Text

Proposed Tech Specs Re Fire Protection Instrumentation,Fire Suppression Water Sys,Spray,Sprinkler &/Or Deluge Sys,Fire Hose Stations,Penetration Fire Barriers & Fire Brigade Administrative Controls
	ML20011D395
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/15/1989
From:	; PORTLAND GENERAL ELECTRIC CO.
To:	;
Shared Package
ML20011D389	List: ML20011D388; ML20011D392; ML20011D395;
References
	NUDOCS 8912270118
	Download: ML20011D395 (73)
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I INDEX LCA 151 Rev. 1 Page 1 of 27 EIMITING CONDITIONS FOR OPERATION AND SURVEltl ANCE REQUIREMENTS SECTION

_Page 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 Axial Flux Difference...................

3/4 2-1 3/4.2.2 Heat Flux Hot Channel Factor...............

3/4 2-5 3/4.2.3 RCS Flowrate and FR....................

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...

3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMLNTATION.

3/4 3-13 3/4.3.3 MON 110 RING 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 l

Decouple Switches.....................

3/4 3-50 Accident Monitoring Inst'umentation............

3/4 3-51 Radioactive Liquid Effluent Instrumentation........

3/4 3-54 Radioactive Gaseous Process and Effluent Monitoring Instrumentation................

3/4 3-59 S0 Detection Systems...................

3/4 3-68 p

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REAC10R COOLANT LOOPS...................

3/4 4-1 TROJAN-UNIT 1 IV Amendment No. #5, 58, 78, 99, 795, 737 8912270118 891215 FDR ADOCK 05000344

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INDEX LCA 151, R;v. 1 Page 2 of 27 LIMITING CONDITIONS FOR OPERATION AND SURVE!LLANCE REQUIREMENTS SECTION PAGE 3/4.7.2 STEAN 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 DELE 1ED Deleted Deleted Deleted 3/4.7.9 DELETED 3/4.7.10 SNUBBERS...............................................

3/4 7-32 3/4.7.11 CONTROL BUILDING MODIFICATION CONNEC110N BOLIS.........

3/4 7-38 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating..............................................

3/4 8-1 Shutdown...............................................

3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution -

Operating..........................

3/4 8-6 A.C. Distribution -

Shutdown...........................

3/4 8-7 0.C. Distribution -

Operating..........................

3/4 8-8 D.C. Distribution - Shutdown...........................

3/4 8-10 3.4.8.3 UNDERVOL1 AGE PR01ECTION 4.16 kV Emergency Bus Undervoltage Protection..........

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TROJAN-UNIT 1 VII Amendment No. 78, 37, #7, 50, 57, 192j

INDEX LCA 151, Rev. 1 Page 3 of 27 BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE.........................................

B 3/4 7-1 3/4.7.2 S1EAM GENERA 10R PRESSURE / TEMPERATURE LIMITATION.......

B 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 3/4.7.6 CONTROL ROOM VENTILATION SYSTEM.......................

B 3/4 7-5 3/4.7.7 SEALED SOURCE CONTAMINATION...........................

B 3/4 7-5 3/4.7.8 DELETED 3/4.7.9 DELETED 3/4.7.10 SNUBBERS..............................................

B 3/4 7-6 3/4.7.11 CONTROL BUILDING MODIFICATION CONNECTION BOLTS........

B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.

SOURCES..........................................

B 3/4 8-1 3/4.8.2 ONS11E POWER DIS 1RIBUTION 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 INS 1RUMENTAT10N.......................................

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-UNil 1 XIII Amendment No. 18, 37, #7, 102 l

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INDEX LCA 151. Rev. 1 Page 4 of 27 3/4.0 APPLICABILITY SURVEILLANCE REOUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERA-TIONAL MODES or other conditions specified f or individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillence 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.

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)(1).

1ROJAN-UNIT 1 3/4 0-2 Amendment No. 67

LCA 151 Rev. 1 Page 5 of 27 (INTENTIONALLY DELETED)

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LCA 151, R^v,1 Page 14 of 27 (INTENTIONALLY DELETED)

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TROJAN-UNIT 1:

3/4 7-31 Amendment No. 18, 39,,pg, 77--

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i LCA 151, Rev.1 Page 18 of 27 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 personnel and is consistent with the recommendations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release", February 1975.

3/4.3.3.7 DELETED l

l 3/4.3.3.8 DEC00PLE SWITCHES OPERABILITY of the decouple switches ensures that the control cables passing through the cable spreading-room (CSR) and other Plant areas to certain equipment required for safe shutdown of the Plant will be isolated and local-operation of the equipment can be achieved.

In the event that a portion of the decouple switches becomes inoperable, a fire watch will be established in the CSR until the inoperable equipment is restored to OPERABILITY.

3/4.3.3.9 ACCIDENT MONITORING INSTRUNENTATION The OPERABILITY of the accident monitoring instrumentation ensures that suf ficient 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.

- NURf 3- 037, " Clarification of TMI Action Plan Requirements".

TROJAN-UNIT 1 8 3/4 3-3 Amendment No. 50, 56, 93

4 LCA 151, Rev.1 Page 19 of 27 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 habi ble for operations personnel during and following all credible accident conditions.

The OPERABILITY of 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.

System operability can be affected by ECC3 recirculation leakage and Containment leakage should the conditions assumed in FSAR Section 15.6.5.6 be exceeded.

The OPERABILITY of _ this system in conjunction with control room design provisions is also based on limiting the toxic gas exposure to centrol room personnel consistent with the FSAR design basis and Regulatory Guide 1.95.

Recirculation mode of operation is defined as operation of the control room emergency ventilation system with the outside air dampers closed.

in the event of a radiation release while operating the system in the recirculation mode of operation, the system is operated in the pressurization mode of operation by opening the outside air dampers.

Operation of the system in this manner meets the intent of this specification and satisfies the FSAR design basis and requirements of GDC 19.

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 permissible body burden for total body irradiation if the source material is inhaled or ingested.

3/4.7.8 DELETED i

TROJAN-UNIT 1 B 3/4 7-5 Amendment No. 78,25,757

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4 LCA 151, Rev.1 Page 21 of 27 PLANT SYSTEMS L

BASES 3/4.7.9 DELETED l

4 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 effect on any safety-6 related-system.

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

LCA 151, Rev.1 Page 22 of 27 ADMINISTRATIVE CONTROLS 6.2.2 FACILITY STAFF The Facility organization shall be subject to the following:

a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

The minimum shift crew necessary for safe shutdown is five, b.

At least one licensed Operator shall be in the control room when fuel is in the reactor, c.

At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips, d.

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

All CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

TROJAN-UNIT 1 6-la Amendment No.

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LCA 151, Rev. 1 Page 23 of 27 ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF 00ALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.I-1971 for comparable positions, except for (1) the Radiation Protection Branch Manager 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 1

transients and accidents.

6.3.2 The Operations Branch Manager shall hold a Senior Reactor Operator License.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staf f shall be maintained under the direction of a 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 Plant General-Manager on all matters related to nuclear safety.

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TROJAN-UNIT 1 6-5 AmendmentNo.ll5 56, 7#6, Tif

LCA 151, Rev.1 Attachment l' Page 24 of 27 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 assessnent of the safety significance of each violation.

f.

Review of those REPORTABLE EVENTS.

g.

Review of facility operations to detect potential safety hazards.

h.

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

1.

Review of the Plant Security Plan and implementing procedures.

J.

Review of the Emergency Plan and implementing procedures.

k.

Review of the Offsite 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 6.5.1.7 The Plant Review Board shall:

Recommend to the Plant General Manager written approval or disap-a.

proval 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 Plant General Manager; however, the Plant General Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

r TROJAN-UNIT 1 6-7 Amendment No. #2, 52, 88, 97, 99, 728, 735, 185

LCA 151, Rev. 1 Page 25 of 27 ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cogni-zance of the TN08.

These audits shall encompass:

a.

The confornance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months, b.

The performance, training and qualifications of the facility staf f at least once per 12 months.

c.

The results of actions taken to correct deficiencies occurring in f acility equipment, structures, systems or method of opera-tion that affect nuclear safety at least once per 6 months.

d.

The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months, e.

The Facility Emergency Plan and implementing procedures at least once per 12 months.

f.

The Facility Security Plan and implementing procedures at least once per 12 months.

g.

Any other area of facility operation considered appropriate by the TNOB or the Vice President Nuclear, h.

The Facility Fire Protection Plan and implementing procedures l

at least once per 24 months.

i.

An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.

j.

An inspection and audit of the fire protection and loss preven-tion program shall be performed by a qualified outside fire consultant at least once per 36 months.

AUTHORITY 6.5.2.9 The TN08 shall report to and advise the Vice President Nuclear on those areas of responsibility specified in Sections-6.5.2.7 and 6.5.2.8.

TROJAN-UNIT 1 6-11 Amendment No. 18,52,79,92,97

LCA 151, R@v.1 Page 26 of 27 ADMINISTRATIVE CONTROLS 6.7 _ SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The facility shall be placed in at least HOT STANDBY within one hour, b.

The Safety Limit violation shall be reported to the Commission, the Vice President Nuclear and to the TNOB within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PRB.

This report shall describe (1) applicable circumstances preceding the viola-tion, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Commission, the TN0B and the Vice President Nuclear within 14 days of the violation.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November 1972.

b.

Refueling operations, c.

Surveillance and test activities of safety related equipment.

d.

Security Plan implementation, e.

Radiological Emergency Plan implementation.

f.

Fire Protection Plan implementation.

l g.

Offsite Dose Calculation Manual implementation.

h.

Radiological effluent monitoring.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed and approved prior to implementation as set forth in Specification 6.5.3.

TROJAN-UNIT 1 6-13 Amendment No. #2, 52, 97, 99, 706, 728 135 1

LCA 151, Rev. 1 Page 27 of 27 ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 The originals of Special Reports shall be submitted to the Document Control Desk with copies sent to the Regional Administrator, NRC Region V, and the Resident Inspector 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 Meteorological Monitoring Instrumentation, Specification I

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.

l 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.

Deleted.

h.

Deleted.

i.

Accident Nonitoring Instrumentation, Specification 3.3.3.9.

j.

Control Building Modification Connection Bolts, Specifications 3.7.11 and 4.7.11.2.

k.

Overpressure Protection System, Specification 3.4.9.3.

1.

Reactor Coolant Loop, Specification 3.4.1.4.

m.

Deleted.

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n.

Instrumentation Decouple Switches, Specification 3.3.3.8.

o.

Containment Structural Integrity, Specification 4.6.1,6.4.

p.

Radioactive Effluents, Specifications 3.11.1.2, 3.11.2.2, 3.11.2.3 and 3.11.2.5.

q, Radiological Environmental Monitoring, Specifications 3.12.1 and 3.12.2.

r.

Radioactive Gaseous Process and Effluent Monitoring Instrumentation.

Specification 3.3.3.11.

s.

Radiation Monitoring Instrumentation, Specification 3.3.3.1.

i TROJAN-UNIT 1 6-17 Amendment No. 56, 78, 78, 87, 92, 77, 77, 99, 105, 142

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LCA 151, Rev.1 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

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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 meximum time interval between samples of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Prior to final conversion to the modified rack design, fuel may be stored, as needed, in either the new storage racks described in Technical A

Specification 5.6.1.2 or in the existing storage racks

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(or both). The existing racks are designed and shall be maintained with a nominal 13.3-inch center-to-center distance between fuel assemblies placed in the storage racks to ensure a K rr of less than or equal e

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) Ouality Assurance Except for.the installation 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 wnich a Quality Assurance Program is applicable shall, after the date of issue of this license, be conducted in accordance with the Nuclear A

Quality Assurance Program..

AlA i

Amendment No. 22, 34, 88, 110 Date of Issuance:

J

LCA 151, Rev.1 Page 2 of 2

-Sa-

2. (cont.)

C. (cont.)

(8)

Portland General Electric shall implement and maintain in effect all provisions of the approved fire protection program as described in PGE-1012. " Trojan l

Nuclear Plant Fire Protection Plan", and as approved in the SERs dated March 9,1978; March 25,1980; October 6, 1980; December 14,1982; July 8,1983; i

March 5, 1984; October 15, 1985; and November 12, 1987 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval 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, I

(9)

Primary Shieldina Modification The licensee is authorized to modify the primary shielding design as described in PGE letter dated

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April 22, 1977, as supplemented and amended by

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letters dated September 22 and 23, 1977, December 22, 1977, January 4 and 24, 1978, March 20, and April 4,1978.

(10)

(This paragraph intentionally deleted.)

(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 subsequent cycles provided:

(a) The fuel with extra-grid straps is used only in the 8 corner locations where previously used, and (b) No fresh fuel modified as above is introduced into the core.

(12)

(This paragraph intentionally deleted.)

(13)

(This paragraph intentionally deleted.)

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Amendment No. 22, 29, 67, 94, 106 Date of Issuance:

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Excerpt f rom Trojan Nuclear Plant Final Safety Analysis Report LCA 151, Rev.1 Page 1 of 1 9.5 OTHER AUXILIARY SYSTEMS 9.5.1 FIRE PROTECTION PROGRAM Fire Protection is provided for the Plant as described in the Topical Report, ' Trojan Nuclear Fire Protection Plan", PGE-1012.

9.5.2 COMMUNICATION SYSTEMS The communication systems include internal inplant and external l

communications designed to provide convenient and effective operational communications among various Plant locations, and between the Plant and locations external to the Plant.

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

(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.

1 (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 supply with the inplant telephone system.

(3) A commercial telephone system provides direct dialing to outside I

local and long-distance areas.

It provides direct dialing between stations throughout the Plant area.

J Amendment 1 (July 1986)

A

'LCA 151, R;v. 1 page 1 of 16 8.0 OPERATING SPECIFICATIONS 8.1 FIRE PROTECTION INSTRUMENTATION 8.1.1 LIMITING CONDITION FOR OPERATION As a minimum, the fire protection instrumentation for each fire detection

-zone shown in Table 8-1 shall be OPERABLE.

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

L Action: With one or more of the fire detection instrument (s) shown'in Table 8-1 inoperable:

(1) Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour unless the instrument (s) is located inside the Contain-ment, then inspect the Containment at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

(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 smoke detection instruments shall be demon-strated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.

Smoke detectors which are not accessible during Plant operation shall be demonstrated OPERABLE by the perfonmance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

l l

One or more of the thermal detection instruments from each fire detector l~

zone shall be tested at least annually and different detectors shall be i.

selected for each test. Within five years, each detector shall have been tested.

8.1-1 l

(October 1988)

4 4

LCA 151 R;v. 1 i

page 2 of 16 The NFPA Code 72D Class B supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months, 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 j

stages. Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall q

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.

l 1

5858k Amendment 4 8.1-2 (October 1988) 1

.c LCA 151. R:v. 1 page 3 of 16 8.2 FIRE SUPPRESSION WATER SYSTEM 8.2.1 LIMITING CONDITION FOR OPERATION The fire suppression water system shall be OPERABLE with:

(1) One 2000-gpm fire pump capable cf being powered by an OPERABLE diesel engine, (2) One 2000-gpm motor-driven fire pump capable of being powered by an i

OPERABLE power supply, and (3) An OPERABLE flow path capable of taking suction from the Columbia f

River and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard' I

hydrant curb valves'and the first valve ahead of the water flow alarm device on each sprinkler / spray / deluge or hose standpipe riser required to be OPERABLE per Sections 8.3.1 and 8.4.1.

Applicability: At all times.

Action:

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

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

(a) Establish a backup fire suppression water system within' 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

8.2-1 Amendment 5 (July 1989)

I

l l

h LCA 151, R;v. 1 Page 4 of 16 8.2.2 SURVEILLANCE REQUIREMENTS i

The fire suppression water system shall be demonstrated OPERABLE:

(1) At least once per 31 days on a STAGGERED TEST BASIS by starting each pump and operating it_for at least 15 minutes.

(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.

4 (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 test which includes simulated automatic actuation of the system throughout its operating sequence, and:

(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 gpm at a system head of 125 psis, (c) Cycling each valve in the flow path that is 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 5 8.2-2 (July 1989)

LCA 151 R;v. l' page 5 of 16 (6) At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, leth Edition, published by the National Fire Protection Association.

The fire pump diesel engine shall be demonstrated OPERABLE:

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

(a) The fuel storage tank contains at least 200 gallons of fuel, and i

(b) The diesel starts from ambient conditions and operates for at least 20 minutes.

]

(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 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 l

inspection in accordance with procedures. prepared in conjunc-tion with its manufacturer's recommendations for the class of service, t

The fire pump diesel starting 24-volt battery bank and charger shall be l

demonstrated OPERABLE:

i-(1) At least once per 31. days by verifying that:

l l

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

(b) The overall battery voltage is 124 volts.

8.2-3 Amendment 5 l

(July 1989) l l

-...-..L-.-A--.--- ---.

4 I

LCA 151, Riv. 1 Page 6 of 16 (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, Light, free of corrosion and coated with anti-corrosion material.

8.2.3 BASES The OPERABILITY 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 fire i

protection program.

l l

In the event that portions of the fire suppression systems are inoperable, l

alternate backup fire-fighting equipment is required to be made available

~

l in the affected areas until the inoperable equipment is restored to service.

l i

Amendment 5 8.2-4 l

(July 1989) l t

I

LCA 151. Rzv. 1 page 7 of 16 8.3 SPRAY. SPRINKLER. AND/OR DELUGE SYSTEMS 8.3.1 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, I

(5) Cable spreading room, 1

(6) Service water booster pump area, and (7) Component cooling water pump area.

Applicability: 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 deluge systems incperable, establish a continuous fire watch with backup fire suppression equipment for the-unprotected area (s) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

/

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

8.3-1 Amendment 5 (July 1989) i 1

.-~

9-LCA 151, R:v. 1 Page 8 of 16 8.3.2 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..

J (2) At least once per 18 months:

(s) By performing system functional tests (including simulated automatic actuation of the system) to:

(1) Verify that the automatic valves in the flow path actuate to their correct positions on a test signal, and (ii) Cycle each valve in the flow path that is not testable during Plant operation through at least one complete cycle of full-travel.

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

(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 unobstructed.

Amendment 5 8.3-2 (July 1989)

LCA 151, R;v. I' Page 9 of 16 8.4 FIRE HOSE STATIONS 8.4.1 LIMITING CONDITIONS FOR OPERATION The fire hose stations shown in Table 8-2 shall be OPERABLE.

Applicability: 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 stations shown in Table 8-2 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE hose station within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

(2) The provis3ons of TTS 3.0.3 and 3.0.4 are not applicable.

8.4.2 SURVEILLANCE REOUIREMENTS Each of the fire hose stations shown in Table 8-2 shall be demonstrated OPERABLE:

(1) At least once per 31 days by visual inspection of the station to j

assure all required equipment is at the station.

Fire hose stations which are not accessible during Plant operation shall be inspected during each cold shutdown exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 31 days.

(2) At least once per 18 months by:

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

Inspecting all gaskets and replacing any degraded gaskets in the couplings.

8.4-1 Amendment 5 (July 1989)

LCA 151.-R::v. 1 Page 10 of 16 (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 psig greater than the maximum pressure available at that hose station.

i

-i i

1 Amendment 5 8.4-2 (July 1989)

I

s a

's LCA 151, R;v. 1 Attachment A Page 11 of 76 8.5 PENETRATION FIRE BARRIERS

?

8.5.1 LIMITING CONDITIONS FOR OPERATION All 3-hr penetration fire barriers protecting safety-related areas shall be functional.

Applicability: At all times.

Action:

(1) With one or more of the above-required penetration fire barriers nonfunctional in areas with a combustible loading >l Ib/sq ft equivalent wood, provide either a continuous fire watch on at i

least one side of the affected penetration within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or verify the OPERABILITY of fire detectors on at least one side of the nonfunctional fire barrier and establish an hourly fire watch patrol.

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

8.5.2 SURVEILLANCE REQUIREMENTS Each of the above-required penetration fire barriers shall be verified to be functional:

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

(2) Prior to returning a penetration fire barrier to functional status following repairs or maintenance byfperformance of a visual inspection of the affected penetration fire barrier (s).

8.5.3 BASES The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjccent 8.5-1 Amendment 5 (July 1989)

LCA 151, R;v. 1 j

Page 12 of 16 3

i

- portions of the facility. This design feature minimizes the possibility 4

- 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 (11 lb/sq ft equivalent wood), credit is allowed for installed detec-j 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 barrier is installed, an installed detection system is provided, and an hourly fire patrol is _ established, or a continuous fire watch is required.

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

l l

r Amendment 5 8.5-2 (July 1989)

LCA 151. R;v. 1 page 13 of 16 3

8.6 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 j

crew necessary for safe shutdown of the unit or any personnel required for i

other essential functions during a fire emergency. Fire Brigade i

composition may be lecs than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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.

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 NFPA Code-1975, except for Fire Brigade training sessions which shall be held at least quarterly.

8.6-1 Amendment 5 (July 1989)

+

4 LCA 151, R;v. 1 Page 14 of 16 TABLE 8-1

]

FIRE DETECTION INSTRUMENTS Page'1 of 2 1

INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE

1 Smoke Thermal 1.

Control Room-a.

KZIU 6-#1, Zone 1 2

b.

KZIU 6-#1,-Zone 2 2

c.

KZIU 6-#1, Zone 3 1

d.

KZIU 6-#1, Zone 4 1

2.

Cable Spreading Room a.

KZIU 6-#2, Zone 1 2

b.

KZIU 6-#2 Zone 2 2

3 c.

KZIU 6-#2, Zone 3 2

d.

KZIU 6-#2, Zone 4 2

3.

Electrical Penetration Area a.

KZIU 6-#5, Zone 1 2

b.

KZIU 6-#5, Zone 4 1

4.

Station Battery Rooms a.

Train A Elevation 65 ft KZIU 6-#6, Zone 2 1

b.

Train B Elevation 65 ft KZIU 6-#6, Zone 1 1

5.

Switchgear Room J

a.

Train B Elevation 61 ft KZIU 6-#6, Zone 3 5'

b.

Train A Elevation 65 ft i

]

KZIU 6-#6, Zone 4 2

c.

Train A Elevation 69 ft (1) KZIU 6-#7, Zone 1 5

(2) KZIU 6-#7, Zone 2 5

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

Amendment 4 (October 1988)

Y

(

LCA 151 R3v. 11 Page 15 of 16 TABLE 8-1 Page 2 of 2 INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE

6.

Service Water Pt.

Area Smoke Thermal a.

KZIU 6-#8, Zone 1 1

b.

KZIU 6 #8, Zone 2 1

c.

KZIU 6-#8, Zone 3 1

7.

Service Water Booster Pump Area i

a.

KZIU 6-#9, Zone 1 1

I b.

KZIU 6-#9, Zone 4 i

i 8.

Component Cooling Water Pump Area a.

KZIU 6-#9, Zone 2 1

b.

KZIU 6-#9, Zone 3 2

i l

9.

Residual Heat Removal and Safety Injection Pump Rooms i

a.

EZIU 6-#13, Zone 1 2

b.

KZIU 6-#13, Zone 2 4

.l 1

i 10.

Centrifugal Charging and Positive Displacement Pump Rooms a.

KZIU 6-#14.. Zone 2 1

l b.

KZIU 6-#14, Zone 3 2

i 11.

Emergency Diesel Generator Rooms a.

KZIU 6-#15, Zone 1 3

b.

KZIU 6-#15, Zone 2 2

12. -Auxiliary Feedwater Pump Rooms i

a.

KZIU 6-#16, Zond L

-2 b.

KZIU 6-#16, Zone 2 1

l c.

KZIU 6-#16, Zone 3 1

~ l 13.

Containment

.l a.

KZIU 6-#19, Zone 3 2

i

The fire detection instruments located within the Containment 4

are not required to be OPERABLE during the performance of Type-A Containment leakage Rate Tests.

Amendment 4 (September 1988)

4 LCA 151 Rev. 1 Page 16 of 16 TABLE S-2 FIRE HOSE STATIONS l

Location Elevation Hose Station 1.

Auxiliary Building 5 ft HS-34 2.

Auxiliary Building 25 ft HS-33 3.

Auxiliary Building 45 ft HS-19, 38 4.

Auxiliary Building 63 ft HS-29 5.

Auxiliary Building 77 ft HS-28 6.

Turbine Building 45 f t HS-3, 5 7.

Turblne Building 69 ft HS-27 8.

Turbint. Building 93 ft HS-15

.i 9.

Control Building 63 ft HS-40 10.

Control Building 77 ft HS-26 11.

Containment 45 f t CHS-A "' I I

12.

Containment 93 f t CHS-B

13.

Containment 93 ft CHS-C "'

r la) From Demineralized Water System

[b] Inspected During COLD ShliTDOWN j

i i

t' Amendment 3 5

(July 1987)

LCA 151. Rsv. 1 i

Attochmsnt 5 Page 1 of 27 i

d

.I.N),[,[

(1MITING CONDITIONS FOR OPERATION AND SURVElllANCE REOUIREMENTS SECTION Pace 3/4.2 POWER DISTRIBUTION llMITS 3/4.2.1 Axial Flux Difference................... 3/42-1 3/4.2.2 Heat Flux Hot Channel Factor............... 3/4 2-5 3/4.2.3 RCS Flowrate and Fa.................... 3/4 2 8 Qua d ra n t Powe r T i l t Ra t i o.............. '...3/4 2 10 t

3/4.2.4 3/4 2-12 3/4.2.5 DNB Parameters.....

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.

3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM

[

INSTRUMENTATION..

3/4 3-13 l A3h

(

3/4.3.3 MONit0 RING INSTRUMENTATION i

Radiation Monitoring Instrumentation........... 3/4 3-33 I

Movable incere Detectors................. 3/4 3-37 l

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 re[eiestien'as;i.......;e;i.;.m.

.v..........

3/4 Decouple Switches...................

3/4 3-50 Accident Monitoring Instrumentation............ 3/4 3-51 Radioactive Liquid Effluent Instrumentation.

3/4 3-54 Radioactive Gaseous Process and Effluent Monitoring instrumentation................ 3/4 3-59 50 Detecti n Systems................... 3/4 3 68 2

3/a.a REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS.................. 3/44-1 y= Amendment No. #5, 55, 78. 99,165. ///

TROJAN-UNIT 1 IV April 22,1 ^07-1 l

l

LCA 151, Rev. 1 s

Page 2 of 27 I

INDEX i

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

SECTION PAGE l

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 YENTILATION SYSTEM.............

3/4 7-18 3/4.7.7 SEALED SOURCE CONTAMINATION...........................

3/4 7-21 4 oc t.mro

"~

3/4.7.8 fitt-St* PRE $tiCN-$YSTEM we. a Tir; h ;;r;;;iO h t0r Sy t O -8. C................ 3/4 7 h

- SY.$ $d er ti;ter..." d........................... 3/4 7-27 HN"E : a u chem................................

.c txutTro 3/4.7.9 FEidiMTMPtRt-9RRft!tR$ rff7........................ 3/4 7 31 3/4.7.10 SNU B B ERS.............................................. 3 / 4 7 - 3 2 h,)

3/4.7.11 CONTROL BUILDING MODIFICATION CONNECTION BOLTS........

3/4 7-38 Q / ok 3

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES O p e ra t i n g............................................. 3 / 4 8-1 S h u t d own.............................................. 3 / 4 8 - 5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating.........................

3/4 8-6 A.C. Distribution - Shutdown..........................

3/4 8-7 D.C. Distribution - Operating.........................

3/4 S-8 D.C. Distribution - Shutdown..........................

3/4 8-10 3/4.8.3 UNDERVOLTAGE PROTECTION 4.16 kV Emergency Bus Undervoltage Protection.........

3/4 8-11 TROJAN - UNIT 1 VII Amendment No. JB, 37.-47,50,57,M/

-Februeg ', IMV

LCA 151. R2v. 1 l

I At t achm nt 5 1,

Page 3 of 27 i

INDEX BASES SECTION PAGE l

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........ B 3/4 7 3 3/4.7.3 COMPONENT COOLING WATER SYSTEM......................... B 3/4 7-4 3/4.7.4 SE RVICE WATE R SYSTEM................................... B 3/ 4 7 4,

3/4.7.5 UL T I MAT E H EAT S I N K..................................... B 3/ 4 7 4 3/4.7.6 CONTROL ROOM VENTILATION SYSTEM........................ B 3/4 7-5 3/4.7.7 S EALED SOURCE CONTAMINATION............................ B 3/4 7 5 3/4. y pr u rtp q 7.8 TIRE SUPPRttSION 575TEF. M............................ B 3/4 7-5

% f=>

btLLTro %

3/4. 7. 9---PfMETRAYl0N-fi RE OARRI E RS............................. B 3/4 7-6 3/4.7.10 SNUBBERS............................................... B 3/4 7 6 l ict v'

3/4.7.11 CONTROL BUILDING MODIFICATION CONNECTION BOLTS......... B 3/4 7-8 3/4.8 ELECTRICAL 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 OE CAY T I ME............................................. B 3/ 4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS...................... B 3/4 9-1 3/4.9.5 CO MMU N I CAT I ON S......................................... B 3 / 4 9-1 TROJAN - UNIT 1 XI!!

AmendmentNo.78,37,f7.jf/

N

. m m.

r o.

iro

LCA 151, Rev. I j

Attochment 5 Page 4 of 27 J

3/a,0 APPtiCAPitiTY SUpyttttANCE eEOU1REwENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERA-i T10NAL MODES or other conditions specified f or individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Recuirement.

i 4.0.2 tach Surveillance Recuirement 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 l A l *'

surveillance interval.

4.0.3 Performance of a Surveillance Recuirement within the specified time interval shall constitute compliance with OPERABILITY recuirements for a Limiting Condition for Operation and associated AC110N statements unless otherwise required by the specification. Surveillance Recuire-ments do not have to be performed on inoperable ecuipment.

4.0.4 Entry into an OPERATIONAL. MODE or other specified applicability condition shall not be made unless the Surveillance Recuirement(s)

(

associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

The provisions of Specification 4.0.4 are not applicable to the perform-ance of surveillance activities associated with fire protection tech-l nical specifications 4.3.3.7.1, a.3.3.7.2, 4.7.8.1.1, a.7.8.1.2.

4.7.8.1.3, 4.7.8.3 and 4.7.9 untti the completion of the initial sur-weillance interval associated with each specification, j

4.0.5 Surveillance Requirements Sr inservice inspection and testing of l

l ASME Code Class 1, 2 and 3 components shall be applicable as follows:

a.

Inservice inspection of ASME Code Class 1, 2 and 3 comoo-i nents and inservice testing of ASME Code Class 1, 2 and 3 pumpe and valves shall be performed in accordance with

.sSection XI of the ASME Soiler and Pressure Vessel Code

/g' and applicable Addenda as required by 10 CFR 50. Sec-tion 50.55a(g), except where specific written relief has been granted by the Connission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

r g menc *nt No. //

TROJAN-UNIT 1 3/4 0-2 A

May-8 r1981-QNRC-Corteetien-1 steer (dated-June-S-tten k

l LCA 151, Rev. 1 l

Page 5 of 27 j

&-~ x_

f TNSTRUMENTATION

\\

FIRE PROTECTION INSTRUMENTATION C

.LIMITING CONDITION FOR OPERATION

}

l

!3.3.3.7 As a minimum, the fire protection instrumentation for each fire

! detection zone shown in Table 3.3-10 shall be OPERABLE.

5APPLICABILITY: Whenever equipment in that fire detection Zone is i

{equiredtobeOPERA8tE.

l j

jM: With one or more of the fire detection' instrument (s) shown in Table 3.3-10 inoperable:

I a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect I

the zone (s) with the inoperable instrument (s) at least once per hour unless the instrument (s) is located inside the Containment, then inspect the Containment at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , and b.

Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other report required by

/\\

Specification 6.6.1 or 10 CFR 50.72, prepare and submit a

/97 \\

Special Report to the Consnission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plins and schedule for restoring the instrument (s) to OPERA 8LE status.

c.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

l}yRVEILLANCE REOUTREMENTS

\\

i 4.3.3.7.1 Each of the above required fire protection instruments shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.

Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

j f a s.3.3.7. 2

+4 The NFPA Code 72D Class 8 supervised circuits supervision sociated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

\\

C (NutJTutjAttg> getg7to}

(

TROJAN-UNIT 1 3/4 3-48 AmendmentNo.75,if,//

Ntobe&S0r-1984-i

-~~,

,n.

1.CA 151. Rev. 1 j

l At t achment 5 j

Page 6 of 27

- ~ ~ ~

/

N,' x TABLE 3.3-10 nar ocnerteN rNsnuMorts

's.-

N i

!Nsnusti LotATION MINIMUM INsnUMorT3 OPERAstte l

Smoke

[

s 1.

Control Room MU 6-100 1

MU 6-100, Zone 1 a.

i b.

. Zone 2 2

c. MU 6-100, Zone 3 1

i d.

MU 6-100, Zone 4 1

t 7

Total 5

2.

Cable spreading Room a.

ZIU 6-dt, Zone 1 3

f b.

ZIU 642, Zone 2 3

c. ZIU 642, Zone 3 3

d.

!!U 642, Zone 4 3

1 Total 12 I

A 3.

Electrical Penetration A'rea

[

a. I!U 645, Ione 1 1

I b.

ZIU 6-45, Zone 4 1

f Total 3

,4.

Switchgear Room 4

a.

Train A Elevation 69 ft

\\

(1) ZIU 6-47, Ione 1 3

(2) I!U 647 Ione 1 3

Total 6

t

{

,. ~ ~ _

q

_j TROJAN-UNIT 1 3/4 3-49 AmendmentNo.IS,30.I[

4hber-14,198L y--.

LCA 151, Rev. 1 At.t ac hment 5 Page 7 of 27

, /

~'-

~~

x'N INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE

Smoke b.

Train B Elevation 61 ft (1

ZIU 6-#6, Zone 3 2

(2 ZIU 6-#6, Zone 4 3

Total

~T l5.

Station Battery Rooms a.

Train A Elevation 63 ft ZIU 6-#6, Zone 2 1

b.

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

6.

Containment I

a.

ZIU 6-#5, Zone 2 1

i b.

ZIU 6-#5, Zone 3 1

c.

ZIU 6.#19, Zone 3 1

t Total 7

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

~7 8.

Residual Heat Removal and Safety A

Injection Pump Rooms C'

a.

ZIU 6-#13, Zone 1 2

b.

ZIU 6-#13, Zone 2 2

Total

~T 9.

Service Water Pump Area

/

a.

ZIU 6-#8, Zone 1 1

/

b.

IIU 6-#8, Zone 2 1

/

c.

ZIU 6-#8, Zone 3 1

./

NIotal

'T

/

~ '

A TROJAN UNIT 1 3/4 3-49a Amendment No. 18, 59, 69, 92

(

August 17, 1984 HCliLIT10N4L6Y OE (ETE O

LCA 151. R3v. 1 At t ec hment 5 Page B of 27

/",_..p" N

NY INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE * \\

/

Smeke

10. Service Water Booster Pump Area a.

I!U 6 J9, Zone 1 1

i

}

b.

ZIU 6-99, Zone 4 1

Total 2

11. Centrifugal Charging Pump Rooms a.

Z!U 6-414, Zone 2 1

b.

IIU,6-41a, Zone 3 1

Total 2

l

12. Emergency Of esel Generator Acoms a.

I!U 6-415, Zone 1 2

b.

ZIU 6-d15, Zone Z Z

Total 4

13. Component Cooling Water Pump Area a.

I!U 6-49, Zone 2 1

g s

b.

ZIU 6-#9, Zone 3 1

1 l

.\\

Total 2

t*;

s l tJTE9T10NA LL Y N LGEJ

' s The fire detection instruments located within the Contairment are not recuired to be OPERABLE auring the per'ormance of Type A i

(%__

Containment leakage Rate Tests.

-j TRCLIAN. UNIT 1 3/4 3 49b A uguet-lh-it9e,18. ja //

knendment No. 78 A

b

~ - -

LCA 151 Rev. 1 Attachment S l

Pege 9 of 27 l

,,7

--~~~ ~ ~ -

~ ~.

' PLANT SYSTEMS

~~ '

~

3/4.7.8 FIRE SUPPRESSION SYSTEMS FIRE SUPPRE SION WATER SYSTEM i

LIMITING CONDITION FOR OPERATION

\\

3.7.8.1 The fire suppression water system shall be OPERABLE with:

4 a.

One 2000 gpm fire pump capable of being powered by an OPERABLE aiesel engine, b.

One 2000 gpm motor-driven fire pump capable of being powered by an OPERA 8LE power supply, and c.

An OPERABLE flow path capable of taking suction from the Columia River and transferring the water through distri-bution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves and the first valve ahead of the water flow alars device on each sprinkler / spray / deluge or hose standpipe riser required l

to be OPERABLE per Specifications 3.7.8.2 and 3.7.8.3.

' APPLICABILITY: At all times.

i

. ACTION:

s a.

With one pump inoperable, restore the inoperable equipment to OPERA 8LE status within 7 days or, in lieu of any other A

i report required by Specification 6.6.1 or 10 CFR 50.72, l /97\\ '

prepare and submit a Special Report to the Comission pursuant to Specification 6.9.2 within the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system. The provisions j'

of Specifications 3.0.3 and 3.0.4 are not applicable.

/

l b.

With the fire suppression water system otherwise inoperable:

/

1.

Establish a backup fire suppression water system

/,

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and p

2.

Submit a Special Report in accordance with

/

Specification 6.9.2:

,1 a) By telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b) Confirsed by telegraph, mailgram or facsimile

/

transmission no later than the first working day following the event, and m

~/

A AmendmentNo.JS.O7/

TROJAN-UNIT 1 3/4 7-23 s k erobe d O M ?8t. -

[pTetJ7109 ALW D( LE 7d

1 LCA 151, Rev. I At t ac hment 5 Page 10 of 27 l

l' l

l i

lPLutT tis m s N

1 l

h LIMmM6 COM0mCN FOR CPOULTICN (Ccntinuedl

\\

i l

c)

In wMting within 14 days following the event, out-l lining the action taken, tne cause of the inopers-i bility and the plans and schedule for restaring the t

system to CPEAASLE status.

SURvtII.LANc! REOUmL i.ua i

l 4.7.8.1.1 The fire suppression wter systas shall be damonstrated CPET.AILE:

j a.

At least once per 31 days on a STAGEERG TIIT LA513 by starting i

each pung and operating it for at least 15 minutes.

i n.

At least once per 31 days. by veHfying cat each valve (anual, power operated er autmaticl in the flow pac is in its carrect position.

j At least onca per 12 months by perforssance of a syrtas flush.

t.

l d.

At least onca per 12 months by cycling each tastable valve in 4

the flow path through at least one completa cycle of full travel.

\\

e.

At least onca per 18 asnths by performing a syntes functional test which includes simulated automatic ac :ation of tne syntan

/

\\

throughout its operating sequenca, and:

1.

YeHfying that each autmatic valve in the flow path actuatas ta its 'c=rrect position on a test signal,

\\

2.

VeMfying that each pump develops at least 20C0 sps at a j

systas head of 125 psig,

\\

3.

Cycling each valve in the flow path that is not tastable

'k during plant operation through at least one caplete cycle of full travel, and 4

4 YeMfying that each high pressure pas starts (sequentially) to maintain the fire suppression watar system pressure t 100 psig.

x J

~~%-

_,,,, - ~ -

t TROJAN-UNIT 1 3/4 7-24 Amendment No. [I l

tgwpT10tJ A LLy pg LQf 0

LCA 151. Rev. 1 Page 11 of 27

!'PLANTSYSTEMS N

{$UeYt1LLANCEet0VIREMEWT5(Continued)

'N I

f.

At least once per 3 years by perfoming a flow test of i

I the system in accordance with Chapter 5, Section 11 of i

the Fire Protection Handbook,14th Edition, published by the National Fire Protection Association.

4. 7. 8.1. 2 The fire pump diesel engine shall be demonstrated OPERABLE:

4.

At least once per 31 days by verifying:

l 1.

The fuel storage tank contains at least 200 gallons of fuel, and 2.

The diesel starts from ambient conditions and operates for at least 20 minutes.

4 i

b.

At least once per 92 days by verifying that a sample of i

diesel fuel f rom the f uel storage tank, obtained in accord-i ante with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM 0g75-78 when checked for I

water, viscosity and sediment.

c.

At least once per 18 months by subjecting the diesel to an inspection in accordance with procedures prepared in

/

conjunction with its manufacturer's recommendations for I

the class of service.

' 4.7.8.1.3 The fire pump diesel starting 24-volt battery bank and charger shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that:

i

\\

1.

The electrolyte level of each battery is above

/

the plates, and

/

\\

2.

The overall battery voltage is 124 volts.

/

\\

'/

x,

_._p tm W OIJALL.Y M t6WO TROJAN-UNIT 1 3/4 7-25 Amendment No. 73, 3f, 40, (2p' March-3;-1986-4

---w, e

-e---r--

y v.-

-,-e w-w y,..-

,m-g

-+w ww.

v

LCA 151 Rev.1

)

i Page 12 of 27

/

PLANT $YSTEMS

.,' N -

h A

$URVEILLANCE REQUTREMENTS (Continued) s b.

At least once per 31 days by verifying that the charging current h

is appropriate for continued service of the battery.

c.

At least once par 18 months by verifying that:

)

\\

1.

The batteries, ceil plates and battery racks show no visual i

indication of physical damage or abnormal deterioration,

\\

and 2.

TPd battery-to-battery' and terisinal connections are clean,

/

\\

tight, free of corrosion and coated with anit-corrosion

'/,

material.

~ ~ ~ _ _

/

, UTt f&n Oh)AL(..Y OE ggg g l

l l

l TROJAN-UNIT 1 3/4 7-26 % Amendment No. 78, /f August-17 -190 b I

T l

~

LCA 151. Rev. 1 At t ac hment 5 Page 13 of 27 PLANT $YSTEMS N

/

N SPRAY. $PRINKLER. AND/0R DELUGE SYSTEMS

\\

LIMITING CONDITION FOR OPERATION

\\

3.7.8.2 The following spray, sprinkler, and/or deluge systems shall be

\\

OPERABLE:

ii 4.

Emergency diesel generator roms, lI b.

Auxiliary feedwater pump room.

\\

c.

Electrical penetration areas, I

d.

Diesel fire pump room, e.

Cable spreading room, i

f.

Service water booster pump area, and k

g.

Component cooling water pump area.

{

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

ACTION:

I a.

With one or more of the above required spray, sprinkler, and/or

(

deluge systems inoperable, establish a continuous. fire watch with

\\

backup fire suppression equipment for the unprotected area (s) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; restore the system to OPERABLE status within 14 days g

or, in lieu of any other report required by Specification 6.6.1 or 10 CFR 50.72, prepare and submit a Special Report to the Comission p'

pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability, and the plans and

/

schedule for restoring the system to OPERABLE status, j

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

[

SURVEILLANCE REQUIREMENTS 4.7.8.2 Each of the above required spray, sprinkler, and/or deluge systems shall be demonstrated OPERABLE:

/

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, b.

At least once per 18 months:

1.

By performing system functional tests (. including simulated automaticactuationofthesystem)to-

/

a)

Verify that the automatic valves in the flow path actuate,'

t N

to their correct positions on a test signal, and _/

^

TROJAN. UNIT 1 3/4 7-27 AmendmentNo.78,$9,#fe//

sdOcteber-30rl?Nr h NTt em c0 ALW (EtATE D

LCA 151. Rev. 1 At t ac hment 5 Page 14 of 27

(

~. ~. -

' PLANT SYSTEMS N-s N

$URVEILLANCE REQUIREMENTS (Continued)

\\

l b)

Cycle each valve in the flow path that is not lA l

testable during plant operation through at least one complete cycle of full travel.

2.

By inspection of the spray headers to verify their integrity, and 3.

By inspection of each nozzle to verify no blockage.

At least once per 3 years by performing an air flow test through c.

each open head spray /sprinklet header and verifying each open s

head spray / sprinkler nozzle is unobstructed.

~ _ _. _ _

_y/

l WhfTlOM A Lk M LETE.D TROJAN-UNIT 1 3/4 7-28 AmendmentNo.18,//

U August-itr-ite4~

(

- - - ' ~ - - -

LCA l$1. Rev. 1 Page l$ of 27

( N -

~'N PLANT SYSTEMS FIRE HOSE STATIONS h

1 (IMITINGCONDITIONSFOROPERATION h.7.8.3 The fire hose stations shown in Table 3.7-4 shall be OPERABLE.

l

\\

)

APPLICABILITY: Whenever equipment in the areas protected by the fire 16TFTUTTET is recuired to be OPERABLE.

ACTION:

1 4.

With one or more of the fire hose stations shown in Table 3.7-4 inoperable, route an additional equivalent caoacity fire hose to the unprotected area (s) from an OPERABLE hose station wihin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Restore the fire hose station to OPERABLE status within 14 days or, in lieu of any other report reovired by Specification 6.6.1 g

or 10 CFR 50.72, prepare and submit a Special Report to f

the Connission pursuant to Specification 6.9.2 within t

the next 30 days outlining the action taken, the cause

/

of the ir. operability, and plans and schedule for restoring

/

the station to OPERABLE status.

I b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

/i SURVEILLANCE REOUIREMENTS 4.7.8.3 Each of the fire hose stations shown in Table 3.7-4 shall be

/

demonstrated CPERABLE:

a.

At least once per 31 days by visual inspection of the station l

to assure all reovired ocuipment is at the ttation. Fire hose

/

stations which are not accessible during plant operation shall

/

be inspected during each cold shutdown exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l

unless perfomed in the previous 31 days.

/

1 b.

At least once per 18 months by:

j 1.

Removing the hose for insoection and re-racking, and

\\

2.

Inspecting all gaskets and replacing any degraded

/

i gaskets in the couplings.

/

i c.

At least once per 3 years by:

1.

Partially opening each hose station valve to

/

\\

verify valve OPERABILITY and no flow blockage.

'\\

2.

Conducting a hose hydrostatic test at a pressure

/

at least 50 psig greater than the maximum pressure /

\\x,available at that hose station.

t TROJAN-UNIT 1 3/4 7-29 Amendment No. 78, 36, f A). //

W tober-30;-1?8c' s

IA W W ALLY R g

l LCA 151. Rev. 1 l

At t achment 5 I

l Page 16 of 27 I

l

[

TAsLt 3.7-4 N

i l

/

\\ b

[/

\\

l FIRE N0st STATIONS V

i i

l

\\

[

l LOCATION ELEVATION N0$E STATION

\\

/

1.

Auxiliary building 5 ft 5 34 2.

Assiliary Duf1 ding 25 ft 5 33 l

3.

Aust11ary building 45ft 5 19, 34

,l 4.

Aust11ary building C ft 55 f

8. Auxiliary building 77 ft 5 28 l

4. tertise Building 48 ft E 3. 5 7.

Tuttfee lu11 ding e ft S t7

(

8.

Tertine Building 93 ft E lf 9.

Control Buildfag C ft.

mt

10. Centrol luilding 77 ft.

S ti C4.b3

11. Cantainment 45 ft CEA bj

12. Contairement g3 ft CS8(ab3

13. Contairment 95 ft CSC(e.b3 Cal Fras Dominer:112ed Water Systm 7

(b) Inspected During COLD SHUTDOWN 1

l

+

x' lWMhMJALLYOELE.Eb)

T T M1AN. UNIT 1 3/4 7 30 AmenementNo.M,//

', November-ter-1941-(

. _. ~

LCA 151. Rev. 1

' ' ~.. - -

~..... ~ ~

At t achment 5 Page 17 of 27

~~

PLANT SYSTEMS 3/4.7.9 PENETRATION FIRE BARR!!R$

\\

LIMITING CONDITIONS FCR 0PERATION x

i 3.7.9 All 3-hour penetraten fire barriers prctecting safety related areas thall be functional.

g i

b

' APPLICABILITY: At all times.

iACTION:

I With one or more cf the above required penetratien fire a.

i barriers nonfunctional in areas with a combustible loacing

(

greater than 1 lb/sq ft equivalent weed, provice either a continucus fire watch en at least one side cf the affectec 3

penetration within I hour or verify the OPERASILITY cf fire j

i detectors en at least one side of the nenfunctional fire barrier and establish an hourly fire watch patrol. Rastere the nonfunctional fire barrier penetration (s) to functional status within 7 days or, in lieu of any other report recuirec b

i

$y Specification 6.6.1 or 10 CFR 50.72, prepare and submit a l

i pecial Report to the Consnission pursuant to Specification i

6.9.2 within the next 30 days outlining the action taken, the cause of the nonfunctional penetrations and plans and schedule for restering the fire barrier penetration (s) to functional status.

b.

The provisions cf Specifications 3.0 3 anc 3.0.4 are not applicable.

I

_SURVE!LLANCE REOUIREMENTS 1

4.7.9 Each cf the above mquired penetration fire barriers shall be verified to be functional:

\\

At least once per 18 menths, by a visual inspection.

a.

/

\\

b.

Prior to rtturning a penetration fire barrier to fonctional

/

status following repairs or maintenance by performance of a x

f

\\

visual inspection of the affected ;enetratien fire terrier (s).

N, j

l N.~

t 9Tt:NT)04 4i L T OELfi~({}

TROJAN-UNIT 1 3/4 7-31 V-October-40r4MWAmen6entNo,72,D,A

LCA l$1. Rev. 1 Attachment $

Page 18 of 27 Ut!TRt.PENTtTION 1A!E3 3/a.3.3.6 CHLOR!NE CETEC ION $Y! p!

The CPERASILITr of the chlorine detecticn system ensures that sufficien-capability is available, to premetly detact and initiata protective action in the event of an accidarttal chierine release. This capability is ntuired to protect c:ntrol roca perscanal and is censistent with the ree:arendatient of Regulatcry Guide 1.95, 'Pntaction of Nuclear Power Plant Conti:1 Acom Operators Against an Accidental Chierine Release," Febr.iar/1975.

tic o t' 'Tr t> 4 3/a.3. 3. 7 P95-DETTCTEM-t%573U8ENTtT4 CN-J4-0PERAEILITY cf the fire detection it trumentatien ensures that adecIDf

, warning capability is availatle for the premst detection of fires. This

\\

capability is neuired in ordar to detect and 1ccata fires in their early

\\

j stages. Prempt detecticn of fires will reduce the ;ctantial f:r c cage ::

safety related ecut; ment anc is an integrai element in the ever:11 facility fire protection pregram.

1 In the event that a portion of the fire detecticn ir.straentati:n is inoperahle, the establishment of frequent firs patrels in the affected a ea:

ts requind to pesvice datection capabiitty until the incperable instrmen-tapen is restered to CPE'44ILITt.

3/a.3.3.8 CECOUPLI rd770F!!

E CFEME!LITr cf the dec:::le rdtthes ir. C mle n ::d4p_jt3M

,a recuired f r safe shutdewn of the Plant wit 1 te isolated and 1 cal _:tcu.:me.t~,,me ent:res that the c:ntral cables passing thrcugn theGERYt: _ car 341n cf the etuipment can te acaf eved.

In the event that a ;crtien of tne: erat *:n]c.% P""1 decaucle switches tec:mes ineparable, a fire wat:n will te estat11snee in weMn),a the CSR until the ineperable equipment is reat: red t: OFERAEILI'"f.

n 3/1.3.3.9 AC"*0EN* M Nf CRING IMSTRL?ENTATT*N The CFERASILITf of the accidant monit: ring instr.:nentatien ensures that sufftetent infermatten is availatie en selectac plant para.ete-: t: menit:r and assess these variabies during and felicwing an ac:ident. Tnis ca:a:il-ity is ::nsistent with the rec:nnancatica cf NUREG-0578, 'TM!-2 Less:.s Learned Task FoMe Status Re:crt and Short-Tern Rec:mmendatices" anc NUREG-0737, "Clarificatien cf TMI Actica Plan Requirteents."

l/d i

i i

TRCJAN-UNIT 1 3 3/t 2-3 MercmentNo.!D,Ji,M.

'teneses4r-ui-

LCA 151. Rev. 1 PLAWT SYSTEMS J

BASES i

I 3/a.7.6 CONTR0'. 200M VENTIL ATION 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 I

personnel during and following all credible accident conditions.

The OPERABILITY of 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 Et M1 Design b

i Criteria 1g of Appendix 'A',10 CFR 50.

System operability can be affacted

/

1 by ECCS recirculation leakage and Containment leakage should the conditions

[

\\

assumed in FSAR Section 15.6.5.6 be 6xceeded.

i I

The OPERABILITY of this system in conjunction with control room design j

i l

provisions is also based on limiting the toxic gas exposcre to control

\\

room personnel consistent with the FSAR design basis and Regulatory

{

Guide 1.95.

i 15.~

Recirculation mode of operation is defined as operation of the control room emergency ventilation system with the outside air dampers closed.

In the event of a radiation release while operating the system in the recirevlation mode of operation, the system is operated in the l

/

I pressurization mode of operation by opening the outside air dampers.

/

Operation of the system in this manner meets the intent of this I

/

specification and satisfies the FSAR design basis and requirements k

j-of 60C 19.

\\

3 /4,7. 7 SEALED SOURCE CONTAMINATION l

l The limitations on sealed source removable contamination ensure that i

the total body or individual organ irrad W on does not exceed allowable limits in the event of ingestion or inhalstion of the source material.

i The limitations on removable contamination for sources. requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.

Leake9e of sources excluded from the requirements of this specification represent less than one maximum permissible body burden for total body irradiation if the source material is inhaled or ingested.

DtLtTtb1 3/4.7,8 f!RE-SUPetES$10N-$YSTtM O

/

TheOPERABILITYofthefiresuppressionsystemsensuresthatadesateN

~

[ 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, l

sprinklers and fire hose stations. The collective capability of the fire

/

tsuppression systems is adequate to minimite potential damage to safety frelatedequipmentandisamajorelementinthefacilityfireprotectionj/

(.

p[ogram.

TRO.1AN-UNIT 1 3 3/4 7-5 AmendmentNo.75,28,%/

O, Nay-15,--1999-

LCA 151. Rev. I l

1 1

Page 20 of 27 PLANT SYSTEMS BASES fCentinued)

/

In the event that portions of the fire suppression systems are

[ inoperable, alternate backup fire fighting equipment is required to be i

I made available in the affected areas until the inoperable equipment is stored to service.

1 i

kcmovt.

jhis l

C O M b id t;

@A r} d-4 Ms Tec l, n i c n j

'ho r

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TROJAN-UNIT 1 8 3/4 7-5a Amendment No. 75, rg, IST(

if May 15, 1989

LCA 151 Rov. 1 1

Attachu nt 5 Pags 21 of 27 i

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PLANT SYSTEMS aAsts j

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In the event the fire suppression water system becomes inoperable, j~

j 1 mediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.

The requirement for a twenty-four hour report to the Comission provides for Prompt evaluation of i

l sion capability for the continued protection of the nuclear plai IXuntb N 3/4.7.9 PEMETAATION-FIAf-SARR!!R$"- E The funct19nal integrity of the penetration fire barriers ensures that, fires will be confined or adequately retarded from spreading to adjacent i

/

i portions of the facility.

This design feature minimites the possibility of i

a single fire rapidly involving several areas of the facility prior to detec-tion and extinguishment.

The penetration fire barriers (doors, walls, dampers, and seals) are a passive element in the facility fire protection i

program and are subject to periodic inspections.

1 j

During periods of time when the barriers are not functional, the combustible loading of the safety-related areas dictates the type of temporary i

protection to be provided.

The combustible loadings for each room in the

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~

plant are listed in Table 3-1 of PGE.1012. Trojan Nuclear Plant Fire Protec-1 tion Review. Where combustible loadin equal to 1 lb/sq ft equivalent wood), gs are considered low (less than or

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tion systems and installation of temporary fire barriers. credit is allowed for installe in addition to an hourly fire patrol, give adequate assurance that a fireEither of these could not initiate and propagate through the nonfunctional penetration barrier.

Where combustible loadings are somewhat greater (greater than 1 lb/sq ft equivalent wood) either a temporary fire barrier 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 or the fire watch patrol is required to be maintained until the barrier is restored to functional status.

3/4.7.10 SNUB 8ERS

/

rity of the reactor coolant system and all other safety-related d

maintained during and following a seismic or other event initiating dynamic loads.

Snubbers excluded from this inspection program are those installed

/\\ j; n nonsafety-related systems and then only if their failure or failure of the

, dgA/l o

l system on which they are installed would have no adverse effect on any safety-

"Jt elated system.

l r

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N AN - UNIT I B 3/4 7-6 Amendment No Jg 33, g Febroery-6r--196$-

4

LCA l$1, Rev. 1 Page 22 of 27 ADMlWISTRATIVE CONTROLS a

T e Fat y

g ration shall be subject to the following:

Each on duty shif t shall be composed of at least the a.

minimum shif t crew composition shown in Table 6.2-1.

The minimum shif t crew necessary f or safe shutdown is five, b.

At least one licensed Operator shall be in the control room when f uel is in the reactor, At least two licensed Operators shall be present in the c.

control room during reactor start-up, scheduled reactor shutdown and during recovery f rom reactor trips.

d.

An individual evalified in radiation protection procedures shall be on site when fuel is in the reactor, All CORE ALTERATIONS af ter the initial fuel loading shall e.

be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation. _ _ _ _ _

[,f.

A Fire trigade of at least 5 members shall be maintained 's onsite at all times. The Fire Brigade shall not include

/

members of the minimum shif t cr'ew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

Fire $rigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accom-modate unexpected absences of onduty members provided insnediate action is taken to restore the Fire trigade j

composition to within the minimum requirement of 5.

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' ~ ~ ~ ~

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AmendmentNo.//)f TROJAN-UNIT 1 6-la

- August-Sr19BB-d

(

LCA 151, Rev.1 Attachtnent 5 t

Page 23 of 27 ADMINISTRATIVE CONTROL $

i l

6,3 FACILITY STAFF OUALIFICATIONS

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6.3.1 Each member of the facility staf f shall meet or exceed the minimum quellfications of ANSI N18.1-1971 for comparable politions, except for (1) the Radiation Protection Branch Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8. September 1975 and (2) the Shif t 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.

6.3.2 The Operations Branch Manager shall hold a Senior Reactor Operator License, t

6,a TRAINING 6.4.1 A retraining and replacement training program for the facility

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staf f shall be maintained under the direction of a General Manager (ni and shall meet or exceed the requirements and recommendations of Section 5.5 of ANS! N18.1-1971 and Appendix

'A' of 10 CFR Part $5.

I o

6.4.2 A training program for the Fire Brigade shall be maintaine under the direction of a General Manager and shall meet or exceed 1

the requirements of Section 27 of the NFPA Code-1975, except for Fire gigade training sessions which shall be held at least quarterly, j 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 Plant General Manager on all matters related to nuclear safety.

l TROJAN-UNIT 1 6-5 Amendment No. #F. If,148. Tig.///l

-Novemw r 5, M69-C_.

- - - ^ ' ' ' -

LCA 151 Rev.1 ADMINISTRATIVE CONitots e.

investigation of all violations of the Technical Specifications

' neluding the preparation and forwarding of reports covering eve 1L;4 tion 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 those REPORTABLE EVENTS.

g.

Review of facility operations to detect potential safety hazards.

h.

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

1.

Review of the Plant Security Plan and implementing procedures.

J.

Review of the Emergency Plan and implementing procedures, k.

Review of the Offsite Dose Calculation Men'ual.

1.

Review of the Process Control Program for Solid Radioactive Waste.

w.

hvi w. F h ris NMbe Pi m a 3 epa wtig fre>c.edu re s AUTHORITY 6.5.1.7 The Plant Review Board shall:

u a.

Recommend to the Plant General Manager written approval or dis-5\\

approval 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-C dent Nuclear and the Trojan Nuclear Operations Board of disagreement

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between the PRB and the Plant General Manager; however, the Plant General Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

TROJAN-UNIT 1 6-7 Amendment No. #2, il 135,lM

, 97, ff, 178, 58 h.bs 6. 1M9{_

.J

LCA 151. Rev. 1 l

i Page 25 of 27 ADMINIS'.TIVE CONTROLS i

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AUDITS 6.5.2.8 Audits of facility activities shall be perfomed under the cogni -

zance of the TNOB, These audits shall encompass:

l

~ ~ '

The confomance of facility operation to provisions contained a.

within the Technical Specifications and applicable license conditions at least once per 12 months.

b.

The perfomance, training and qualifications of the facility staff at least once per 12 months.

The results of actions taken to correct deficiencies occurring c.

in facility equipment, structures, systems or method of opera-4 tion that affect nuclear safety at least once per 6 months.

d.

The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix *B",10 CTR 50, at least once per 24 m nths.

The Facility Emergency Plan and implementing procedures at least e.

once per 12 months.

f.

The Facility Security Plan and implementing procedures at least once per 12 months.

g.

Any other area of facility operation considered appropriate by the THOB er the Vice President Nuclear.

l 97 h.

The Facility Fire Protecthf g am and implementing procedures at least once per 24 months.

1.

An independent fire protection and loss prevention program inspection and audit shall be perfomed at least once per 12 months utilizing either qualified offsite licensee personnel l

or an outside fire protection fim.

l j.

An inspection and audit of the fire protection and less preven-tien program shall be perfomed by a qualified outside fire

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consultant at least once per 36 months.

AUTHORITY 6.5.2.9 The TNOB shall report to and advise the Vice President Nuclear l/

on those areas of responsibility specified in Sections 6.5.2.7 anc 6.5.2.8.

Amendment No. 78, 52, M, M II TROJAN-UNIT 1 6-11 mm-ser19s4--

i

r LCA 151, Ibv. 1 At t ec hm2nt 5 Pass 26 of 27 ADMINISTRATIVE CONTROLS 6.7 SAFETY 11 NIT VIOL ATION 6,7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The facility shall be placed in at least HOT STANDBY within one hour.

b.

The Safety Limit violation shall be reported to the Comission, the Vice President Nuclear and to the TN08 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , c.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRB. This report shall describe (1) applicable circumstances. preceding the viola-tion. (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence, d.

The Safety Limit Violation Report shall be submitted to the Comission, the TNOB and the Vice President Nuclear within la days of the violation.

6.8 PROCT 00Rf5 AND PROGRAMS 1

6.8.1 Written procedures shall be established, implemented and main-i tained covering the activities referenced below:

a.

The applicable procedures recomended in Appendix

'A' of Regulatory Guide 1.33, November,1972.

b.

Refueling operations, c.

Surveillance and test activities of safety related equipment.

d.

Security Plan implementation, e.

Radiological Emergency Plan ireplementation.

Pl* n

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Fire Protection-Pro %, 9 gram 1mplementation.

f.

g.

Offsite Dose Calculation Manual implementation, h.

Radiological effluent monitoring.

6.8.2 Cach procedure and administrative policy of 6.8.1 above, and

/

changes thereto, shall be reviewed and approved prior tc implementation l d2L as set forth in Specification 6.5.3.

TROJAN-UNIT 1 6-13 Amendment No. #2, f2, 97, ff, 796, 72P

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,1)%

tctober+r495W l

L i

o LCA IS3,R^v. 1 Attcchm:nt 5 O

ADMINISTRATIVf CONTROLS Peg 2 27 of 27

$PICIAL REPORTS b'

6.9.2 The originals of Special Reports shall be submitted to the Document js Control Desk with copies sent to the Regional Administrator, NRC Region V,

,MJ and the Resicent inspector within.'he time period specified for each report.

lhese reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

4.

fr. operable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

b.

Inoperable Meteorological Monitoring Instrumentation, Specification i

3.3.3.4.

(

Failed or inoperable PORY or safety valve, Specification 3.4.2, c.

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.

Txtc.+ed. ~

f.

Seismic Event Analysis, Specification 4.3.3.3.2.

%(iire Detection Instrumentation, SpecificationD[

g.

,,g '

M

h. S ire Suppression Systems Specifications 3.7.8.1, 3.7.8.2, and

! 3.7.8.3. p

i. Accident Monitoring Instrumentation, Specification 3.3.3.9.

g

j. Control Building Mortification Connection Bolts Specifications 3.1.11 and 4.7.11.2.

k.

Overpressure Protection System, Specification 3.4.9.3.

1.

Reactor Coslant Loop Specification 3.4.1.4.

kelta1101LlifR Barr4ers -Specif_ic_ation 3.T.)G v

n.

Instrumentation Decouple Switches, Specification 3.3.3.8.

o.

Containment Structural Integrity, Specification 4.6.1.6.4.

p.

Radioactive Effluents Specifications 3.11.1.2. 3.11.2.2, 3.11.2.3 and 3.11.2.5.

q.

Radiological Environmental Monitoring, Specifications 3.12.1 and 3.12.2.

Radioactive Gaseous Process and Ef fluent Monitoring Instrumentation, r.

Specification 3.3.3.11.

s.

Radiation Monitoring Instrumentation, Specification 3.3.3.1.

TROJAN-UNIT 1 6-17 Amendment No. 56, 76. 78, 87. 92. 7.

77,99,70f,///

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ML20011D395

Text

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