ML19331D987

Amend 22 to License DPR-34,revising Diesel Fuel Storage Requirements,Updating Company Reorganization & Altering Fire Protection Tech Specs

ML19331D987
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/19/1980
From:	Tedesco R Office of Nuclear Reactor Regulation
To:
Shared Package
ML19331D986	List: ML19331D985 ML19331D987 ML19331D988
References
NUDOCS 8009040509
Download: ML19331D987 (51)

Text

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enow UNITED STATES

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NUCLEAR REGULATORY COMMISSION y ; g(

g WASHINGTON, D. C. 20555

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PUBLIC SERVICE COMPANY OF COLORADO

s. DOCKET NO. 50-267 FORT ST. VRAIN NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE s

Amendment No. 22 License No. OPR-34 The Nuclear Regulatory Commission (the Canmission) has found that:

1.

The applications for amendment by Public Service Company of Colorado A.

(the licensee) dated March 23,1976, March 7,1979, August 13, 1979, August 29, 1979, September 28, 1979 and January 11, 1980, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Connission's regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the 8.

provisions of the Act, and the regulations of the Commission; There is reasonable assurance (i) that the activities authorized by C.

this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common D.

defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 E.

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

Accordingly, the license is amended by changes to the Technical Specifications 2.

as indicated in the attachment to this license amendment, and paragraph 2.0(2) of facility Operating License No. DPR-34 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 22, are hereby incorporated in the The licensee shall operate the facility in accordance license.

with the Technical Specifications.

.P 80 09040 Qc

2-3.

The license amendment is effective as of the date of its issuance.

s FOR THE NUCLEAR REGULATORY COMMISSION C QFA4A Robert L. Tedesco, Assistant Director for Licensing Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: August 19, 1980 I

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ATTA0HMENT AMENDMENT NO. 22 TO FACILITY OPERATING LICENSE DPR-34 DOCKET NO. 50-267 Remove existing pages 4.2-4, 4.2-21, 4.3-9, 4.3-10, 4.3-11, 4.6-2, 4.10-1, 4.10-2, 4.10-3, 5.2-10, 5.2-11, 5.2-21, 5.4-3, 5.4-11, 5.10-1, 5.10-2, 5.10-3, 6.1-3, 7.1-1, 7.1-2, 7.1-3, 7.1-4, 7.1-5, 7.1-6, 7.1-7, 7.1 -9, 7.1-10, 7.1-11, 7.1-12, 7.1-13, 7.2-1, 7.4-1, and 7.4-2.

Al so, add pages 4.2-4a, 4.3-12, 4.10-4, 4.10-5, 4.10-6, 4.10-7, 4.10-8, 4.10-9, 5.2-10a, 5.2-10b, 5.2-10c, 5.2-21(a ), 5.2-22, 5.10-4, 5.10-5, and 5.10-6 which contain new material.

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4.2-4 any normal operating conditions.

Fqr further explanation see FSAR Sections 1.4,10.3 and 14.4.

Specification LCO 4.2.6 - Fire Water System / Fire Suporession Water System, Li=iting Condition f or Oceration s

The reactor shall not be operated at power unless the fire water system is operable including the following:

a)

Both fire va:er pu=p pi:s are operable.

b) 3c:h the motor driven and engine driven fire pumps are operable and there is a: least 325 gallons of fuel for the engine driven pump in storage.

c) The discharge of both the fire water pumps is aligned to the fire water header.

d) As cperable flow pa h shall exist frem :he fire water pt.-; dis charges

o those fixed water spray systems, fire hose stations, and yard fire hydras:s required to be operable in Specifications LCO 4.10.5, LCO 4.10. 7, and LCO 4.10. 8.

3 asis f: Soecification ICO 4.2.6 The operabill:7 ef the fire suppress m systems ensures that adequate fire suppression capabili:7 is available to ceufine and ex:inguish fires oc-curring in any porties of the facility where safety rela:ed equipment is lo-ca:e d.

The fire suppression system censis:s of the va:er systa=, spray and/or sprinklers, carbon dioxide, Halen, fire hose sta:1cus, and yard fire hydrancs.

The ecliec:ive capab111:7 of the fire suppression systems is adequate to mini-1 ni:e po:en:ial dz= age to safety related equipmen:.

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Amendment No. 22 i

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x-4.2.4 A 1

Basis for Specification LCD 4.2.6 (continued)

In addition to the fira. suppression function either of the fire pumps operating in conjunction with either fire water booster pump provides adequate capacity to operate a circulator water turbine and supply emergency cooling water for safe shutdown cooling. With the 325 gallons of fuel in storage, the engine driven fire pump can operate at rated conditions for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> which l

is adequate time to have more fual delivered to the site. For f urther explana-tion, see Final Safety Analysis Raport, Sections 1.4,10.3, and 14.4.

l Srecification LCO k.2.7 - PCRV Pressurizatien Li=itin: Cenditiens for Oreratien e

The PC?.V shall n:t be pressurited te nere than 100 psia unless:

a) The PCEV safety valve installation is operable, and there is less than 5 psig between the rupture disc and relief valve, and bcth inlet bicek valves are locked open.

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• b) All p-inary ar.i seconda y penetration closures and hold 1

i vn plates are in place and operable, per Specification f

LCO k.2 9

• c) The interspaces between the prinary and secondary penetratien l

closures are saintained at a pressu e greater than prinary 1

system pressure with purified heliun Eas.

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• During the initial low power physics testing (< 0.1% of rated thermal power) with the PCRV pressurized and when helium circulators C and D are in the pre-nuclear Pelton wheel configuration, exceptions to provisions b) and c) of this LCO vill be the installation of the secondary closures and pressurization of the crimary secondary closure intersnace of C and D helium circulator cenetrations.

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Amendment No. 22

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e 4.2-21 Specification LCO 4.2.17 - Diesel-Driven Generator for ACM, Limiting Conditions for Operation The reactor shall not be operated at power unless the ACM diesel-generator is operable, including the following:

s 1.

One fuel oil transfer pump from the fuel oil storage tanks to the diesel fuel oil day tank is operable.

2.

The associated switchgear and motor control center are operable.

3.

There are at least 10,000 gallons of fuel total in storage.

The diesel-generator set may be inoperable for up to 7 consecutive days per month or a total of 21 days in a three month period for performance of maintenance, with the reactor at power.

Basis for Specification LCO 4.2.17 The ACM diesel-generator provides power independently of the plant electrical distributien network to various valves, lighting, and pieces of equipment. That equipment provides an alternate means of maintaining PCRV cooling during the Loss of Forced Circulation situation described in the Final Safety Analysis Report, Section 14.10.

The 10,000 gallons of fuel provides for 108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> operation of the generator with full ACM load, which is adequate time for obtaining additional fuel from off site sources.

Specification LCO 4.2.18 - Primary Coolant Depressurization Limiting Condition for Operation The reactor shall not be operated at power unless a flow path for depressurization of the primary system exists that includes the HTFA, Helium Purification Cooler, Helium Purification Dryer, Low Temperature Gas-to-Cas Exchan7er, LTA, and associated valves and piping to the reactor building exhaust ducting.

Basis for Specification LCO 4.2.18 In the event that permanent loss of forced. circulation occurs, it is necessary to depressurize the primary coolant system.

Start of depressuri-zation following onset of loss of circulation is initiated as a function of prior power levels, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> from full power operation, and is completed in approximately seven hours.

Depressurization is completed by venting the purified gas to the atmosphere.

Amendment No. 22

4.3-9 l

9 TABIZ 4.3.10-1 CLASS I ETDRADLIC SNUNEERS s

Turbine Water Drain Snubbers TWDS-1 IWDS-6 WDS-2 TWDS-7 WDS-3 TWDS-8 WDS-4 TWDS-9 W DS-5 WDS-10' Cold Raheat Snubbers - Circulater CRS-Cl-1 CRS-C3-1 CRS-Cl-2 CRS-CF2 CRS-Cl-3 CRS-C3-3 CRS-Cl CRS-C3-4 CRS-Cl-5 CRS-C3-5 CRS-Cl-6 CRS-C3-6 CRS-C2-1 CRS-C4-1 CRS-C2-2 CRS-C4-2 CRS-C2-3 CRS-C4-3 CRS-C2-4 CRS-C4-4 CRS-C2-5 CBS-C4-5 CBS-C2-6 CRS-C4-6 Cold Rahest Snubbers CBS-29 CRS-262 CRS-589 CBS-31 CRS-297 CRS-591 CES-72 CRS-317-1 CRS-632 CRS-76 CRS-317-2 CRS-636 CRS-104 CRS-371 CRS-664 CRS-114 CBS-372 CBS-674 CRS-144 CBS-474 CRS-707 CBS-146 CRS-476 CRS-742 CRS-187 CRS-517 CRS-751 CRS-191 CRS-521 CRS-752 CRS-219 CES-549 CRS-821 CRS-229 CRS-556-1 CRS-822 CRS-556-2 Amendment No. 22

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i 4.3-10 TABLE 4.3.10-1 (continued)

OMS I HYDRAULIC SNUBBERS (continued) klot Raheat Snubbers HRS-23 HRS-128 HRS-24 6 HRS-356 HRS-24 HRS-129 HRS-278 ERS-357 HRS-26 HRS-131 HRS-279 HRS-378 HRS-58 HRS-158 HRS-281 ERS-379 HRS-59 HRS-159 ERS-289 HRS-381 HRS-61 HRS-161 HRS-314 HRS-413 HRS-69 HRS-193 HRS-315 HRS-414 ERS-94 HRS-194 HRS-318 HRS-416 HRS-95 HRS-196 liRS-321 ERS-421 HRS-98 HRS-201 ERS-324 HRS-422 HRS-101 HRS-202 HRS-34 8 ERS-428 HRS-103

'HES-205 HRS-349 HRS-985 ERS-104 HRS-243 HRS-351 ERS-990 HRS-105 HRS-244 Main Steam Snubbers MSS-9 MSS-118 MSS-194 MSS-11 MSS-16 MSS-120-1 MSS-201 MSS-339 MSS-17 MSS-120-2 MSS-204 MSS-346 MSS-18 MSS-120-3 MSS-206 MSS-347 MSS-19 MSS-125 MSS-222 MSS-348 MSS-27 MSS-126 MSS-239 MSS-356 MSS-29 MSS-246 i

MSS-44 MSS-135-1 MSS-247 NSS-369 MSS-51 MSS-139 MSS-248 MSS-376 M55-52 MSS-145-1 M5S-249 MSS-377 i

MSS-54 MSS-145-2 MSS-257 MSS-379 MSS-61 MSS-145-3 MSS-258 MSS-64 MSS-146 MSS-274 MSS-74 MSS-147 MSS-281 MSS-414 MSS-81 MSS-149 MSS-284 MSS-421 MSS-82 MSS-291 MSS-422 MS S-84 MSS-304 MSS-424 i

MSS-109 MSS-IS4 MSS-311 MSS-431 MSS-ll6 MSS-191 MSS-312 MSS-433 MSS-ll7 MSS-192 MSS-314 MSS-822-1 8-Amendment No. 22

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4.3-11 s

TABLE 4.3.10-1 (centinued)

CLASS I HYDRAULIC SNUBBERS (centinued) 3o12er Feed Snubbers Generators BFS-B1-1 3FS-31-4 3FS-32-1 3F5-32-4 BFS-31-2 3F5-B1-5 3F5-32-2 BFS-B2-5 BFS-11-3 3FS-51-6 335-32-3 3FS-B2-6 Boiler Feed Snubbers BFS-54 3FS-421 BTS-526 B73-577 3FS-138 BFS-422 BIS-52 8 BFS-614 BFS-130 375-425 BFS-529 SFS-641 BFS-142 3F5-434-1 B75-530 3FS-679 3FS-149 3'FS-434-2 B75-532 BFS-711 3 FS-152 BFS-434-3 375-534 BFS-763 315-153 3FS-435 BFS-536 SFS-764 3FS-297 325-437 BFS-537 3FS-796 3F5-352 375-451 375-553-1 375-820 B75-397 375-477 bis-553-2 BFS-823 3FS-39 8 375-479 375-556 3FS-824 3FS-400 3F5-498 3F5-563 3FS-843 3FS-402 375-500 BFS-564 375-844 3F5-412 575-501 BI5-566 375-870 BFS-416 375-516 3FS-572 375-871 3FS-420 375-523 375-573 Boiler Feed Snubbers - E:nerzenev BFS-14E BTS-89E BFS-219E BFS-399E BFS-ISI 3FS-122E BIS-228E 3FS-405E 3FS-16E 375-141I BFS-229E 3FS-414E BFS-26E BFS-142E 3FS-243I 3FS-417E BFS-29E 3FS-143E BFS-244E BFS-419E 3FS-30E BFS-158E 3FS-245E 3FS-421E j

375-31E B75-167E 3FS-257E BFS-422E 3FS-47E 3FS-181E 3FS-260E BFS-423E 3FS-52E 3FS-197E 3FS-263E BFS-4 30E 3FS-36E BFS-203E 333-264E BFS-431E 3FS-57I BTS-204E BFS-268E 3FS-432E BFS-74E 3FS-210E.,

BTS-269E 3FS-442E 3FS-76E 3FS-216E l

BFS-444E BFS-77E 3FS-21SI BFS-39 8E Amendment No. 22

4.3-12 TABLE 4.3.10.-1 (continued)

MS I HYDRAULIC SNUBBERS (continued)

Hydraulic 011 Snubberg 305-1 HOS-22 HOS-48 HOS-2 HOS-23 HOS-49 HOS-71 HOS-3 HOS-24 HOS-50 205-72 HOS-4-1 HOS-25 HOS-51 H05-73 H05-4-2 B05-27 HOS-52 HCL-74 E05-5 HOS-28 BDS-53 B05-75 HOS-6 HOS-29 HOS-54 H05-76 HOS-7 B05-30 HOS-55 305-77 B05-8 B05-31 HOS-56 H05-78 H05-9 B05-33 BOS-57 HOS-79 H05-10 H05-34 HOS-58 E05-80 HOS-ll

.HOS-35 HOS-59 HOS-81 305-36 HOS-60 H05-82 505-13 HOS-37 H05-61 B05-83 H05-14 HOS-38 HOS-63 HOS-84 HOS-15 HOS-39 B05-64 H05-85 HOS-16 B05-40 HOS-65 H05-86 HOS-17 B05-41 BOS-66 HOS-87 HOS-IS HOS-42 HOS-88 HOS-19 B05-45 005-89 HOS-20 BOS-46 H03-90 HOS-21 E:nerstency Condensate Snubbers ECS-1 ECS-3 E'CS-5 ECS-7 I

ECS-2 ECS-4 ECS-6 Vent Stack Snubbers VSS-101 VSS-107 VSS-113 VSS-119 VSS-102 VSS-108 VSS-114 VSS-120 VSS-104 VSS-110 VSS-116 VSS-122 VSS-105 755-111 VSS-117 VSS-123 Amendment No. 22

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c) The auxiliary power k80 V a-c essential buses 1A, 13 and 1C must ba operable.

Each essential bus may be inoperable for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> provided the following conditions are satisfied:

1.

Only one k80 V essential bus is inoperable at a time.

2.

h160 V a-c bus 13 is operable.

3.

Engina Driven Fire Pu=p is operable.

h.

Energency Condensate Header is operable.

5 The diesel-generator set (s) supplyins the remaining operable 480 V a-c essential buses are operable.

6.

All equipment supplied by the operable esser

....es, associated with Safe Shutdown Cooling

=ust be operable.

7 Reactor building exhaust fans supplied from the operable essential buses must be operable.

d) Ecth the diesel-generator sets are operable, including the following:

1.

One fuel oil transfer pump from the diesel fuel oil storage tank to the diesel fuel oil day tanks.

2.

One starting air compresser and receiver per.

diesel-generator set.

3 Associated automatic load shedding, load programming, and auto diesel-generator set starting equipment.

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325 gallons of fuel in each day tank.

One diesel generator set =sy be inoperable for up to 7 days (total for both) dur,ing any month provided the 8

Amendment No. 22

4.10-1 4.10 Fire Suppression Systems - Lindting Conditions for Operation Apolicabilit?

Applies to the minimum operable equipment for the plant fire suppress' ion system.

Objective To ensure that the capability for suppressing any fire involving safety related equipment is maintained.

Specification LCO 4.10.1 - Room Isolation Dampers, Three Room Control Complex, Limiting Condition f or Operation The HVAC Room Isolation Dampers of the control room, auxiliary electric room and the 480 volt switchgear room, shall be operable during reactor power operation.

If the dampers become inoperable and cannot be made operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the reactor shall be shut down in an orderly nanner.

Basis for Spec'ification LCO 4.10,{

The HVAC room isolation dampers for the centrol room, auxiliary electric room and the 480 volt switchgear room, provide the required area isolation for maintaining an dffective concentration of Halen after actuation of the Halon fire suppression system.

Soecification LCO 4.10.2 - Halen Fire Suoeression System, Three Room Control Comolex, Limiting Condition for Operation The Halon Fire Suppression system for the control room, auxiliary electric room, and the 480 volt switchgear room shall be operable during reactor power operation.

If the Halon system becomes inoperable and be made operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> the reactor shall be shut down cannot in an orderly manner.

Basis for Specification LCO 4.10.2 The Halon system provides fire suppression capability for the control l

room, auxiliary electric room, and the 480 volt switchgear room. Halon is a non-toxic, halogenated chemical fire suppressant. The Halon system One is a total flooding extinguishing system divided into three sections.

section supplies the 480 volt switchgear room, the second section supplies the control room, and the third tee auxiliary electric room.

Total floeding of these areas will er.tinguish an active fire without requiring abandon =ent i

of the area.

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Amendment No.22

O 4.10-2 The auxiliary electric room Halon System Section is automatically initiated by the simultaneous actuation of a detector in zone #2 and #3 of Table 4.10-3; the 480 volt room Halon System Section is automatically initiated by the simultar.eous actuation of a detector in fire detection zone #5 and #6 of Table 4.10-3.

l The Halon System Section for the 480 volt switchgear room may be manually initiated by a switch located just outside the door of the room.

The Halon System for the auxiliary electric room may be manually initiated by a switch located just outside of the rocm.

The j

Halon System Section of the control room is manually initiated by a i

switch located in the control room.

In the event that electrical power is not available to initiate Halon System operation, each Ralon storage bottle is provided with a manually operated release mechanism which will release the bottle contents when operated.

Specification LCO 4.10.3 - Smoke Detectors and Alarms for Three Room Control Complex and Congested Cable Areas, Limiting Condition fer Operation The reactor shall not be operated at power unless the minimum number of smoke detectors for each of the zones listed in Table 4.10-3 are operable.

If the minimum number of detectors of each zone are not operable, the following actions shall be taken:

An individual shall be designated to inspect the area or areas with inoperable detectors once per hour.

I The inoperable detectors shall be made operable within thirty (30) days or the reactor shall be shut down in an orderly manner.

Basis for Specification LCO 4.10.3 The smoke detection and alarm system provides detection and alarm capability for the control room, auxiliary electric room, the 480 volt switen gear room, the congested cable areas located at the "G" and "J"

coluen rows and selected reactor building HVAC return air ducts in various areas which are not normally manned.

In additienthe system will automatically initiate operation of the Halen fire suppressien system in the auxiliary electric room or the 480 volt switch-gear room upon actuation of a detector in both of the zones in each roo=.

The system alerts the operator to the possibility of a fire in the congested cable areas and to the necessity of investigation of conditions in these areas.

Amendment No. 22

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4.10-3 Specification LCO 4.10.4 - Fire Barrier Penetration Seals, Limiting Condition for Operation All fire barrier penetration seals shall remain intact.

If a fire barrier penetration seal is disturbed, a continuous fire watch shall be posted on either side of the disturbed seal.

Basis for Specification LCO 4.10.4 There are a number of fire 'oarrier penetration seals installed between vital plant areas where cables penetrate walls which act as fire stops.

In -

order to prevent the spread of a fire from one vital area to another, cable penetrations have been sealed with various fire retardant materials.

If the material of a fire barrier must be disturbed for maintenance, establishing a fire watch on either side of the barrier assures early notification of a potential fire hazard.

Soecification LCO 4.10.5 - Fixed Water Spray Svstem. Limi:1st Condition for Overation ne fc11owing fixed water spray or sprinkler systems shall be operable during power operation:

a) ne 430 volt switchgear reem systes.

b) ne auxilia:y elacrrical equipmen: roem system.

c) ne system serving the cengested cable area of the reactor building side of the "J' vall.

d) ne system se:ving the congested cable area of the turbine building side of the "G" vall.

e) The Loop 1 hydraulic power unit sys:am.

f)

The Loop 2 bydraulic power uni ~: system.

g) The bciler feed pume 1A sys am.

b)

'"he boiler feed pump IC system.

1) Auxiliary boiler room.

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Raac:c plan: et.aus: filters.

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1 Amencment No. 22 l

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s 4.10-4 If one or more of the spray. systems becomes inoperable, a fire va:ch shall be established along with backup fire suppression equipment for the The affec:ed area vill be inspected once per hour.

affected area er areas.

If the system or systems can not be made operable within 14 days the reactor

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shall be shutdown in an orderly manner.

Basis for Soecifiestion LCD 4.10. 5 that adequate The operability of the fire suppression systems ensures fire suppression capability is available to confine and extirguish fires oc-is lo-curring in any portion of the facility where saf ety related equipmen:

The fire suppressica system consists of the water system, spray and/or cated.

sprinklers, carbon dioxide, Raion, fire hose stations, and yard fire hydran:s.

The collective capability of the fire suppression syste=s is adequate to =ini-mize potential damage to safety related equipment and is a major element in

.he f a :111:7 fire protection progra=.

h the event that portions of the fire suppression sys:cas are inoperable, al:ernate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipmen: is resto:ed :o s errice.

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l Soecification LCO 4.10.6 - Carben Dieride Fire Sueeression Svstem, !=ereenev Diesel Generator Rooms,1.1=1:ing Condicion for Coeration

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The carbon dioxide fire suppression system for the emergency diesel gen-rooms shall be operable whenever the emergency diesel generators are era:o required to be operable.

If :he carben dioxide fire suppression systes becomes inoperable, the following ac: ion shall be taken:

An ind1tidual shall be assiped :o inspect the emergency diesel gen-

a:or roo=s once per ho"'r.

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Amendment No. 22

4.10-5 Alternate fire suppression equipment shall be s:ationed outside the t

emergency diesel generator rooms.

The carbon dioxide fire suppression sys:em shall be made operable within 30 days or the emergency diesel genera ors shall be considered inoperable.

Basis for Soecifica:Lon LCO 4.10.6 The carbon dioxide fire suppression sys:em provides for detee:1on and suppression of fires in :he emergency diesel generator rocos, areas which are normally manned, and manual backup fire suppression for the 480 vol: room no:

and auxiliary boile room areas.

In the event part of the carbon dioxide fire suppression sys:en becomes made inoperable the hourly, inspections and portable fire fighting equipmen:

available vill minimi.:e the possibility of fire da= age to safe:y rela:ed equip-nent.

Seecificatien LCO 4.10.7 - Fire Hose S:atie:s, Limi:ine Condi:Los for Oeerati:n 4

The fire hose stations listed in Table 4.10-7 shall be operable whenever

he equipment they proteer is required to be operable.

If one or more of these fire hose stations should become 1moperable, an al:erna:e fire hose shall be laid out to the unprotected area from an operable fire hose sta=1on.

Fire hose stations any be added to Table 4.10-7 vi hout prior License l

Amendment provided a revision to Table 4.10-7 is included vi:h a subsequen:

L1:ense Amendmest request.

Amendment No. 22 1

4,10-6 Basis for Specification LCD 4.10.7 The fire water system is the plant's primary fire suppression system and provides the final backup to all other fire suppression systems.

The fire water hoses, or laid out alternates, provide adequate protection for required equipment to minimize damage in case of a fire.

TABLE 4.10-7 BCSE STATION NO.

BICLDING M'"7ATION TH 6 Turbine 4829 TH 7 Turbine 4829 E8 Turbine 4829 E9 Turbine 4829 TH 10 Turbine 4811 3 11 Turbine 4811 3 12 Turbine 4811 3 13 Turbine 4811 TH 1 Turbine 4791 32 Turbine 4791 TH 3 Turbine 4791 34 Turbine 4791 35 Turbine 4791 AG 3 Access Bay 4885 AG 4 Access Bay 4885 l

AG 6 Access 3ay 4864 l

AG 7 Access 3ay 4864 ACd B Acces,s Bay 4846 Amendment No. 22

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l TABLE 4.10-7 (continued)

HOSE STATICN NO.

BUTLDING ELIVATION ACE 5 Access Bay 4885 ACE 2 Access Bay 4940 ACS 1 Access Bay 4960 RH 39 Reac:or 4916 RH 40 Raactor 4916 RH 38 Reactor 4906 RH 34 Raacto r 4881 EE 35 Raaetor 4881 RE 36 Rasetor 4881

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RH 37 Reactor 4881 RH 30 Ranctor 4864 RE 31 Reactor 4864 RE 32 Raacto 4864 RS 33 Raaetor 4864 RH 28 Reactor 4854 RE 29 Rasc:or 4849 RE 26 Reactor 4839 l

RE 27 Raac:or 4839 IE 22 Raactor

-oi9 KE 23 Raac:or 4829 l

l RH 24 Raacto r 4829 RH 25 Reactor 4829 E 20 Raac:or 4811 i

RE 21 Ranctor 4811 1

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'I Amendment No. 22

4.10-8 TA3LE 4.10-7 (continued)

_ HOSE STATION NO.

BUILDING ELEVATION RE 18 Reactor 4801 RE 19 Reactor 4801 RE 13 Reactor 4791 RE.16 Raaetor 4791 E 17 Reactor 4791 i

RE 13 Reactor 4781 RE 14 Reactor 4781 i

RE 10 Reactor 4771 RE 12 Reactor 4771 RE 9 Race:or 4769 RE 11 Raactur 4769 RE 6 Raaetor 4759 RE 7 Rase:or 4759 i

RE 5 Reactor 4756 RE 8 Raactor 4756 RE 1 Raactor 4740 RE 2 Imacrer 4740 E3 Raaetor 4740 RE 4 Reactor 4740 Amendment No. 22 P

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4.10-9 Soeef t'iytion LCO 4.10.8 - Tard Fire Hedracts and Hydrant Rose Hous es, Li=iting Cot.11tions f or Operation The following yard fire hydrants and associated hydrant hose houses shall be operable during power operation:

s a) Number 1 northeast of the circulating water valve pit.

b) Number 3 north 'of the circulating water cooling tower.

c) Number 6 south of the circulating water cooling tower, d) Number 7 southeast of the servica water cooling tower, e) Nu:nbar 11 sputheast of the turbine building.

If one or more of the yard fir.t hydrants or associated hydran: hose houses become inoperable, locate suffic.ient additional lengths of 21/2 inch diameter hose in an adjacent operable hydrant hose house to provide service to the un-protected area.

Basis for Soecification LCD 4.10.8

'"he operabili:7 of the fire suppression systems ensures tha: adequa:e i

fire suppression capabill:7 is available to confine and extinguish fires oc-1 I

curring in any portion of the f acility where saf t:y related equipment is lo-I 1

ca te d.

The fire suppression system consists of the water systen, spray and/or I

sprinklers, carbon dioxide, Halen, fire hose stations, and yard fire hydran:s.

I The ecliect'.ve capabili:7 of the fire sumpression systems is adequa:e to mini-mize potential damage to safety related equipment and is a major ele ant in tha f acility fire proteetion program.

In the event that portions of the fire suppression systa=s are inoperable, alterna:e backup fire fighting equipment is required to be made available in I*

the affected areas until the isoperable equipment is restored :o se:--ice.

Amendment No. 22

(

~.

5 2-10

, Basis for Specification SR 5.2.8 During accident conditions described in FSAR Section 10.3 9, the circulator bearing water =akeup pump is required to operate inter-

=ittently to =ake up bearing vater. 37ur specified testing interval is sufficient to ensure proper operation of the pumps and associated controls.

Sreeification SR 5.2.9 - He Circulator Bearing Water Accu =ulators The heliu= circulator bearing vater accu =ulators, instrumentation, and controls shall be functionally tested =onthly and calibrated annually.

Basis for Seeeification SF 5.2 9 He Circulater bearing water is ner= ally supplied froc the bearing vnter syste= and is backed up by the backup bearing vater syste=

supplied frc= the Energency Feedvater Header.

In the event of a failure in both cf these syste=s, the water stored in the bearing vater accu =ulators is adequate to safely shut dev: both heliu= circulators in a loop.

The

=enthly test interval and annual calibratien interval vill assure proper operatic of the accu =ulator centrols if they should ever be called vpon to function.

1 1

l 1

3 Amendment No. 22

5. 2-10a Specification SR 5.2.10 - Fire Water System / Fire Suppression Vater System, Surveillance Recuirement

~

a) ne fire water system shall be verified operable as follows:

1) ne motor driven and engine driven fire pumps shall be functien-ally tested monthly. ne associa:ed instruments and centrols shall be functionally tes:ed monthly and calibrated annually.

2) ne diesel engine fuel shall be inventoried. mcc..thly and sampled and tested quarterly.

3) ne diesel engine shall be inspected during each refueling shu:-

down.

4) ne diesel engine starting battery and charger shall be inspec:ed veek.17 for proper electrolyte level and overall ba.ery voltage.

ne ba::e:y electrolyre shall be tested quarterly for proper spe-c.ific grav1:7 5)

~he batteries, cell pla:es, and battery racks, shall be inspected each refueling cycle for evidence of physical da= age or abnor=al degrada:icn. ne ba::ery-:o-battery and terminal connections shall be verified to be clean, tight, free of conesion, and coated with an:1-conosion na:erial each refualing cycle, b)

The fire suppression va:ar system shall be verified operable as fol-lows:

1)

Monthly by verifying tha: each valve (manual, power operated, f

or suc..:stic) in the flow path that is no: locked, sealed, or othe: tise secured in posi:1on, is in its correct pos1:1on.

l

(

Amendment No. 22 l

5.2-10b Soecification SR 5.2.10 - Fire Water Svstem/ Tire Suporession Water Svstem, Surveillance Raouirement (con tinued)

2) Semi-annually,by performance of a fire suppression veter system 21ush.

3) A=nually by cycling each testable valve in the fire suppressien va:e system flow path through at least one complete cycle of full travel.

4)

Each refueling cycle by performing a fire suppression water sys-

en functional tes: which includes simulated autocaric actua:1on of the system throughout its operating sequence, and:

(a)

Ve:1.*71ng that each automatic valve in :he flow path ac:u-a:es :o its correct posi:1on.

(b) Verifying tha: each' fire water pu=p develops at leas: 1,500 gym at a sys:en head of 290 feet.

(c)

Cycling each valve in the flow path tha: is not :est able during plan: opera: ice through a: leas: cue comple:e cycle of full travel.

(d) Verifying tha: each fire va:er pump starts sequentially to main: min the fire suppressics va:e system pressure at greater than c equal to 125 psig.

5) Each three years by perfor=1ng a flev tes:.

Amendment No. 22 8

l 3

6. 2, -- lO C.

Seecification SR 5.2.10 - Tire Water SystenJFire Sueeressien Water Systen, Surveillance Recuirement (con tinued)_

5 Basis for Soecification SR 5.2.10 The fire water pumps are required to supply water for fire suppression The specified testing interval is sufficient to and safe shu:down cooling.

The motor driven pump ensure proper operation of the pumps and een:rols.

routinely operates incarmittan:17 The operability of the fire suppression vacer system ensures that ade-is quate fire suppression and emergency safe shu:devn cooling capab111:7

~

available. The specified testing in:arval is sufficient to ensure proper cperatien of the system when required.

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Amendment No. 22 i

b.Z-ll Specification SR 5.2.11 - Primary Reactor Coolant Radioactivity Surveillance

'A grab sample of primary. coolant shall be analyzed a minimum of once per week during reactor operation for its ra'ioactive constituents and shall be used to calibrate the continuous primary coolant activity monitor.

If the contir.uous primary coolant activity monitors is inoperable, the primary coolant activity level reaches 25% of the limits of LCO 4.2.8, or the primary coolant acitivity level increases by a f actor of 25% over the previous equilibrium value of the same reactor power level, the frequency of i

sampling and analysis shall be increased to a mini =um cf once each day until the activity level decreases or reaches a new equilibriu= value (defined by four consecutive daily analysis whose results are within i 10%) at which thee weekly sampling may be resumed.

Basis for Soecification SR 5.2.11 The design of the instrumentation is such that under nor=al operating conditions the activity of the pri=ary coolant is measured and indicated on a continuous basis. The weekly smspling intervai provides an adequate check on the continuous monitoring equipment.

Specificatien SR 5.2.12 - Primary Reactor Coolant Chemical Surveillance The primary coolant shall be analyzed for che=ical constituents a

=ini=u= of once per week.

If the che=1 cal impurity levels exceed 50 percent of the linics of LCO 4.2.10 or LCO 4.2.11, whichever is applicable, the l

f requency of sa=pling and analysis shall be increased to a =inimu= of once each day until the level decreases ei reaches a new equilibrium value (defined by four consecutive daily analysis whose results are within 110%),

at which ti=e weekly ra=pling may be resumed.

Amendment No. 22

5.2-21 Specification SR 5.2.23 - Fireveter Rooster Pump Surveillance Each firavater booster pump shall be tested annually by providing motive power to one water tu'rbine drive in conjunction with the performance, of SR 5.2.7.

In addition each pump shall be functionally tested quarterly.

The associated instruments and controls shall functionally be tested quarterly and calibrated annually.

Basis for Specification SR 5.2.23 During accident conditions described in Final Safety Analysis Report, Section 14.4.2.1, one of the firevater booster pumps and one fire-water pump are required to provide adequate core cooling. The specified testing interval is sufficient to ensure proper operation of the pump and associated controls.

Seecification SR 5.2.24 - Circulating Water Makeue Svsta=, Su veillance ?4-o uiremen t

(

l 4

i l

The circulating water makeup systen shall be verified operable as fol-i j

lows:

a)

The circulating water makeup pond mi: Linum inventory shall be verified l

daily. The pond level instrumentation shall be functionally tested monthly and calibrated annually.

l b)

The circulating water makeup pumps shall be functionally tested weekly, i.

The pu=p controls and instrumentation including the fire water pw 1

f pits shall be functional.'y tested enthly and calibrated annually.

Amendment No. 22

(

l.

y

5.2-2)(a) c)

The valve lineup of the flow path between the circulating water stor-age ponds and the fire water pump pits shall be verified correct month 17

.5 Basis for Soecificarion Sit 5.2.24

~

The circulating water makeup system is required to supply water for fire j

suppression and safe shutdown cooling.

The specified testing interval is suf-ficien t to ensure proper operation of the pu=ips and ccatrols. The system rou-timely operates during normal plant operation.

4

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TESTING OF H0D WITilDRAHAI, PR0llIBIT SYSTDI IllilllillH FREQllEllCIES F0tt CllECKS, CAI.IltRATIONS Aill) fleihod Functlon Frespiency, Clea.in. l Desc rIpt lon Comparison of two separate Channel Indicators.

n.

Check D

a.

1.

Start tip Channel sir.nal to verif y all trips and h.

Tent P

h.

Internal tent alarma.

The internal test signal shall be checked and calibrated

c. assure that its output is in accordance with the desiqri requi rements. This shall be done after congileting the c.

Calibrate R

external test sl90al procedure by checking the output indication when turning the internal test signal switch.

Comparinon of f. separate icvel indicators.

a.

Check D

a.

2.

1.Inear Channel h.

Test H

h.

Internal Leut vinnat to vertry trips and alarms.

balance c.' Cliannel adjusted to arice wJ th licat c.

Calthrate D

calculation.

f Internal test signaln to adjust trips and d.

CalJhrate R

d.

AndlentIons.

Comparison of three separate indicators.

3.

Wide Range Power a.

Clieck D

a.

Cliannel Internal test signals to verify trips and alarms.

h.

Test P

b.

Channel adjusted to ar.ree with heat

' lance c.

Calthration H

c.

calculation.

N d.

Calibration it d.

Intcinal test signals to ad, lust t rips and no indIcatlons.

a S 4.

Ihiltipic Itod Pair a.

Tent P

a.

At t empt tuo rod pair withdrawal.

re z

1111 bd rawa 1 h.

Check It h.

Simniate current t hrough sensor to verify trip y

anl alarms.

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lit tlT 1 :

D - nally when in unc H - 11ont bly 11 -- Once per refuellug cycleIf not don. prevlons ueek P -- l'r tor t o each st art -up

5.104 5.10 Fire Sueoression Systems - Serwillance Recruirements Apo li cab ili ty Applies to the survei lance of the fire suppression and protectics sy's-E 4

- teme and equpment.

5_

Obfeetive To establish the =inimum frequeecy and type of surveillance on the equip-ment of the fire suppression and patmetion equipment to assure that the capa-r bility exists for suppressing any fire involving safety related equipment.

Specification SR 5.10.1 - Three Room Control Complex HVAC System, Surveillance Reouir ement The HVAC isolation dampers and associated fans of the control room, auxiliary electric room, and the 480 volt switchgear room, shall be tested annually to verify correct response to a simulated actuation signal from the Halon Fire Suppression System.

Basis for Soecification SR 5.10.1 l

Annual testing of the room isolation dampers and associated fans of the three-roo= control complex is sufficient to demonstrate capability to operate when required by the Halon Fire Suppression System. The dampers in the ventilation systems of the control and auxiliary electric rooms, and of the 480 volt switchgear room automatically close upon actuation of the Halon Fire Suppression System for that room. At the same time, the various ventilation fans associated with these areas are also tripped off or prevented frem starting.

The isolation of t%~ et;.114caon oystem corcur-rent with Halen d4=chcr;a a requirec to m=intsia effective concentrations cf Halen in the area of the fire.

Specification SR 5.10.2 - Halon Fire Suceression System, Surveillance Recuirements Operability of the Halen fire suppression system for the control room, auxiliaty electric equipment room, and 480 volt switchgear room shall be deconstrated as follows:

a) Quarterly, verify that Halon Storage Cylinder weight is at least 95% of full rated charget b) Quarterly, verify that Halon Stcrage Cylinder pressure is at least 90% of full rated ch,arge.

3 Amendment No. 22

5.10- 1 c) Annually, verify that distribution headers and nozzles are open by flowing clean air at low pressure through the system.

d) Annually, verify response of system to an actuation signal by disconnecting each solenoid coil and measuring the voltage created by the actuating signal.

s Basis for Specification SR 5.10.2

~

Quarterly, check-weighing and pressure verification of the Halon Fire Suppression System cylinders meets the requirements of NFPA Code Section 12A for fire suppression system operability tests. Annual verification that the cistribution headers are not plugged demonstrates their ability to distribute Halon when needed to suppress a fire, while measurement of an actuation signal to the solenoid coil of each cylinder release mechanism gives extra assurance that the system will be capable of performing its design function when required.

Specification SR 5.10.3 - Smoke Detectors and Alarm. Surveillance Recuirement The smoke de:ectors and alar =s listed in Table 4.10-3 shall be demon-strated operable as follows:

a) Monthly by func: focal tes of the non-supervised circui:s between the local panels and the main control panel.

b)

Semi-annually by functional test of the smoke detectors and ala =s,

and by functional tes: of supervisory circuits associated vi:h the s:cke detector alarms.

Basis for Soecifica: ion SR 5.10.3 Operability of :.ke fire detec:1on instrume=tation ensures that adequa:e va ning capabili:y is available for the prompt detec:1c cf fires. This capa-bili:7 is required is order to de:ect and loca:e fires in their early s: ages.

Tes ting a: the specified 12:ervals is sufficies: to ensure operabili:y of the sys:e=.

Amendment No. 22 e

i

~

~

5.10-3

~

Specification SR 5.10.4 - Fire " Barrier Penetration Seal, Surveillance Requirements Fire Barrier Penetration Seals shall be visually inspecttd:

a) Annually, to verify each remains intact, or b)

Immediately following any maintenance which disturbs the retardant material, to verify seal is returned to its previous condition.

Basis for Specification SR 5.10.4 Inspection of penetration seals either annually or following maintenance assures that the Fire Barrier Penetration Seals remain unchanged.

Soecification SR 5.10.5 - Breathing Air Svstem, Surveillance Recuirement The operability of the Breathing Air System shall be demonstrated annually, as follows:

a)

Functionally test the compressors and air supply piping, t

b) Test the quality of the air supplied.

I Basis for Specification SR 5.10.5

(

The Breathing Air System and associated piping supplies compressed air for recharging air cylinders of self-contained breathing apparatus and to the control room for personnel use with approved breathing equipment, in a Halon or toxic gas atmcsphere. By functionally testing the system annually, assurance of breathing air availability and quality is provided.

Soe cificatien SR 5.10.6, Fixed Water Sprav Svste=, Surveillance Receirement Each of the fixed water spray systans listed in LCO 4.10.5 shall be veri-find operable as follows:

a) Annually by cycling each valve in the flow path through one ce=plete cycle of full travel.

b)

Each refueling cycle by inspection of the flow headers to verify their i

integrity a=d inspectice of each no::le' to verify no block. age.

f s

Amendment No. 22

~

d"

's.Iu-o c)

At least once per three years by performing an air flow test through each,open head spray /sprinklar header and verifying each open head spray / sprinkler nozzle is unobstructed.

)

d) The te=perature instruments and controls associated vich the rasctor plant exhaust filters shall be functionally tested se=1-a=nua117

?

i Basis for Soecification SR 5.10.6 Operation of the valves and verification of the flow path at the speci-fled intervals is sufficient to an=nnstrata capability to operate if required.

~

Ser.i-annually cas ting the temperature ins truments and controls associated with the reactor plant exhaust filters is suf ficient to ensure operability of

=

the systen.

i Seecificattee SR 5.10.7 - Carbon Dioxide Fire Sueoression Systen, Surveilluce Recuireme t The carbon dioxide fire suppression system shall be demonstrat.d operable as follows:

a) Weekly - verify storage tank level and pressure.

b)

Annually:

1)

Verify operation of system valres and associated dampers upon actuation signal.

2) 7erify flow fron each nozzle during a " puff tast".

Basis fer Seecificatien SR 5.10.7 A weekly check of level and pressure in the carbon dioxide storage tank

.i insures sufficient carbon dicxide for fire suppression and the support equip-i I

Amendment No. 22 6

4 e.

. t ee.

s.10-5 l

ment is operating properly.

An annual flow check and simulated automatic actuation of the systen along with the regular calibration of system inst:.tmentation provides adequate assurance that the system v1.11 be ready to suppress any fire that could occur

}

s in the emergency diesel generator rooms.

4 Specificatien SR 5.10.8 - Fire Hoes S tations. Surveillance Recuirement Each of the fire hose stations listed in Table 4.10-7 shall be checked monthly to insure all required equipment is at the station.

The fire hoses at these stations shall be removed for inspection, re-packing, and refurbishing as required once per refueling cycle.

These fire hose stations shall be tested for flow and the fire hoses hydrostatically tested ence every 3 years.

Basis for Seecification SR 5.10.8 These checks of the fire water hose system v111 demonstrate the systa='s ability to operate if required.

Specifica1 on SR 5.10.9 - Tard Fire __Hydran ts a=d Rydrant Hos e Hous es, Surveil-1 lance Reedrement Each of the yard fire hydrants and associated hydrant hose houses listed in LCO 4.10.8 shall be verified operable as follows:

a) Honthly by risual inspectica of the hydrant hose house to assure all required equip = ant is at the hose hous e.

l Amendment No. 22 I.

l b) Semi-annually (ones duriig March, April, or May, and once during Sep-cember, October, or November) by visually inspecting each yard fire hydrant and verifying that the hydrant barrel is dry and that the hydrant is not damaged.

c)

Annually by conducting a hoes hydrostatic test at a pressure at least 50 psis greater than the maximum pressure available at any yard fire hydrant and by replacament of all degraded gaskets in couplings.

Basis for Soecificacion' SR 5.10.9 Inspection and testing at the specified intervals is sufficient to ensure operability of the hydrants and hydrant hose houses when required.

Amendment No. 22 l

1 I

6.1-3 Each fuel element is a hexagonal right prism with nominal dimensions Of 14.2 inches across the flats by 31.2 inches high.

The fuel beds and coolant channels are distributed on a triangular array of about 3/4 inch pitch spacing with an ideal ratio of two fuel beds for each coolant channel.

The bottom of the fuel beds in the bottom fuel element of the control rod fuel column does not exceed a length of 23.1 inches frem the top face of the fuel element.

Fuel The fuel consists of fissile uranium highly enriched (93.15%) in 235U and fertile thorium.

The initial fuel loading is about 773 Kg of uranium and 16,000 Kg of thorium.

The initial core is loaded with 13 fuel compositions whose distribution within the core is designec to mock

(

up the fuel content of the equilibrium cycle refueling regions and to shape the radial and axial power distribution.

Fuel is designed for up to a six year life. About one-sixth of the core will be replaced at each refueling interval. The fuel loading in a reload segment will be about 200 Kg of uranium and 2300 Kg of thorium.

All uranium and thorium in the reference fuel elements is in the form of heavy metal carbide and pyrecarbon, referred to as coated fuel particles.

The coatings form the primary fission product barrier.

The coated fuel particles consist of two general types, fissile particles (TH:UC ) and 2

i fertile (TH C2) particles. The fissile particles shall contain thorium and uranium in a weight ratio of about 3.5 to 1 (+1.2, - 0.2) of thorium to uranium. The fertile particles shall contain cnly the-ium.

t.

Amendment No. 22 i.

w

7.1-1 7.1 ORGANI'.J. TION, RD*IE'il AND AUDIT-AEMINISTRATnT Coh"*ROLS Aeolicability Applies to the lines of authority and responsibility for the opera-tional safe:y of the facility, and the organization for periodic reviev and audit of facility o'peration.

Obiectives To define the principal lines of authority and responsibill:y for providing continuing review, evaluation and improvement of the plan:

4 operational safe:y.

Seecifica:ien AC 7.1.1 - Organization, Administrative Controls The organiza: ion and lines of responsibility which govern plant opera: ion shall be as follows:

The Opera: Lens Manager is directly responsible for overall a.

f acility opera: ion and shall delega:e in vri:ing :his responsi-bility during his absence.

b.

In all =a::ers concerning the plan: Operations Review Con =1::ee (p0RC), the Ad-inistrative Services Manager will report to the Opera:icns Manager.

In all natters pertaining to operation and maintenance of the plant c.

and to these Technical Specifications, the Operations Manager shall i

report :c, and be directly responsible to, the Manager, Nuclear production.

The administra:ive and departmental managemen: organi-zations are shows in Figures 7.1-1 and 7.1-2.

d.

Organiza:icn for condue: cf operations of the plant is shown in 1

Figure 7.1-3.

l Amendment No. 22

7.1-2 1.

A licensed senior operator shall' be present on site at all t4 mas when there is fuel in the reactor.

2.

A licensed operator must be in the control room at all times when fuel is in the reactor.

During reactor startup, shutdown, and recovery from reactor trip, two licensed operators must be in the control rec =.

'3. ALL COPI ALTIRAIIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reacto-Operator or Senior 3aac-tor Operator 11=1:ed to 7ual Handling who has no other concurren: respon-sib 111:1es during this opera. ion.

4.

An operator cr technician qualified in radiation protec:Lon procedures shall be presen: 4: the facility at all times tha: there is fual on site.

5.

A size Fire Brigade of at leas: 5 members shall be maintained en site at all tinesi. The F1re 3rigade shali no t include (3) me=bers of the d.ni-- shif t crew necass ary for safe shutdown of the uni: and any per-sonnel required fer other essential fune: ions during a fire emergency.

1. 71re 3rigade co=pesi:1cn may be less than the *d===

requirements for a period of :1me so: to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to ace:moda:a unexpec:ed ab-sence of Tire 3rigade me=bers provided immedia:e action 1.s taken to restore che Fire Brigade to vi hin the =d

'm=

requirements.

Upon ce=mencement of crucercial opera:1cn the staffing of the plan:

shall be i= accordancs irith America = Nazional S:andarda Institute N12.1-1971,

" Selection a=d Training of Perse=nel for Nuclear Power Pla= s" Amendment No. 22 i

7.1-3 Each member of the facility staff shall aset or exceed the miniansa qualifications of ANSI N18.1-1971 for cogarable position, except for the Haalth Physics Supervisor who shall uset or exceed the qualifications cf Regu-I late:7 Guide 1.8, September,1975.

A retraining and replacement training program for the f acility staf f shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommenda:Lons of Section 5.5 of ANSI N18.1-1971 and Appendiz "A" of 10CTR Part 55.

Compliance with Section 5.5 of ANSI N13.1-1971 shall be achieved no latar than si.x months following connance-

sts: of coc:nercial eperation.

A :ral ing program for the Tire 3rigade shall be maintained u= der the directien of the Training Supervisor and shall mee: or exceed the requirements of Section 27 of the P7A Code-1975, excap: for Fire Brigade trai ing sessions which shall be held a: least once per 92 days.

S o e ci fi ca _d.cn AC 7.1. 2 - Plac Coeratiens Review Courittee (? CRC), Adminis-trative Centrels The organiza:1cs, rasponsibilities, and authorir7 of the FORO shall be as follevs:

a.

Me=be -s bio The Plac: Operaticus Xaviav Committee shall be ccaposed of the folleving:

02 air: nan:

Wad etrative Servicas Manager Opera:Lons Manager Superintendant Operations Heal h Physics Supervisor Rasul:s Engineering Superriser 3aac:or Ingineer Technical Services Suoervisor Shif: Supervisor j

Amendment No. 22 1

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s 7,l_4 Superintendent Maintenance, Training Supervisor Scheduling Supervisor b.

Alte rna tes Alternate members shall be appointed in writing by the FORC Chairnan to serve in the absence of a member; however, no more than two alterna:es shall participate in FORC activities at any cne tine.

c.

Meeting Frecuency The FORC shall meet at least once per calendar month and as convened by the Chair =an.

d.

Ouctu:

A quorum shall consis: of the Chairman or alternate Chair =an, and four menbers including alternates.

e.

Reseensib111 ries The ? ORC shall be responsible for:

1.

Review of all procedures required by Technical Specifica: ion

7. 4 (a), (b) and (c) and changes thereto, and any other proposed procedures or changes to approved procedures as deternined by the Operations Manager or Ad=inistrative Services Manager to affect nuclear safety.

2.

Review of all proposed tests and experiments that affec:

nuclear safety.

3.

Review of all proposed changes to the Technical Specifica:icns.

4.

Review of all proposed changes or modifica:1cas to plan l

systa=s or ecuipnent tha: af fect nuclear safety.

5.

invas: iga:1cn of all vi lati:ns of :he Technical Specifications including the preparation and forwarding cf reperts covering the evaluation and recon =epdaticus to prevent recurrence te l.

Amendment No. 22

7.1.-5 I

the Manager, Nuclear Production and to the Chairman of the Nuclear Facility Safe:y Committee.

6.

Review of even:s requiring 24-hour notifica:1on to the Com=ission.

7.

Review of facili:y' operations to detect poten:ial nuclear safe:y hazards.

S.

Perfor=ance of special reviews, investiga: ions and repor:s

hereon as requested by the Chair:an of the Nuclear Facili:y Safe:y Conti::ee.

9.

Review of the Plan: Security Plan and i=plemen:ing procedures and sub=ittal of reco= mended changes to the Chair:an of the Tor: St. Vrain Security Committee.

f.

Authori v The PORC shall:

l 1.

Function to advise the Operations Manager on all =a::ers that I

affect nuclear safety.

I 2.

Rec===end to the Operati:ns Manager, in vriting, approval er i

disapproval of itecs considered under e.l. through 4 ab ove.

3.

Render deter =inations in writing vi:h regard to whether or no: each 1:e= considered under e.l. through 5. above consti:u es an unreviewed safety question.

4 Provide i= media:e wri::en notificatien to the Manager, Suelear Production and the Chair =an of NTSC of disagree =ent be:vae: :he 1

Amendment No. 22

7.1-6 PORC and the Operations Manager; however, the Operations Manage I

shall have respensibility for resolution of such disagreements pursuant to 1 above.

g.

Records The PORC shall maintain written minutes of each meeting and copies i

shall be previded to th'e Manager, Nuclear Production and Chair =an of 3

the For: St. Vrain Nuclear Facility Safety Committee.

Soecifica: ion AC 7.1.3 - Nuclear Facility Safety Com=ittee (NTSC).

Adminis::ctive Centrels The organiza: ion, responsibilities, and au:hori:y of the NTSC shall be as fellows:

a.

Function The Nuclear Facility Safe:y Co--4: tee shall function to provide independen: review and audit of designa:ed activi:1es in the areas of:

1.

Nuclear Power Plan: Opera:1ons 1.

Nuclear Engineering 3.

Chemistry and Fadioche=istry 4.

Me tallurgy 5.

Ins:rumenta:1on and Con:rol 6.

Radiological Safety 7.

Mechanical and Elec::ical Engineering E.

Quali:y Assurance ?:ac:1ces 9.

(0:her appropria:e fields associated with the unique characteris:ics of the nuclear power plan:.)

Amendment No. 22 n

7.1-7 b.

Me=bershio The NTSC shall be cesposed of the following:

Chairman:

Vice Presiden: Production Ntclear Projec: Manager Manager of Safety a'nd Security Quality Assurance Manager Manager Nucisar Produe:1on Consul:a= s, as required and appointed by the Chai:=an c.

Alta nates Alterna e me=bers shall be appointed in writing by the Chair =an; however, no more than two alternates shall participate in NTSC ac.1vities at any cue time.

d.

Censultan ts Consultants shall be utilized as datarzined by the Chair :an, NTSC, to p:=vida expert advice to the NTSC.

a.

Meetine Trecuenc r The EISC shall meet at laast once per calendar quarter during the ini"a1 year of facili.y epara. ion following fuel leading and at least once per six men hs thereaf ar.

f.

Quer-m A que:m of the NISC shall c=sist of the Chairman or his desig=ated al.arnata and a majo:ity of the NTSC members including al:arnatas.

Amendment No. 22 e

(h)

Any indication that there any.b4 a deficiency in some aspect of design or operation of structures, systems, or componen:s, that af fect nuclear saf ecy.

(i)

Reports and meeting minutes of the PORC.

2.

Audits of heility activities shall be performed under the cognizance of the s

Nuclear Facility Safety Committee. These audits shall encompass:

.(a)

The conformance of facility operation to all provisions contained within the Technical Specifications and applicable license condi: ions at least onca per year.

(b)

The performance, training, and qualifica: ions, of :he f acili:y s:af f a: leas: once per year.

(c)

The results of actions taken to correct deficiencies occurring in facili:y equipment, structures, systems, or method of opera: ion that af f ec: nuclear safety a: least once per six menths.

(d)

The performance of ac:ivities required by the Quali:y Assurance Progra=

1 to meet the criteria of Appendix "3",10 CFR 50, a: least once per :ve years.

(e)

The facill:y Emergency Plan and implementing procedures at leas: ence per two years.

(f)

The facility Securi:7 Plan and implementing procedures at least once per two years.

(g)

Any other area of facility operation considered appropriate by :he. FSC V

or the appropriate Vice President.

(h)

An audi: of the Fire Protection Program including a fire protection and loss prevention inspectica shall be performed ann tally, u:ilizing qualified off si:e licensee personnel, an outside fire prote :Lon firm, or an outside qualified fire consul: ant.

This audi: =ust be performed by an ou: side qua14fied fire consul: ant a: invervals no j

grea:er :han 3 years.

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Akendment No. 22 m

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IIIRT ST. VRAIN NilCI. EAR CENERATING STATION CONDllCT OF OPERATIONS CilART flAllACER Nik:1.EA R PRODIK' TION ADMINISTRATIVE OPEllATIONS SERVICES MANAGER HANAGER

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7'.2-1 7.2 SA7 TTY LIMITS, ADMINISTRATIVE CONTROLS Applicability Applies to the administrative procedures to be followed in the s.

event that a safety 11:1: is exceeded.

Objectives To define the ad=inistrative procedures which will be followed in the event that a safety 11=1: is exceeded.

Soecification AC 7.2 - Action to be Taken if a Saferv 11=1: is Exceeded, Ad=inistrative Controls If a safe:y li=it is exceeded, as de fined in Specification SL 3.1 and 3.2, the folleving action shall be taken:

a.

The reactor will be shu: down immediately and reactor operatiens shall no: be resu=ed until approval is received fro = the NRC.

b.

The safe:y limit violation shall be reper:ed to the Cc==ission, the Par.ager, Nuclear Production and to the Chair an, NTSC i==ediately.

c.

A Safety Li=1: Violation Report shall be prepared.

The report shall be reviewed by the p0RC.

This report shall describe (1) appli-cable cir===s:ances preceding the vielation, (2) ef fects of the violatien upon facility co=ponents, syste=s or s:ructures, and (3) cc rec:ive action taken to prevent recurrence.

d.

The Safe:y lini: Violation Repor: shall be sub=itted to the Cor *ssion, the Chair =an, NTSC and the Manager, Nuclea ? oduction i

1 vithin ten days of the violation.

Amendment No. 22 s

' ~

7.4-1 7.4 PROGDURES - AIEINISTRE"IVE CDNTROIS App 11cmb111:v.

Applies to administrative procedures which vill govern plant opera-tions.

Objee:1ve To ensure that vri.ttan proceduzus vill be maintained to define re-quirements for plac operation.

Spe cifica: ion AC 7.4 - Procedures, AA #"#scrative Cocerols W:1::an procedures shall be established, implemented and =aintained l

a.

i covering the activities referenced below; 1.

The applicable proceduras recommended in Appendix A of Regula-tory Guide 1.33, November,1972.

2.

Refueling operations.

3.

Surveillance and tas: activi das of safety-related equipsca:.

.4.

Security Flan implamentation.

5.

Imargency Plan iglacascation, b.

Proemduras and ad=inistra:ive policias of a. above, and changes chareto, shall be reviewed by the PORC aod approved by :he appro-priate Manager prior to iglementation a=d reviewed periodically as set for h in AM"4 strative Proceduras.

Security Plan proceduras, and changes thereto, shall be reviewed by the Plan: Operations Eaview Committe's and approved by :he desi;;oa:ed Plan: Security officar prior to implementa:1cn.

l Security Plan proceduras and changes thereto, shall be reviewed by i

the Tor: S t. Train Secu=1:7 Com=i::ae.

a#

Amendment No. 22 t

_. e -_ -----_ -

-______m 7.4-2 Temporary changes to procedures of a. above may be made provided:

c.

1.

The intent of the original procedure is not altered.

2.

The change is approved by two members of the plant manage-ment staff, at least one of when holds a Samiar Reactor Operator's license.

3.

The change is documented, reviewed by the FORC and approved

{

by the appropriate r.ana ge r within 14 days of implementation.

d.

Procedures for personnel radiation protection shall be prepare.d consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations

(

involving personnel radiation' exposure.

Pursuant to 10 CFR 20.103(c)(1) and (3), allowance shall be made for the use of respiratory protective equipment in restricted areas where individuals are exposed to concentrations in excess of the limits specified in Appeedix 1, Table I, i

Column 1, of 10 CFR 20, subject to the following conditions and limitations:

1.

The limits provided in Section 20.103(a) and (b) shall not be exceeded.

2.

If the radioactive material is of such form that intake through the skin or other additional route is likely, individual exposures to radioactive meterial shall be

{

controlled so that the., radioactive content of any critical organ from all routes of intake averaged over 7 consecutive days does-ot neceed that which would result Amendment No. 22

__.-