Text

Proposed Tech Specs Deleting Sections Re Fire Protection
	ML20195H897
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/24/1987
From:	; PORTLAND GENERAL ELECTRIC CO.
To:	;
Shared Package
ML20195H869	List: ML20195H866; ML20195H880; ML20195H897;
References
	NUDOCS 8801200399
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LCA 151 Attachment 1 Page 1 of 25 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION Pace 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 Axial Flux Differ 2nce. . . . . . . . . . . . . . . . . . . 3/4 2-1 3/4.2.2 Heat Flux Hot Channel Factor . . . . . . . . . . . . . . . 3/4 2-5 3/4.2.3 RCS Flowrate and R F . . . . . . . . . . . . . . . . . . . . 3/4 2-8 3/4.2.4 Quadrant Power Tilt Ratio. . . . . . . . . . . . . . . . . 3/4 2-10 3/4.2.5 DNB Parameters. . . . . ................. 3/4 2-12 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION. ........... 3/43-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION . . ................... 3/4 3-13 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation . . . . . . . . . . . 3/4 3-33 Movable Incore Detectors . . . . . . . . . . . . . . . . . 3/4 3-37 Seismic Instrumentation. . . . . . . . . . . . . . . . . . 3/4 3-38 Meteorological Instrumentation . . . . . . . . . . . . . . 3/4 3-41 Remote Shutdown Instrumentation. . . . . . . . . . . . . . 3/4 3-44 Chlorine Detection Systems . . . . . . . . . . . . . . . . 3/4 3-47 Deleted. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-48 Deleted. . . . . . . . . . . . . . . . . . . . . . . . .. 3/4 3-50 Accident Monitoring Instrumentation. . . . . . . . . . . . 3/4 3-51 Radioactive Liquid Effluent Instrumentation. . . . . . . . 3/4 3-54 Radioactive Gase;us Process and Effluent Monitoring Instrumettation. . . . . ......... .. 3/4 3-59 S0 Detection Systems. . . . . . . . . . . . . . . . . . .

2 3/4 3-68 3/4.4 REACTOR COOLANT SYSTEM 3/4.t. 1 REACTOR COOLANT LOOPS. . . ... . ............ 3/44-1 TROJAN-UNIT 1 IV An,andment No. (8, 58, 78, 99,105,137 8801200399 871224 PDR ADOCK 05000344 P PDR

c LCA 151 Attachment 1 Page 2 of 25 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........ 3/4 7-12 3/4.7.3 COMPONENT COOLING WATER SYSTEM......................... 3/4 7-13 3/4.7.4 SERVICE WATER SYSTEM................................... 3/4 7-15 3/4.7.5 ULTIMATE HEAT SINK..................................... 3/4 7-17 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM.............. 3/4 7-18 3/4.7.7 SEALED SOURCE CONTAMINATION............................ 3/4 7-21 3/4.7.8 DELETED Deleted................................................ 3/4 7-23 Deleted................................................ 3/4 7-27 Deleted................................................ 3/4 7-29 3/4.7.9 DELETE 0................................................ 3/4 7-31 3/4.7.10 SNUBBERS............................................... 3/4 7-32 3/4.7. ' CONTROL BUILDING MODIFICATION CONNECTION BOLTS......... 3/4 7-38 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating.............................................. 3/48-1 Shutdown............................................... 3/4 8-5

! 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - 0perat'ing.......................... 3/4 8-6 A'.C. Distribution - Shutdown........................... 3/4 8-7 0.C. Distribution - Operating.......................... 3/4 8-8 0.C. Distribution - Shutdown........................... 3/4 8-10 3.4.8.3 UNDERVOLTAGE PROTECTION 4.16 kV Emergency Bus Undervoltage Protection.......... 3/4 8-11 l

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LCA 151 Attachment 1 Page 3 of 25 INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE......................................... B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION....... 8 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM........................ B 3/4 7-4 3/4.7.4 SERVICE WATER SYSTEM.................................. B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK.................................... B 3/4 7-4 3/4.7.5 CONTROL ROOM YENTILATION SYSTEM....................... B 3/4 7-5 3/4.7.7 SEALED SOURCE CONTAMINATION........................... B 3/4 7-5 3/4.7.8 DELETE 0............................................,.. B 3/4 7-5 3/4.7.9 DELETED............................................... B 3/4 7-5 3/4.7.10 Sl;UBBERS.............................................. B 3/4 7-5 3/4.7.11 CONTROL BUILDING MODIFICATION CONNECTION BOLTS........ B 3/4 7-7 3/4.8 ELECiRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES.................................. ....... B 3/4 8-1 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS..................... B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.......... ........................ B 3/4 9-1 3/4.9.2 INSTRUMENTATION....................................... B 3/4 9-1 3/4.9.3 DECAY TIME............................................ B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS..................... B 3/4 9-1 3/4.9.5 COMMUNICATIONS........................................ B 3/4 9-1 TROJAN-UNIT 1 XIII Amendment No. 78, 37, #7, 702

LCA 151 Attachment 1 Page 4 of 25 3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERA-TIONAL MODES or other conditions specified for individual Limitiag Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

a. A maximum allowable extension not to exceed 25% of the sur-veillance interval, and

b. A total maximum combined interval time for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.

4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification. Surveillance Require-ments do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

I 4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:

a. Inservice inspection of ASME Code Class 1, 2 and 3 compo-nents and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Sec-tion 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

TROJAN-UNIT 1 3/4 0-2 Amendment No. EI

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LCA 151 Attachment 1 Page 19 of 25 INSTRUMENTATION BASES 3/4.3.3.6 CHLORINE DETECTION SYSTEMS The OPERABILITY.of the chlorine detection system ensures that sufficient capability is available to promptly detect and initiate protective action in the event of an accidental chlorine release. This capability is required to protect control room personne*. nd is consistent with the recommendations of Regulatory Guide 1.95, "Prot (ction of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release", February 1975.

3/4.3.3.7 DELETED 3/4.3.3.8 DELETED 3_/4.3.3.9 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor-and assess these variables during and following an accident. This capabil-ity is consistent with the recommendation of NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations" and NUREG-0737, "Clarification of TMI Action Plan Requirements".

TROJAN-UNIT 1 B 3/4 3-3 Amendment No. 50, 58, 93

I LCA 151 Attachment 1 Page 20 of 25 PLANT SYSTEMS BASES 3/4.7.6 CONTROL ROOM VENTILATION SYSTEM The OPERABILITY of the control room ventilation system ensures that

1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY cf this system in conjunction with control room design pro-visions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.

This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A",10 CFR 50.

3/4.7.7 SEALED SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that the total body or individual organ irradiation does not exceed allowable limits in the event of ingestion or inhalation of the source material.

The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. Leakage of sources excluded f rom the requirements of this specification represent less than one maximum permissibla body burden for total body irradiation if the source material is inhaled or ingested.

3 /4. 7 . 8 DELETED 3/4.7.9 DELETED 3/4.7.10 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integ-rity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse ef fect on any safety-related system.

A visual inspection sample size for mechanical snubbers of 82 with fewer than two failures was selected because it demonstrates with a 95 percent confidence level that 95 percent of the snubbers are operable. This sample should be randomly selected in order to validate the statistical methodology used to arrive at this sample size. The inclusion in the sample of those snubbers selected for functional testing does not violate the random selection requirement.

TROJAN-UNIT 1 B 3/4 7-5 Amendment No. 18, 25

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LCA 151 Attact lent 1 Page 21 of 25 PL ANT SYSTEMS BASES Visual inspections may be performed using binoculars in those cases where the snubber is inaccessible without scaf folding. In such cases, it must be demonstrated that the acceptance criteria are met. If a suspected defect is found during a binocular inspection and cannot be resolved, a "hands-on" visual inspection will be conducted.

The visual inspection f requency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25 percent) may not be used to lengthen the required inspec-tion interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.

When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspec-tion, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.

When a snubber is found inoperable, an engineer ng eva' uation is performed in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure he: imparted a significant effect or degradation on the supported component or system.

To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested at 18 month intervals. Selection of a representative sample of 10 percent provides a confidence level of approximately 95 percent that 90 percent to 100 percent of the snubbers in the plant will be OPERABLE within acceptance limits.

Observed failures of these sample snubbers shall require functional testing of additional units. When a snubber is found to be inoperable due to failure to lock up or f ailure to move (i.e., f rozen in place), the cause will be evaluated for further action or testing.

In cases where the cause of failure has been identified, additional snubbers that have a high probability for the same type of failure or are being used in the same application that caused the failure shall be tested.

This requirement increases the probability of locating inoperable snubbers without testing 100 percent of the snubbers.

TROJAN-UNIT 1 B 3/4 7-6 Amendment No. 78, 39, 702

LCA 151 Attachment 1 Page 22 of 25 PLANT SYSTEMS BASES (Continued)

Hydraulic snubbers and mechanical snubbers may each be treated as a dif ferent entity for the above surveillance programs.

The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc. . .). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.

The requirements for the maintenance of records and the snubber service life review are not intended to af fect plant operation.

3/4.7.11 CONTROL BUILDING MODIFICATION CONNECTION BOLTS This limitation ensures that the structural adequacy of the modified Control Building will be maintained consistent with the design. Structural adequacy is required to ensure the capability of the Control-Auxiliary-Fuel Building Complex to withstand safely the Operating Basis Earthquake and Safe Shutdown Earthquake. The measurement of tension in and inspection of the through-wall bolts connecting the new structural elements to the Control Building at the specified intervals are sufficient to ensure that loss of tension or degradation of the bolts will not reduce this capability.

The design initial bolt tension includes a 25 percent allowance for bolt tension losses due to phenomena such as bolt relaxation, creep of the concrete and grout and shrinkage of concrete and grout. The combined effect of such phenomena is expected to produce a reduction in bolt tension which is an approximately logarithmic function of time, thus the decreasing sample frequency and sample size is appropriate. Maintenance of bolt tension above

.8 of design initial bolt tension (.8X ) provides margin above the design limit of .75X . Inspectionofthecon8itionofboltsandendanchorageswill detect abnorm 31 degradation of bolts which could result in failure of bolts or unexpected loss of function. The surveillance of the special sample group pursuant to Specification 4.7.11.2 and the trend analysis pursuant to Specification 4.7.11.1.e will ensure that mean bolt tension will not fall below 75Xg between inspections.

TROJAN-UNIT 1 B 3/4 7-7 Amendment No. 39, 702, 705

LCA 151 Attachment 1 Page 23 of 25 ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OVALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Radiation Protection Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in Plant design, and response and analysis of the Plant for transients and accidents.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staf f shall be maintained under the direction of the General Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB)

FUNCTION 6.5.1.1 The Plant Review Board shall function to advise the General i Manager on all matters related to nuclear safety, r

TROJAN-UNIT 1 6-5 Amendment No. #2, 56

LCA 151 Attachment 1 Page 24 of 25 ADMINISTRATIVE CONTROLS

e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President Nuclear and to the Chairman of the Trojan Nuclear Operations Board. The investigation shall include an assessment of the safety significance of each violation.

f. Review of all REPORTABLE EVENTS.

g. Review of facility operations to detect potential safety haza rds,

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Trojan Nuclear Operations Board.

i. Review of the Plant Security Plan and implementing procedures.

j. Review of the Emergency Plan and implementing procedures,

k. Review of the Ot? site Dose Calculation Manual.

1. Review of the Process Control Program for Solid Radioactive Waste. ,

m. Review of the Fire Protection Plan and implementing procedures.

AUTHORITY 6.5.1./ The Plant Review Board shall:

a. Recommend to the General Manager written approval or disapproval of items considered under 6.5.1.6(a) through (c) above.

b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (c) above constitutes an unreviewed safety question,

c. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice Presi-dent Nuclear and the Trojan Nuclear Operations Board of disagreement between the PRB and the General Manager; however, the General Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

TROJAN-UNIT 1 6-7 Amendment No. #2, 52, 55, 97, 99, 728, 735

LCA 151 Attachment 1 Page 25 of 25 ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special Reports shall be submitted to the Regional Administrator, NRC Region V, within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a. Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

b. Inoperable Meteoro?:gical Monitoring Instrumentation, Specification 3.3.3.4.

c. Failed or inoperable PORV or safety valve, Specification 3.4.2, 3.4.3.1, and 3.4.3.2.

d. ECCS Actuation, Specifications 3.5.2 and 3.5.3.

e. Sealed Source Leakage in excess of limits, Specification 4.7.7.1.3.

f. Seismic Event Analysis, Specification 4.3.3.3.2.

g. Accident Monitoring Instrumentation, Specification 3.3.3.9.

h. Control Building Modification Connection Bolts Specifications 3.7.11 and 4.7.11.2.

i. Overpressure Protection System, Specification 3.4.9.3.

j. Reactor Coolant loop, Specification 3.4.1.4.

k. Containment Structural Integrity Specification 4.6.1.6.4.

1. Radioact: ye Effluents, Specifications 3.11.1.2, 3.11.2.2, 3.11.2.3 and 3.ll.E.5.

m. Radiological Environmental Monitoring, Specifications 3.12.1 and 3.12.2.

n. Radioactive Gaseous Process and Ef fluent Monitoring instrumentation, Specification 3.3.3.11.

o. Radiation Monitoring Instrumentation, Specification 3.3.3.1.

TROJAN-UNIT 1 6-17 Amendment No. 55, 78, 78, 87, 92, 77, 99, 705

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?- LCA 151 Attachment 2 Page 1 of 2

2. (cont.)

C. (cont.)

(6) Spent Fuel Pool Modifications racks or the new racks in the spent fuel pool in conjunction with replacement of the existing racks with new racks:

(a) the water in the spent fuel pool shall contain at least 2000 ppm boron and shall be maintained at this boron concentration until completion of the rack replacement; and (b) spent fuel stored in the spent fuel pool must have A decayed at least 60 days from the time it was last QS4 removed from the reactor.

During the time that boron is required in the spent fuel pool, it shall be verified to meet the concen-tration requirement by chemical analysis at least 3 times per 7 days, with a maximum time interval between samples of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Prior to final converainn to the modified rack design, fuel may be stored, as needed, in either the new storage racks described in Technical Specification 5.6.1.2 or in the existing storage racks A

Q88 (or both). The existing racks are designed and shall be maintained with a nominal 13.3-inch center-to-cen2er distance between fuel assemblies placed in the storage racks to enr.ure a Ke gg of less than or equal to 0.95 with the storage pool filled with unborated water, including a conservative allowance for uncertainties as described in Section 3.1.2 of Topical Report PGE-1013.

(7) Quality Assurance Except for the insta1.lation of the hangers, restraints and snubbers identified in item A.1 of Enclosure 1 to this license, which may be completed in accordance with the Quality Assurance Program for Construction, all activities to which a Quality Assurance Program is applicable shall, after the date of issue of this license, be conducted in accordance with the Nuclear Quality Arsurance Program.

Amendment No. 22, 34, 80, 110 Date of Issuance:

March 3, 1986

-4 LCA 151 Attcchment 2 Page 2 of 2

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2. (cont.)

C. (cont.)

(8) Portland General Electric shall implement and maintain in effect all provisions of the approved fire protec-tion program as described in PG1-1012. "Trojan Nuclear Plant Fire Protection Plan - Program Description", and as approved in the SERs dated March 9, 1978; March 25, 1980; October 6,1980; December 14, 1982; July 8, 1983; March 5, 1984; October 15, 1485; and November 12, 1987 subject to the following provision:

The licensee may make changes to the approved fire protectio 7 program without prior cpproval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

(9) Primacy Shielding Modification The licensee is authorized to modify the primery shielding design as described in PGE letter dated April 22, 1977, as supplemented and amended by 29 letters dated September 22 and 23, 1977, December 22, 1917, January I and 24, 1978, March 20, and April 4, 1978.

(10) (This paragraph inten&.onally deleted.)

l (11) Fuel Assemblies The licensee is permitted to use fuel with stainless steel pins and fuel with stainless steel pins and extra grid straps for Fuel Cycle 7 and rubsequent cycles provided:

(a) The fuel with extra grid straps is used only in the 8 corner locations where previously used, and I

l (b) No fresh Cuel modified as above is introducad into the core.

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(13) (This paragraph intentionally deleted.)

lM Amendment No. 22, 29, 67, 91, 106 Date of Issuance:

l April 24, 1985 i

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Excerpt from LCA 151 Trojan Nuclect Plant Attechmsnt 3

-. Updated Final Safety Analysis Report I

95 OTHER AUIILIARY SYSTEMS

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9.5.1 FIRE PROTECTION PROGRAM

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Pire protection is provided for the Plant as describec in the Topical Report, "Trojan Nuclear Plant Fire Protection Plan", PGE-1012. Ihh 9.5.2 COMNUNICATION SYSI,$df, The communication sy6tems include internal inplant and external cosuuni-cations designed to provide convenient and effective operational communi-cations among various Plant locations, and between the Plant and locations external to the Plant.

9.5.2.1 Desian Bases Various communication systems are provided in the Plant to ensure reliable communications during Plant startup, operation, shutdown and 4 maintenance under normal and emergency conditions.

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(1) An inplant communication system includes a central private automatic exchange telephone system with public address features for intercommunication between two or more stations, and for paging and the issuance of Plant-wide instructions such as those for Plant evacuation.

(2) A separate communication system is provided between the refueling area, the spent fuel pool (SFP) area and the control room, which shares a common power eupply with the inplant telephone system.

(3) A commercial telephone system provides direct dialing to outside local and long-distance areas. It provides direct dialing between stations throughout the Plant area.

9.5-1 Amendment 4 b (July 1986)

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Excerpt fros PGE-1012 LCA 151 Trojan Nuclear Plant Attachment 4 Fire Protection Plan - Program Description Page 1 of 19 8.0 OPERATING SPECIFICATIONS 8.1 FIRE PROTECTION INSTRUMENTATION 8.1.1 LIMIT'NG CONDITION FOR OPERATION As a minimum, the fire protection instrumentation for each fire detection zone shown in Table 8-1 shall be OPERABLE.

Aeolicability: Whenever equipment in that fire detection zone is required to be OPERABLE.

Action: With eN or more of the fire detection instrument (s) shown in Table 8-1 inecutsble:

(1) Within I he establish a ftre watch patrol to inspect the zone (s) with the iroperable instrument (s) at least once per _

hour unless the instrument (s) is located inside the Contain- D

( ment, then inspect the containment at least once per 8 he.

1 (2) The provisions of TTS 3.0.3 and 3.0.4 are not applicable. ~

8.1.2 SURVEILLANCE REQUIREMENTS Each of the above-required fire protection instruments shall be demon- ,

strated OPERABLE at least once per 6 months by performance of a CHANNEL

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FUNCTIONAL TEST. Fire detectors which are not accessible during Plant

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operation shall be demonstrated OPERABLE by the performance of a CHANNEL l

FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hr unless l

performed in the previous 6 months.

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The NFPA Code 72D Class B supervised circuits supervision associated with ;

the detector alarms of each of the above-required fire detection instru-

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ments shall be demonstrated OPERABLF at least once per 6 months. l i

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8.1-1 Amendment 3 (July 1987)

LCA 151 Attachment 4 Page 2 of 19 8.1.3 BASES

)

OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall

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facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

)

I Amendment 3 8.1-2 (July 1987) s

LCA 151 Attachment 4 Page 3 of 19

( 8.2 DECOUPLE SWITCHES 8.2.1 LIMITING CONDITION FOR OPERATION All decouple switches in either Train A or Train B and those comon to both trains shall be OPERABLE.

Apolicability: Whenever the applicable equipment is required to be OPERABLE.

Action:

1 (1) With one or more of the decouple switches inoperable, establish a fire watch in the cable spreading room until OPERABILITY is restored.

(2) The provisions of TTS 3.0.3 and 3.0.4 are not applicable.

O

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s 8.2.2 SURVEILLANCE REQUIREMENTS .

Each of the above-required decouple switches shall be demonstrated OPERABLE at least once per 18 months by performing a system functional test by:

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(1) Verifying that the connected equipment will start in the ;

decoupled mode either by cycling the breaker or actually l

starting the equipment. This test may substitute for other

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surveillance testing requirements for applicable components. lt I

(2) Verifying the control room alarm when the decouple switch is

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placed in the decouple mode.

8.2.3 BASES OPERABILITY of the decouple switches in the cable spreading room (CSR) ensures that the control cables passing through the CSR to certain ;

8.2-1 Amendment 3 (July 1987)

LCA 151

Attachment 4

Page 4 of 19 ,

P P

equipment required for ssfe shutdown of the plant will be isolated and local operation of the equipment can be achieved. In the event that a

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g portion of the decouple switches becomes inoperable, a fire watch will be established in the CSR until the knoperable equipment is restored to OPERABILITY, i i

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Amendment 3 .2-2 3

(July 1987)

LCA 151 Attachment 4 Page 5 of 19 8.3 FIRE SUPPRESSION WATER SYSTEM 8.3.1 LIM 7 TING CONDITION FOR OPERATION ii.- fire suppression water system shall be OPERABLE with:

(D One 20 3 spa fire pump capable of being powered by an OPERABLE l diesel engine.

(2) One 2000 spm motor-driven fire pump capable of being powered by an OPERABLE power supply, and (3) An OPERABLE flow path capable of taking suction from the Columbia River and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valvas to the yard hydrant curb valves and the first valve thead of

{h the water flow slatin device on each sprinkler /s; pray / deluge or l hose standpipe riser required to be OPERABLE per Sections 8.4.1

( and 8.5.1. ,

Aeolicability: At all times.

Actions (1) With one pump inoperable, restore the inoperable equipment to l OPERABLE status within 7 days. The provisions of TTS 3.0.3 and 3.0.4 are not applicable. l l

l I (2) With the fire suppression water system otherwise inoperable: l l

(a) Establish a backup fire suppression water system within l 5

24 hr. 1 I

(

8.3-1 Amendment 3 (July 1987)

LCA 151 ;

Attachnent 4 Page 6 of 19 l 8.3.2 SURVEILLANCg REOUIREMENTS The fire suppression water system shall be demonstrated OPERABLE:

(1) At least once per 31 days on a STACCERED TEST BASIS by starting each pump and operating it for at least 15 min.

(2) At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position.

(3) At least once per 12 months by performance of a system flush.

(4) At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

(5) At least once per 18 months by performing a system functional g test which includes simulated automatic actuation of the system throughout its operating sequence, andt (a) Verifying that each automatic valve in the flow path actuates to its correct position on a test signal, (b) Verifying that each pump develops at least 2000 spm at a system head of 125 psis, (c) Cycling each valve in the flow path that ! 3 not testable during Plant operation through at least one complete cycle of full travel, and (d) Verifying that each high pressure pump starts (sequen-tially) to maintain the fire suppression water system pressure 1100 psig.

Amendment 3 8.3-2 (July 1987)

LCA 151 Attachment 4 Page 7 of 19 (6) At least once per 3 years by perfor1ning a flow test of the system in accordance with Chapter 5. Section 11 of the Fire

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Protection Handbook, leth Edition, published by the National Fire Protection Association.

The fire pump diesel engine shall be demonstrated OPgRABLE:

(1) At least once per 31 days by verifying:

(a) The fuel storage tank contains at least 200 gallons of fuel, and (b) The diesel starts from ambiont conditions and operatec for at least 20 min.

(2) At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in

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Table 1 of ASTM D975-78 when checked for water, viscosity and -

sediment.

(3) At least once per 18 months by subjecting the diesel to an ;

inspection in accordance with procedures prepared in conjunc- l tion with its manufacturer's reconaendations for the class of service. ,

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l The fire pump diesel starting 24-volt battery bank and charger shall be 1 demonstrated CPERABLE:

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(1) At least once per 31 dayc by verifying that: l l

l (a) The electrolyte level of each battery is above the plates. l t

and l

(b) The overall battery voltage is 124 volts, t k

8.3-3 Amendment 3 (July 1987)

LCA 151 Attachment 4 Page 8 of 19

( (2) At least once per 31 days by verifying that the charging current is appropriate for continued service of the battery. )

(3) At least once per 18 months by verifying that (a) The batteries, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, and (b) The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.

8.3.3 BASES 2

v The OPERASILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety-related equipment is located. The fire suppression system consists of the water system. .

sprinklers and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety-related equipment and is a major element in the facility firc protection program.

In the event that portions of the fire suppression systems are inoperable, alternate backup fire-fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.

Amendment 3 8.3-4 (July 1987)

o LCA 151

, Attachment 4 Page 9 of 19 8.4 SPRAY. SPRINKLER. AND/OR DELUCE SYSTEMS 8.4.1 LIMITING CONDITION FOR OPERATION The following spray, sprinkler, and/or deluge systems shall be OPERABLE:

(1) Emergency diesel generator rooms, (2) Auxiliary feedwater pump room, (3) Electrical penetration areas, (4) Diesel fire pump room.

(5) Cable spreading room.

(6) Service water booster pump area, and

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(7) Component cooling water pump area.

Acclicability: Whenever equipment in the spray, sprinkler, and/or deluge protected areas is required to be OPERABLE.

Action:

(1) With one or more of the above-required spray, sprinkler, and/or

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deluge systems inoperable, establish a continuous fire watch j with backup fire suppression equipment for the unprotected f area (s) within 1 he. !

l (2) The provisions of TTS 3.0.3 and 3.0.4 are not applicable. !

i 8.4-1 Amendment 3 (July 1987)

. LCA 151 Attechment 4 Page 10 of 19 8.4.2 SURVEILLANCE REQUIREMENTS Each of the above-required spray, sprinkler, and/or deluge systems shall be demonstrated OPERABLE:

(1) At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

(2) At least once per 18 months:

(a) By perfonning system functional tests (including simulated automatic actestion of the systea) to:

(i) Verify that the automatic valves in the flow path b actuate to their correct positions on a test signel, and

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(ii) Cycle each valve in the flow path that is not testable during Plant operation thrt.iugh ,at least one complete cycle of full travel.

(b) By inspection of the spray headers to verify their integrity, and (c) By inspection of each nozzle to verify no blocka4e.

(3) At least once per 3 years by performing an air flow test through each open head spray / sprinkler header and verifying each open head spray / sprinkler nozzle is unotstructed.

Amendment 3 8.4-2 (July 1987)

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LCA 151 Attachment 4 Page 11 of 19 8.5 FIRE HOSE STATIONS 8.5.1 LIMITING CONDITIONS FOR OPERATION The fire hose stations shown in Table 8-2 shall be OPERALLE.

Acolicability: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

Action:

(1) With one or more of the fire hose ctations shown in Table 8-2 inoperable, route an additional equivalent capacity fire hose to the unprotecte<' area (s) ite: an OP2RABLE hose station within 1 hr.

(2) The provisions of TTS 3.0.3 and 3.0.4 are not applicable. l

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( l-8.5.2 SURVEILIANCE REQUIREMENTS Each of the fire hose stations shown in Table 8-2 shall be demonstrated OPERABLE:

(1) At least once per 31 days bv visoal inspection of the stataon to assure all required equipment is at the station. Fire hose l stations which are not accessible during Plant operation shall be inspected during each cold shutdown exceeding 24 he unless performed in ths previous 31 days. f l

(2) At least once per 13 months by: ;

(a) Removing the hose for inspection and re racking, and i

(b) Inspecting all gaskets and replacing any degraded gaskets l in the couplings. !

(

8.5-1 Amendment 3 (July 1987)

LCA 151 4 Attachment 4 Page 12 of 19 (3) At least once per 3 years by:

)

(a) Partially opening each hose station valve to verify valve ,

OPERABILITY and no flow blockage.

(b) Conducting a hose hydrostatic test at a pressure at least 50 psis gteater than the maximum pressure available at that hose station.

4

)

a 8.5-2 t.mendment 3 (July 1987)

. ~.__ _ _ - _ _ _ _ _

.' LCA 151

Attachment 4 Page 13 of 19 8.6 PENETRATION FIRE BARRIERS 8.6.1 LIMITING CONDITIONS FOR OPERATION All 3-hr penetration fire barriers protecting safety-related areas shall be functional.

Aeolicability: At all times.

Action:

(1) With one or more of the above-required penetration fire barriers nonfunctional in areas with a combus6,1ble loading

>l lb/sq ft equivalent wood, provide either a continuous fire watch on at least one side of the affected penetration within 1 he or verify the OPERABILITY of fire detectors on at least one side of the nonfunctional fire bart'ier and establish an hourly l fire watch patrol.

(2) The provisions of TTS 3.0.3 and 3.0.4 are not applicable.

8.6.2 SURVEILLANCE REQUIREMENTS

Each of **.e above-required penetration fire barriers shall be verified to be functional:

I (1) At least once per 18 months, by a visual inspection.

l (2) Prior to returning a penetration fire barrier to functional l

status following repairs or maintenance by performance of a f

visual **tpection of the affected penetration fire barrier (s).

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l 8.6.3 BASES I I

The functional integrity of the penetration fire barriers ensures that I fires will be confined or adequately retarded from spreading to adjacent 8.6-1 Amendment 3 (July 1987)

. LCA 131 Attachment 4 Page 14 of 19 I

portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to ,)

detection and extinguishment. The penetration fire barriers (doors, walls, dampers, and seals) are a passive element in the facility fire protection program and are subject to periodic inspections.

During periods of time when the barriers are not functional, the com-bustible loading of the safety-related areas dictates the type of temporary protection to be provided. The combustible loadings for each room in the Plant are listed in Table 3-2 of PGE-1012. Trojan Nuclear Plant Fire Protection Review. Where combustible loadings are considered low (il ib/sq ft equivalent wood), credit is allowed for installed detec-

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tion systems and installation of temporary fire barriers. Either of these, in addition to an hourly fire patrol, give adequate assurance that a fire could not initiate and propagate through the nonfunctional penetration barrier. Where combustible loadings are somewhat greater

(>l lb/sq ft equivalent wood) either a temporary fire barrior is installed, an installed detection system is provided, and an hourly fire patrol is established, or a continuous fire watch is required.

For either case, the continuous fire watch c.c the fire watch patrol is required to be maintained until the br.rier is restored to functional status, i

l l

8.6-2 Amendment 3 (July 1987)

LCA 151 Attachment 4 Page 15 of 19

-( 8.7 FIRE BRICADE ADMINISTRATIVE CONTROLS A Fire Brigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include members of the minimum shift cred necessary for safe shutdown of the unit or any personnel required for other essential functions (.uring a fire emergency. Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 he in order to accommodate unexpected absences of on-duty members provided immediate action is taken to restore the Fire Brigade composition to within the minimum requirement of 5.

i A training program for the Fire Brigade shall be maintained under the direction of the General Manager and shall meet or exceed the require-ments of Section 27 of the EFPA Code-1975, except for Fire Brigade training sessions which shall be held at least quarterly. :

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l 8.7-1 Amendment 3 (July 1987) l l

LCA 151 Attachmsnt 4 Pago -16 of 19 TABLE 8-1 Page 1 of 3 FIRE DETECTION INSTRUMENTS INSTRUMENT LOCATION RIMllBitLIMAIRVIEMLLQPEll&Ed*

4BEtha

1. Control Room

a. FIU 6-100, Zone 1 1

b. FIU 6-100, Zone 2 2 '

c. FIU 6-100 Zone 3 1

d. FIU 6-100, Zone 4 J j i

Total 5 t

2. Cable Spreading Room

a. ZIU 6-#2, Zone 1 3 r

b. IIU 6-#2, Zone 2 3 e

c. ZIU 6-#2, Zone 3 3

d. ZIU 6-#2, Zone 4 J Total 12 h,

( 3. Electrical Penetration Area r

a. ZIU 6-#5, Zone 1 2 :

b. ZIU 6-#5, Zone 4 1 i

Total 3 ,

5

4. Switchgear Room i

s. Train A Elevation 69 ft !

(1) ZIU 6-#7, Zone 1 3 '

r (2) ZIU 6-#7, Zone 2 J Total 6 l

\ ,

b. Train 3 Elevation 61 ft I (1) ZIU 6-#6, Zone 3 2 '

(2) ZIU 6-#6, Zone 4 J '

[

Total 5

5. Station Battery Rooms !

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a. Train A Elevation 63 ft l

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ZIU 6-#6, Zone 2 1 !

Amendment 3 ;

(July 1987) '

i

--_--_+

o LCA 151

, Attachmsnt 4 Page 17 of 19 j TABLE 8-1 Page 2 of 3 INSTRUMEWT LOCATION MINIMUM INSTRUMENTS OPERABLE

I.!!Udli

b. Train B Elevation 63 ft ZIU 6-#6, Zone 1 1

6. Containment

a. IIU 6-#5, Zone 2 1

b. ZIU 6-#5, Zone 3 1

c. ZIU 6-#19, Zone 3 1 Total ,

3

7. Auxiliary Feedwater Pump Rooms

a. ZIU 6-#16, Zone 1 1

b. ZIU 6-#16, Zone 2 1

c. ZIU 6-#16, Zone 3 1 Total 3 2*

8. Residual Heat Removal and )

Safety Injection Pump Rooms

a. ZIU 6-#13, Zone 1 1

b. ZIU 6-#13, Zone 2 1 Total 4

9. Service Water Pump Area

.a . ZIU 6-#8, Zone 1 1

b. ZIU 6-#8, Zone 2 1

c. ZIU 6-#8, Zone 3 1 Total 3 l

l 10. Service Water Booster Pump Area

a. ZIU 6-#9, Zone 1 1

b. ZIU 6-#9, Zone 4 1 Total 2 l Amendment 3 l (July 1987) l I

o

" LCA 151

Attschment 4 Paga 18 of 19 TABLE 8-1 Page 3 of 3 C-INSTRUMENT LOCATI0d MINIMUM INSTRUMENTS OPERABLt*

I!!L9.h1

11. Centrifugal Charging Pump Rooms

a. ZIU 6-#14, Zone 2 1

b. ZIU 6-#14, Zone 3 1 Total 2 r

12. Emergency Diesel Generator Rooms

a. ZIU 6-#15, Zone 1 2 M~

b. ZIU 6-#15. Zone 2 1 t

Total 4

13. Component Cooling Water Pump Area

a. ZIU 6 #9, Zone 2 1

b. ZIU 6-#9, Zone 3 1

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Total 2 i

The fire detection instruments located within the Containment are not required to be OPERABLE during the performance of Type A Containment leakage Rate Tests.

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Amendment 3 '

(July 1987)

e LCA 151

Attachment 4 Page 19 of 19

( TABLE 8-2 FIRE HOSE STATIONS LOCATION ELEVATION liqSE STATION L

1. Auxiliary Building 5 ft HS-34

2. Auxiliary Buildins 25 ft HS-33

3. Auxiliary Building 45 ft MS-19, 38

4. Auxiliary Building 63 ft HS-29

5. Auxiliary Building 77 ft MS-28 .-

6. Turbine Building 45 f4 HS-3. 5 m&

7. Turbine Building 69 ft HS-27

8. Turbine Building 93 ft HS-15

9. Control Building 63 ft HS-40

10. Control Building 77 ft HS-26 .

11. Containment 45 ft CHS-A "' '

12. Containment 93 ft CHS-s ta b]

13. Containment 93 ft CHS-C

(al From Domineralized Water System (b] Inspected During COLD SHUTDOWW ,

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l Amendment 3 (July 1987)

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ML20195H897

Text

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