ML20024G408
| ML20024G408 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 11/25/1977 |
| From: | Goller K Office of Nuclear Reactor Regulation |
| To: | Mayer L NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20024G409 | List: |
| References | |
| NUDOCS 9102120401 | |
| Download: ML20024G408 (22) | |
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Docket No. 50-26 1
NOV 2 51977 J.d i
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Northern States Potrer Corspatiy e
i ATTN: Mr. L. O. Mayer, Manager Nu:: lear Support Services 414 Nicollet Mall - 8th Floor Minneapolis, Minnesota 55401 Gentlemen: ~
RE: NONTICELLO NUCLEAR GENERATING PLANT i
As you know, the Nuclear Regulatory Comnission (NRC) has been working closely with your staff since the Brown's Ferry fire to enhance the i
fire protection capability of your facility. A number of improvements have been nade in the-areas of reducing the potential for exposure fires i
by control of combustible materials, control of sources of flane and improvenent of fire protection personnel. These are generally reflected j
in your January 31, 1977 response to our September 30, 1976 letter which requested preparation of interim Technical Specifications on fire protection for your Monticello Nuclear Generating Plant. Following-l our rs view, which included discussion with your staff concerning the interim Technica? Specifications, we have determined that revisions. to your submittal are needed and that the enclosed Technical Specifications 4
i should be impler9ented by an amendment-to your facility license.
In c:any. instances these Technical Specifications are similar to things you are already doing at your facility but which have not been included in
~
your Technical Specifications. We believe that it is important that fire protection requirements generally be consistent for all facilities
-1 and we are taking these steps to achieve consistent interin action with respect-to fire protection for all plants. Please let us know in writing within 20 days-as to whether there are any specific requirenents to which you object.
If you object to ary specific provision of _ the enclosed specifications, cite the portion that you find objectionable an_d specify _
your reasons and the technical bases therefor.
If you have no objection
- to these specifications, it is nonetheless inportant to let us know within
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NOV 2 51977 Northern States Power Company., _
20-days. We plan to initiate steps to issue the enclosed changes to the M..
Technical Specifications for your facility ir approximately 20 days following the date of this letter. If we do not hear.from you, we will act to issue the specifications on the basis that assumes your agreeraent.
o Sincerely, OrinInas signed bg EarlR.Goller j Karl R. Goller, Assistant Director for Operating Reactors Division of Oper ating Reactors
Enclosures:
DISTRIBUTION:
1.
Technical. Specifications Uocket 2.
Safety Evaluation NRC PDR Local PDR j.
cc v/ enclosures:
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3 NOV 2 51977 Northern States Power Company cc w/enciesurest
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Gerald Charnoff Esquire The Environmental Conservation Shaw, Pittman, Potts and Library Trowbridge Minneapolis Public Library 1800 M Street N. W.
300 Nicollet Mall Washington, D. C.
20036 Minnetpolis, Minnesota 55401 Arthur Renquist. Esquire State Department of Health Vice President - Law ATTN: Secretary & Executive Officer Northern States Power Company University Campus 414 Nicollet Mall Minneapolis, Minnesota ' 55440 Minneapolis. Minnesota 55401 i
Mr. D. S. Douglas, Auditor Mr. L. R. Eliason Wright County Board of Commissioners l
Plant Manager Buffalo, Minnesota 55313 l
Monticello Nuclear Generating Plant l
Northern States Power Company Chief. Energy Systems Analyses Monticello, Minnesota 55362 Branch (AW-459) 2 i
Of fice of Radiation Programs Russell J. Hatling. Chairman U. S. Environmental Protection Agency i
Minnesota Environmental Control Room 645. East Tower I
CitizensAssociation(MECCA) 401 M Street. S. W.
Energy Task Force Washington, D. C.
20460 j
144 Melbourne Avenue, S. E.
i Minneapolis, Minnesota 55414 U. S. Environmental Protection Agency Federal Activities Branch Mr. Kenneth Dzugan Region V Office Environmental Planning Consultant ATTN: EIS C0ORDINATOR Office of City Planner 230 South Dearborn Street Grace Building Chicago, Illinois 60604 421 Wabasha Street St. Paul. Minnesota 55102 Sandra S. Gardebring Executive Director Minnesota Pollution Control Agency 1935 W. County Road B2 Roseville, Minnesota 55113 Mr. Steve Gadler 2120 Carter Avenue j
St. Paul, Minnesota 55108 l
Anthony Z. Roisman. Esquire Sheldon, Harmon & Roisman i
102515th Street, H.
W., 5th Floor Washington, D. C.
20005 I
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l NRC FORM 318 (9-76) NRCM 0240 W u. e, eovannessur FnmTING OFFICta 2 75 - ggG-SM l
Northern States Power Company 3-November 25, 1977 cc w/ enclosures:
Gerald Charnoff Esquire The Environmental Conservation -
-Shaw, Pittman, Potts and Library Trowbridge Minneapolis Public Library
- 1800 M Street, N. W.
- 300 Nicollet Mall
-Washington, D. C.
20036 Minneapolis, Minnesota 55401 Arthur Renquist, Esquire State Department of Health Vice President - Law' -
ATTN: Secretary & Executive Officer Northern States Power Company University Campus 414 Nicollet Mall Minneapolis, Minnesota 55440
-Minneapolis, Minnesota 55401 Mr..D. S. Douglas, Auditor-Mr. L. R. Eliason Wright County Board of Connissioners Plant Manager Buffalo, Minnesota 55313 Monticello Nuclear Generating Plar.t Northern States-Pcwer Company -
Chief, Energy Systems Analyses Monticello, Minnesota 55362 Branch (AW-459)
Office of Radiation Programs Russell J. Hatling, Chairman U. S. Environmental Protection-Agency Minnesota Environmental < Control Room 645, East Tower CitizensAssociation(MECCA) 401 M Street, S. W.
Energy Task Force Washington, D. C.
20460 144 Melbourne Avenue, S. E.
' Minneapolis, Minnesota 55414 U. S. Environmental Protection Agency Federal Activities Branch Mr. Kenneth Dzugan
- Region V Office Envi ronmental ' Planni ng Cons ul tant ATTN: EIS COORDINATOR Office of City Planner-230 South Dearborn Street Grace Building:
Chicago, Illinois 60604
' 421'Wabasha Street St. Paul,-Minnesota 55102 Sandra S. Gardebring1
- Executive Director Minnesota Pollution Control Agency 1935 W. County Road 82
= Roseville, Minnesota 55113 Mr. Steve Gadler 2120 Carter Avenue St. Paul, Minnesota. 55108'
-' Anthony Z Roisman, Esquire Sheldon, Harmon & Roisman-1025 15th. Street, N. W.,-5th Floor
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- Washington,'D..C. 20005 4
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3.13 and 4.13 FIRE DETECTION AND PROTECTION' SYSTEMS 189R
.pp A.
Fire Detection Instruments 187R B.
Fire Suppression Water System 189S C.
Hose Stations 189T D.
Fire Barrier Penetration Fire Seals 189V 3.13 Bases 189W 4.13 Bases 189X 5.0 DESIGN FEATURES 190 6.0 ADMINISTRATIVE CONTROLS 192 6.1 Organization 192 6.2 Review and Audit 195 6.3 Special Inspections and Audits 201 6.4 Action to be taken if a Safety Limit is Exceeded 201 6.5 Plant Operating Procedures 202 6.6 Plant Operating Records 209 6.7 Reporting Requirements 211 Amendment No. 15, vi
a LIST OF TABLES
~
3.1.1 Reactor' Protection System (Scram) Instrument Requirements 30 4.1.1 Scram. Instrument Functional Tests - Minimum Functional Test Frequencies 34 for Safety Instrumentation and Control Circuits 4.1.2 Scram Instrument Calibration - Mintmum Calibration Frequencies for' 36 Reactor Protection Instrument Channels 3.2.1 Instrumentation that Initiates Frimary Containment Isolation Functions 50 3.2.2 Instrumentation that Initiates Emergency Core Cooling Systems 53 3.2.3 Instrumentation that Initiates Rod Block 57 3.2.4 Instrumentation that Initiates Reactor Building Ventilation Isolation and 60 Standby Cas *1+eatment System Initiation 3.2.5 Trip Functions and Deviations 69 4.2.1 Minimum Test and Calibration Frequency for Core Cooling, Rod Block and 61 Isolation Instrumentation 3.6.1 Safety Related Hydraulic Snubbers 121B 4.6.1 In-Service Inspection Requirements for Monticello 124 3.7.1 Primary Containment Isolation 153 4.8.1 Sample. Collection and Analysis Monticello Nuclear Plant - Environmental 169 Monitoring Program 6.1.1 Minimum Shife. Crew Composition 194A 6.5.1
' Protection Factors for Respirators 206 Amendment No. 15, 29, I
INTRODUCTION These Technical Specifications are prepared in accordance with the requirements of 10 CFR 50.36 and apply to the Monticello Nuclear Generating Plant, 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 incerpretation of the Specifications may be achieved.
A.
Alteration of the Reactor Core 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 scars, SRM and IRM detector movements, etc., are not to be considered core alterations.)
B.
Hot Standby Hot Standby means operation with the reactor critical in the startup mode at a power level l
l just sufficient to maintain reactor pressure and temperature.
C.
Fire Suppression k'ater System The fire suppression water system consists of: water sources; pumps; and distribution piping with associated sectionalizing isolation valves.
Such valves include yard hydrant valves, and the first valve ahead of the water flow alarm device on each sprinkler, hose standpipe, or spray system riser.
Amendment No. 15, 1
e 4.0 SURVEILLANCE REQUIRDfENTS 3.0- LIMITING CONDITIONS FOR OPERATION 3.13 FIRE DETECTION AND PROTECTION SYSTEMS' 4.13 FIRE DETECTION AND PROTECTION SYSTEMS Applicability:
Applicability:
Applies to instrumentation and plant systems Applies to the periodic testing of instru-used for. fire detection and protection of-the mentn*ien and plant systems used for fire nuclear safety-related structures, systens, detection and protection of the nuclear and components of the plant.
safety related structures, systems, and components.
,0bjective:
Obj ective:
To insure that the structures, systems, and components of the plant important to nuclear To verify the operability of instrumentation and plant systems used for fire detection and safety are protected from fire damage..
protection of nuclear safety related structures, systems, and components.
Specification:
Specification:
A.
Fire Detection Instrumentation A.
File Detection Instrumentation 1.
In each fire detection zone containing 1.
Fire detectors located in the cable equipment required to be operable, at least (N-1) of the fire detection instruments spreading room, standby. gas treatment located in that zone shall be operable, system room, 4.16 KV switchgear. area, l
where N is the total number of fire detection and intake structure shall be tested in accordance with the following instruments installed in the zone.
schedule:
2.
If specification 3.13.A.1 cannot be met, within one hour establish a fire watch patrol to A functional test shall be performed inspect the zone (s) with inoperable instrument (s) every six months.
at least once.per hour. Restore at least (N-1) of the instruments.to operable status within 2.
Fire detector alarm circuitry shall be demonstrated operable every six 14 days or submit a 30-day written report months.
outlining the cause of the malfunction and the plans for restoring the instruments to operable status.
3.13/4.13.
189R REV Amendment No.
i 3.0 LIMITING CONDITIONS FOR OPERATION.
4.0 SURVEILLANCE REQUIREMENTS
[
B.
Fire Suppression Water System-B.
Fire Suppression Water System 1.
Except as specified in 3.13.B.2 or 1.
The. system shall be verified operable 3.13.B.3 below, the system shall be as follows:
operable at all times with:
Operability of the diesel-driven fire a.
a.
At least two of the following pumps, pump starting battery shall be including automatic initiation logic, demonstrated by:
operable and capable of delivering at least 1500 gpm at a discharge 1.
Once each week verify electrolyte pressure cf 90 psig:
level and voltage is within specifications.
1.
Diesel-driven fire pump 2.
Motor-driven fire pump 2.
Once every three months verify the 3.
Screen wash pump specific gravity of each cell is within specifications.
b.
Piping and correctly positioned valves to supply fire suppression water to 3.
Once every 18 months inspect the all safety related structures, systems, batteries, battery racks, and and components.
electrical connections for damage or abnormal deterioration.
2.
If Specification 3.13.B.1 cannot be met, l
restore the inoperable equipment to operable b.
The motor-driven fire pump shall be status within seve.1 days or provide a 30-day started every month and run for at written report outlining the plans and least 15 minutes on recirculation flow.
procedures to be used to provide for the loss of redundancy in the Fire Suppression c.
The diesel-driven fire pump shall be 3
Water system.
started every month from ambient conditions and run for at least l
20 minutes on recirculation flow.
d.
The level in the diesel-driven fire pump day tank shall be checked every month and verified to contain at l
least 65 gallons of fuel.
189S 3.13/4.t3 REV Amendrent No.
l l
l 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVIILLANCE REQUIREMEhTS-i Every three months verify that a l
e.
l sample of fuel from the diesel oil storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM D475-74 when checked for viscosity, water, and sediment.
f.
Every 18 months subjr the diesel-et driven fire pump engine to an inspection '
in accordance with procedures prepared in conjunction with the manufacturer's recommendations for this class of standby service.
g.
A simulat.d automatic actuation of each fire pump and the screen wash pump, including verification of pump capability, shall be conducted i
very 18 months.
h.
The yard main and the reactor butiding heater shall be flushed every 12 months. l 1.
System flow tests shall be performed l
every three years.
- j. Valves in flow paths supplying fire suppression water to safety related structures, systems, and components shall be cycled every 12 months.
k.
Each valve (manual, power operated or automatic) in the flow path shall be verified in its correct position every month.
3.13/4.13 189T Amendnent No.
REV
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.
From and after the date that the supply-2.
When it is determined that one of the of fire suppression water to any safety-two pumps required by specification re.ated structure, system, or component 3.13.B.l.a is inoperable, the i
is made or found to be interrupted for remaining operable pump shall be any reason, within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
started daily and run for at least 20 minutes on recirculation flow a.
Establish a backup Fire Suppression until specification 3.13.B.l.a can Water System.
be met.
b.
Provide prompt notification with a written followup report outlining the actions taken and the plans and schedule for restoring the system to operable status.
C.
Hose Stations C.
Hose Stations 1.
Whenever equipment protected by hose The hose stations specified in 3.13.C.1 stations in the following areas is shall be demonstrated operable as follows:
required to be operable, the hose station (s) protecting those areas 1.
Each month a visual inspection shall shall be operable:
be conducted to assure all equipment is available.
a.
Diesel generator rooms b.
Safety related switchgear areas 2.
Every 18 months the hose shall be c.
Safety related areas of the screenhouse removed for inspection and re-racking d.
Reactor building and all gaskets in the couplings e.
Control room shall be inspected and replaced if f.
Cable spreading room necessary.
g.
Safety related battery rooms 3.
Every 3 years each hose station valve shall be partially opened to verify valve operability and no flow blockage.
4.
Every
- years each hose shall be hydrostatically tested at a pressure at least 50 psig greater than the
. maximum pressure available at that 3.13/4.13 hose station.
(This specification is effective as of January 1981).
189U Amendment No.
REV
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 2.
If Specificaticn 3.13.C.1 cannot be 3.
Every three years, partially open met, hoses supplied from operable hose each hose station valve to verify stations shall be made available for valve operatili.ty and no blockage.
routing within one baur to each area with an inoperable hose station.
D.
Fire Barrier Penetration Fire Seals D.
Fire Barrier Penetration Fire Seals 1.
All penetration fire barriers protecting 1.
A visual inspection of fire barrier creas having ehuipment required to be penetration fire seals shall be operable shall'be operable.
conducted evury 18 months.
2.
If Specification 3.14.D.1 cannot be met, 2.
Following repair of a fire barrier a continuous fire watch shall be established penetration fire seal, a visual on at least one side of the affected fire inspection of the seal shall be barrier (s) within one hour.
conducted.
3.13/4.13 Amendment No.
189V REV
3.13 BASES:
Elements of the fire detection and protection' system are required to be operable to protect safety related structures, systems, and components whenever those structures, systems, or components are required to be-operable. Fire detection sud protection systems will normally be maintained operable at all times except for periods of maintenance'and testing.
l Ionization type fire detectors are located in the following areas of the plant to protect safety-related structures, systems, and components:
I Cable spreading room l
Standby gas treatment system room i
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 alarm and an alarm in the Control Room. The specific tions require all but one detector in each area to be operable.
Since there are at least three detectors in each area, the loss of one detector does not significantly degrade the ability to detect fires in any area.
If more than one detector is inoperable a patrolling 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 c:pplied by thtce 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 pump is mo?.or driven and normally assigned as a screen wash pump. Transfer from screen wash duty to fire duty occurs automatically. All pumps are started automatically by instrumen*.ation sensing header pressure. Any one pump.is capable of supplying all fire fighting water requirements. Two of the three pumps are required to be operabic. If two pumps are inoperable, at least one must be repaired within seven days or a report must be submitted to the Commission. If all pumps are inoperable, or if other circumstances interrupt the aupply of water to any safety related area, a backup source of water must be provided within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the Commission notified.
Fire protection for all safety related areas is provided by hose stations supplied. from the fire suppression water system. If the water supply to these areas is interrupted, continued operation is permitted only if a hose supplied from an operable hose station is made available to protect the area having the inoperable station.
If a seal Piping and cabling penetrating fire barriers are provided with fire seals at each fire barrier.
is made or found to be inoperable for any reason, the penetration area is continuously attended until an effective fire seal is restored.
3.13 BASES Amendment No.
iggy REV
4.13 BASES:
~
All tests and inspections Fire detectors are' tested 1 accordance with the manufacturer's recommendations.
Combustion Every six months each detector is functiona".ly tested.
are performed by the plant staff.
Alarm circuits are functionally checked every six months.
generated smoke is not used in these tests.
In addition, all circuitry is automatically supervised for open viring and gri und faults.
Test starting of the screen wash pump is not Fire pumps are tested each month to verify operability.Each fire. pump is manually started and operated for at least required since it is normally in service.-
Every 18 months the operability 15 minutes with pump flow directed through the recirculation test line.
of the automatic actuation logic for the fire pumps and the screen wash pump is verified and the performance of each pump is verified to meet system requirements. The specified flush and valve checks provide assurance that the piping system is capable of supplying fire suppression water to all safety related areas.
Vhen one of the two required pumps is inoperable, the operable pump ir started daily to verify operability until two pumps are once again available.
This test verifies the hydraulic performance of the A system flow test is specified every three years.
The testing vill be performed using Section 11, Chapter 5 fire suppression fire water header system.
This test is generally performed of the Fire Protection Handbook, 14th Edition, as a procedural guide.
in conjunction with a visit from insurance company inspectors.
is in place.
Hose stations in safety related areas are inspected monthly to verify that all required equipmentOperability of hose station gaskets in hose couplings and the hose are inspected very 18 months.
All of these Hose station isolation valves is verified every three years by partially opening each valve to verify flow.
id tests provide a high degree of assurance that each hose station will perform satisfactorily after per o s of standby service.
Where such seals are installed, they fire barrier walls are provided with seals for pipes and cables.
must be maintained intact to perform their function. Visual inspection of each installed seal is required Plant every 18 months and after seal repair. A visual inspection following repair of a seal in the secondary containment boundary is sufficient to assure that seal leakage will be within acceptable 1Laits.
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4.13 BASES 189X Amendment No.
REV s
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-- y 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization The Plant Manager has the overall full-time onsite responsibility for safe operation _of the A.
facility. During periods when the Plant Manager is unavailable, he may delegate this responsibility to other qualified supervisory personnel.
The Northern States Power correrate organizational structure relating to the eperation of B.
this plant is shown in Figure 6.1.1.
C.
The mintamn functional organization for operation of the plant shall be as shewn in Figure 6.1.2 and:
1.
Each on duty shif t shall be composed of at least the minimum shift crew composition shown in Table 6.1.1.
2.
At least once licensed operator shall be in the control room when fuel is in the reactor.
3.
At least two licensed operators shall be present in the control roou during cold startup, scheduled reactor shutdown. and during recovery from reactor trips.
4 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 of et least 5 members shall be mainteined onsite at all times.
The Fire Brigade shall not include the minimum shift crew necessary for safe shutdown of the unit (4 members) or any personnel required for other essential functions during a fire emergency.
D.
Minimum qualifications, training, replacement training and retraining cf plant personnel shall be in accordance with.that stat ed in the " Standard for Selection and Training of Personnel for Nuclear Power Plants", ANSI N18.1-1971.
The minimum frequency of the retraining program shall be every two years. Th3 training proccam shall be under the direction of a designated member of the plant staff.
6.1 192 Amendment No.
1 s
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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 requirements.
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 plant training program.
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f TAB'.E 6.1..
MINIMUM SilIFT CREW COMPOSITION (Note 1)
APPLICABLE PLANT CONDITIONS CATEGORY COLD SilUTDOWN OR AbOVE COLD SIFJTDOWN REFUELING OPERATION No. Licensed Senior Operators 1 (Note 2 1
(LS0)
Total No. Licensed Operators 2
3 (LSo& Lo)
Total No. Licensed and Unlicensed personnel 3
5 l
I NOTES:
1.
Shift crew composition may be one less than the minimum requirements for a period of time to exceed two hours in order to accomodate an unexpected absence of one duty shif t not crew member provided im:dediate action is taken to restore the shif t crew composition to within the minimum requirements specified.
1 2.
Does not include the licensed Senior Reactor Operator, or Senior Reactor Operator Limited to Fuel Handling, supervising alterations of the reactor core.
l l
i 6.1 194A Amendment No.
(
i i
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 Committee minutes to determine if matters considered by that l
Committee involve unreviewed or unresolved safety questions.
- i. Other nuclear safety matters referred to the SAC by the Operations Coumittee, 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.
1 a.
Audits of selected aspects of plant operation, as delineated in Paragraph 4.4 of ANSI N18.7-1972, shall be perforned. with a f requ.,cy commensurate with their nuclear safety significance and in a manner 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.
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 rev*ewed by the Vice President - Power Production & System Operation, by the SAC at a scheduled meeting, and by j
members of management having responsiblity in the areas audited.
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6.2 Amendment No.
17, 197
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 The minutes shall be distributed to the Vice President-Power Production &
Committee.
System Operation, the General Superintendent of Nuclear Power Plant Operation, each member of the SAC and others designated by the Chairman or Vice Chairman within one month of the meeting. There shall be a formal approval of the minutes.
i 9.
Procedures A written charter for the SAC shall be prepared that contains:
+
Subjects within the purview of the group.
a.
b.
Responsibility and authority of the group.
c.
Mechanisms for convening meetings.
d.
Provisions of use of specialists or subgroups.
Authority to obtain access to the nuclent power plant operating record files e.
and operating personnel when assigned audit functions.
f.
Requirements for distribution of reports and minutes prepared by the group to others in the NSP Organization.
l 198
- 6. 2 Amendment No. 17,
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i
(
't l
c.
Mechanism for scheduling meetings
}
d.
Meeting agenda
' 1 e.
'Use of subcommittee f
j f.
Review and apptovat, by members of OC accions 3
g.
Distribution of minutes i
6.3 Special Inspections and Audits I
A.
An independent fire protect.on and loss prevention inspection and audit shall
~
be performed annually utili.:ing either qualified off-site Northern States Power Company personnel or an out side fire protection consultant.
i B.
An inspection and audit by an outside qualified fire protection consultant shall I
be performed at intervals no greater than three years.
6.4 Action to be Taken if a Safety Limit is Exceeded If a Safety Limit is exceeded, the reactor shall be shut down immediately. An immediate repo rt 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 i
circumstances leading up to and resulting from the situation, together with recommendations by
[
the Operations Committee, shall also be prepared. This report shall be submitted to the General Superintendent of Nuclear Power Plant Operation and the Chairman of the Safety-Audit Committee.
Reactor operation shall not be resumed until authorized by the U. S. Nuclear Regulatory Commission.
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l 6.2 - 6.4 201 Amendment No. 15,
'T 6.5 Plant Operatins Procedures Detailed written procedures, including the applicable check-of f and instructf ons, covering areas listad below shall be prepared and followed. These procedures and changes thereto, except as specified in 6.5.D shall be reviered by the Operatian 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.
l 3.
Actions to be taken to correct specific and foreseen potential or actual malfunction of systems or components including responses to alarns, primary system leaks and abnormal reactivity changes and including follow-up actions required after plant protective system actions have initiated.
t 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 rogram. 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 i
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.
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I 6.5 Amendment No.
20!
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