEIMTION 14. . O SURVEILIANCE REQUIRDEN'IE

3. From and after the date that the supply of fire suppression water to any safety-related structure, system, or component is made or found to be in-terrupted for any reason, reactor operation is permissible only during the succeeding 14 days unless the supply is sooner restored.

4. If the requirements of specifications 3.13.B.1 through 3.13.B.3 cannot be met, an orderly shut-down of the reactor shall be initiated and the reactor shall be placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. Hoee Staitons C. Hose Stations

1. Whenever irradiated fuel is in the reactor vessel 'Ihe hose stations specified in 313.C.1 shall be and reactor water temperature is greater than 2120F, hose stations protecting the following areas shall demonstrated operable as follows: h be operable: 1. At least once each month a visual inspection shall be conducted to assure all equipnt is available.

a. Diesel generator moms

b. Safety related switchgear areas 2. At least once each 12 months the hoce shall be

c. Safety related areas of the ccreenhouse removed for inspection ani:re-zseking and all

d. Reactor ballaing ,

gaskets in the couplings shall be inspected aal

e. Control mom replaced if necessary. -

f. Cable spreading mom

g. Safety related battery rooms 189T 3 13/h.13 EE7 .

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30 LmITIrn coroITIOIG FOR OFE2ATION I.0 4 SURVEILIANCE REQUIREMEIGB

2. If specification 313.C.1 cannot be met, hoses 3. At least once each five years the valves shall be supplied from operable hose stations shall be partially opened to verify operability and no made available for muting to each area with blockage.

an inopernble hose station.

D. Fire Barrier Penetration Fire Seals D. Fire Barrier Penetration Fire Seals Wenever irradiated fuel is in the reactor vessel 1. A visual inspection of fire barrier penetration fire aud reactor water temperature is greater than 212 F, seals shall be conducted at least once every 18 all fire barrier penetration fire seals protecting months.

safety related areas shall be intact or they shall be continuously attended. 2. Following repair of a fire barrier penetration fire seal, a visual inspection of the seal shall be conducted.

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Elements of the fire detection and protection system are required to be operable to protect safety related structures, systems, und components whenever there is irradiated fuel in the reactor vessel and reactor water temperature is greater than 212 F.- The system will be maintained operable at other times consistent with testing and maintenance requirements.  ;

Ionization type fire . detectors are located in the following areas of the plant to protect safety-related t structures, systems, and components:

T Cable spreading room Standby gas treat 2nent system room 4.16 KV switchgear area Intake structure These detectors sense the airborne products of combustion during the very early stages of a fire. The detectors in each area initiate a local alam and an alarm in the Control Room. The specifications require all but one detector in each area to be operable. Since there are at least three detectors in each ares, the loss of ,

one detector does not significantly degrade the ability to detect fins in any area. If more then one detector is inoperable a patrouing fire watch is established in the affected area until the required number of detectors are restored to operable status.

The fire suppression water system is supplied by three vertical centrifugal pumps rated at 1500 gpm at 100 psig each.

Two pumps, one motor driven and one diesel driven, are the assigned fire pumps. The third ptanp is motor driven

! and normally assigned as a screen wash pump. Transfer from screen wash duty to fire duty occurs automatically.

j All pumps are started automatically by instrissentation sensing header pressure. Any one ptump is capable of supplying all fire fighting water requirements. Two of the three pumps are required to be operable. If two pumps  ;

become inoperable, up to 14 days are allowed to restore opembility of at least two pumps. If all three pumps '

l are inoperable, or if two pumps are not made operable within lh days, the mactor is placed in cold shutdown.

i l j Fire protection for all safety related areas is provided by hose stations supplied from the fire suppression  ;

j water system. If the water supply to these areas is interrupted, operation of the reactor for a period up to 14 1

! days is permitted. While the nomal supply is interrupted, provision is made for an alternate water supp3,y if l possible during this period. Although major maintenance on the fire protection systems will be scheduled for refueling outages, the ability to isolate sections of the fire header for short periods of time for maintenance

! is provided.

Piping and cabling penetrating fire barr e are provided with fire seals at each fire barrier. If a seal is made-  :

or found to be inoperable for any reaso< e penetration area is continuously attended until an effective  !

j fire sesl is restored. .  ;

i 3.13 BASES 109Y any

O 4.13 BASES:

Fire detectors are tested in accordance with the manufacturer's recomendations. All tests and inspections are perfomed by the plant staff. Every six months each detector is inspe ted for dust accumulation and cleaned if necessary. Every 12 months each detector is activated and proper functionir', of the alam circuitry is checked. Combustion generated cmoke will not be used for these tests. All alarm circuits are automatically supervised for open circuits and ground faults.

Fire pumps are tested each month to verify operability. Test starting of the screen wash pu=p is not required since it is nomally in service. Each fire pu=p is ennually started and operated for at least five minutes with pump flow directed thm2gh the recirculation test line. Every 12 months the operability of the automatic actuation logic for the fire pumps and the scre7n vash pump is verified and the perfomance of each pump is verified to mest system requirements. The specified flush and valve lineup check provide g

assursnee that the piping system is capable of supplying fire suppression water to all safety related areas.

When one of the two required pumps is inoperable, the operable pu=p is started daily to verify operability until two pumps are once again available.

Hose stations in safety related areas are inspected monthly to verify that all required equipment is in place.

Hose station gaskets in hoee couplings and the hose are irspected every year. Operability of hose station isolation valves is verified eve n five years by partially opening each valve to verify flow. All of these tests provide a high degree of assurance that each hose station will perfom satisfactorily after periods of standby service.

Plant fire barrier walls are provided with seals for pipes and cables. Where such seals are installed, they must be maintained intact to perform their function. Visual inspection of each installed seal is required every 18 months and after seal repair. A visual inspection following repair of a seal in the secondary containment bounda g is sufficient to assure that seal leskage will be within acceptable limits.

189W 4.13 BASES Rgl

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- e 6.0 '. ADMINISTRATIVE CONTROLS

• 6.1 Organizati on -

A. The Plant' Manager has the overall full-time onsite responsibility for safe operation of the facility. During periods when the Plant Manager is unavailable, he may delegate this re-sponsibility to other qualified supervisory personnel.

B. The Northern States Power corporate organizational structure relating to the operation of this plant is shown in Figure 6.1.1.-

C. The minimum functional organization for operation of the plant.shall be as shown in Figure 6.1.2 and: '

1. Each on duty shift shall be composed of at. least the minimum shift crew composition shown in Table 6.1.1.

2. At least one licensed operator shall be in the control rocm when fuel is in the. reactor.

3. At least two licensed operators shall be present 'in the control room during cold startup, scheduled reactor shutdown, and during recovery from reactor. trips.

4. An' individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

5. All alterations of the reactor core shall be directly supervised by a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling .

who has no other concurrent responsibilities during this operation.

6. A fire brigade' consisting of three members shall be. maintained on site during the day shift, during refueling outages, and at all other times when site activities such as welding and burning preeent a significant fire hazard. This fire brigade is in addition to the minimum shift crew composition specified in Table 6.1.1 and notes thereto. At all other times three members of the normal shift organization may constitute the fire brigade.

D. Minimum qualifications, training, replacement training and retraining' of plant personnel shall be in accordance with that stated in the " Standard for Selection and Training of Personnel for Nuclear Pcwer Plants", . ANSI N18.1-1971.- The minimum frequency of the retraining program shall be every two years. The training program shall.be under the direction of a designated member of the plant staff.

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E. A training program for individuals serving in the fire brigade shall be maintained under the direction of a designated member of the plant staff. This program shall meet the requirments of Section 27 of the NFPA Code-1976 with the exception of training scheduling. Fire brigade training shall be scheduled as set forth in the operator training and retraining program.

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QUALITY ENCIhTER*

I I MAINTENANCE OPERATIONS TRAINDU RADIATION FIANT ENGINEER- PLANT ENGINEER-SUPERVISOR

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• SHIFT SUPERVISOR (ILO; MECHANICAL LEAD FIATE EQUIP- TECHNICAL ENGINEERS FOR TEODEICAL SUFFORT AND METE & REACTOR SUPPORT & NUCLEAR ENGINEER- FOR OPERATION, ELECTRICAL OPERATOR (IDI TECHNICIANS ING, INSTRL9ENTATION, MAINTENANCE, SUK-MAINTENANCE FOR RADIATION CONTROLS & COMPUTER; VEILLANCE. TESTDIG CB00F PIANT EQUITMENT PROTECTION & I;GTIUME;C & C0;EROIL

& REACTOR OPERATOR (ID) CHEMISTRY SPECIALISTS  !

ASSISTANT PLANT EQUIIHENT OPERATOR FIANT ATTENDANT FIRE BRIGADE MONTICELIA NUCLEAR CENERATING FLANT MEMBERS Functional Organization For (AS REQUIPID) On-Sits Operating Croup CODI:.

• Key Supervisor -

LO Licensed Operator FIGURE 6.1.2 194 ISO Licenced Senior Operator

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MINDUM SHIFT CFS4 COMPOSITION (Ibte 1) 4 APPLICABLE PIAirr CONDITION 3 CATEGORY COLD SHUTD0lH OR ABOVE COLD SHUTDOWN REEUELIM OPERATION No. Licensed Senior Operators 1 (Ibte 2) 1 (ISO)

Total No. Licensed Operators 2 3 (LSO & LO)

Total No. Licensed and Unlicensed 3 5 Personnel O

NOTES:

1. Shift crew composition may be one less than the minimum requirements for a period of time not to exceed two hours in order to accomodate an unexpected absence of one duty shift crew member provided immediate action is taken to restore the shift crew coc: position to within the minimum requirements specified.

2. Does not include the licensed Senior Reactor Operator, or Senior Reactor Operator Limited to Fuel Handling, supervising alterations of the reactor core.

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f. Investigation of all events which are required by regulation or technical specifications to be reported to NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

g. Revisions to the Facility Emergency Plan, the Facility Security Plan, and the Fire Protection Program.

h. Operations Cotraittee minutes to determine if matters considered by that Comittee involve unreviewed or unresolved safety questions.

i. Other nuclear safety matters referred to the SAC by the Operations Comittee, plant management or company management.

J. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems, or components.

k. Reports of special inspections and audits conducted in accordance with specification 6.3.

6. Audit - The operation of the nuclear power plant shall be audited formally under the cognizance of the SAC to assure safe facility operation.

a. Audits of selected aspects of plant operation, as delineated in Paragraph 4.4 of ANSI N18.7-1972, shall be performed with a frequency coczsensurate with their nuclear safety significance and in a mant.er to assure that an audit of all nuclear safety-related activities is completed within a period of two years.

The audits shall be performed in accordance with appropriate written instructions and procedures.

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b. Periodic review of the audit program should be performed by the SAC at least twice a year to assure its adequacy.

c. Written reports of the audits shall be reviewed by the Vice President - Power Production & System Operatbn, by the SAC at a scheduled meeting, and by members of management having responsibility in the areas audited.

6.2 197 REV

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7. Authority The SAC shall be advisory to the Vice President - Power Production & System Operation.

8. Records Minutes shall be prepared and retained for all scheduled meetings of the Safety Audit Cocunittee. Tne minutes shall be distributed to the Vice President-Power Production &

System Operation, the General Superintendent of Nuclear Power Plant Operation, each member of the SAC and others designated by the Chairman or Vice Chainman within one month of the meeting. There shall be a formal approval of the minutes.

9. Procedures A written charter for the SAC shall be prepared that contains:

a. Subjects within the purview of the group.

b. Responsibility and authority of the group.

c. Mechanisms for convening meetings.

d. Provisions for use of specialists or subgroups.

e. Authority to obtain access to the nuclear power plant operating record files and operating personnel when assigned audit functions.

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f. Requirements for distribution of reports and minutes prepared by the group to others in the NSP organization.

6.2 198 REV

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c. Mechanism for scheduling meetings

d. Meeting agenda

e. Use of subcommittee

f. Review and approval, by members, of OC actions

g. Distribution of minutes 6.3 Special Inspections and Audits e

A. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified off-site Northern Statea Power  ;

Company personnel or an outside fire protection consultant.  !

B. An inspection and audit by an outside qualified fire protection consultant shall be performed at intervals no greater than three years.

6.4 Action to be Taken if a Saf y Limit is Exceeded If a Safety Limit is exceeded, the reactor shall be shut down immediately. An immediate report shall be made to the General Superintendent of Nuclear Power Plant Operation, or his designated alternate in his absence, and reported as specified in Section 6.7. A complete analysis of the circumstances leading up to and resulting from the situation, together with recocmendations by the Operations Committee, shall also be prepared. This report shall be submitted to the General Superintendent of Nuclear Power Plant Operation and the Chaiman of the Safety Audit Cocnittee, Reactor operation shall not be resumed until authorized by the U S Nuclear Regulatory Commission.

6.2 - 6.4 201 REV

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9 6.5 Plant Operating Procedures Detailed written procedures, including the applicable check-off and instructions, covering  ;

areas listed below shall be prepared and followed. These procedures and changes thereto, I except as specified in 6.5.D shall be reviewed by the Operation Committee and approved by a member of plant management designated by the Plant Manager.

A. Plant Operations

1. Integrated and system procedures for normal startup, operation and shutdown of the reactor and all systems and components involving nuclear safety of the facility.

2. Fuel handling operations.

3. Actions to be taken to correct specific and foreseen potential or actual malfunction of systems or components including responses to alarms, prLsary system leaks and abnormal reactivity changes and including follow-up actions required after plant protective system actions have initiated.

4. Surveillance and testing requirements that could have an effect on nuclear safety.

5. Implementing procedures of the security plan.

6. Implementing procedures of the emergency plan, including procedures for coping with emergency conditions involving potential or actual releases of radioactivity.

7. Implementing procedures of the fire protection program.

Drills on the procedures specified in A.3 above shall be conducted as a part of the retraining p rog ram. Drills on the procedures specified in A.6 above shall be conducted at least semi-annually, including a check of communications with offsite support groups.

B. Radiological Radiation control procedures shall be maintained and made available to all plant personnel.

These procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20. This radiation protection program shall be organized to meet the requirements of 10 CFR 20.

6.5 202 REV

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