ML20057D077

Amend 192 to License NPF-1,relocating Portions of Plant TS Re Plant Fire Protection Program from TS to Topical Rept PGE-1012

ML20057D077
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	09/22/1993
From:	Masnik M Office of Nuclear Reactor Regulation
To:
Shared Package
ML20057D070	List: ML20057D069 ML20057D077 ML20057D079
References
NUDOCS 9310010073
Download: ML20057D077 (26)

Text

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NUCLEAR REGULATORY COMMISSION e

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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE. OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET N0. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 192 License No. NPF-1 1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Portland General Electric Company, et al. (PGE or licensee) dated March 16, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission as set forth in 10 CFR Chapter I; B.

The facility will be maintained in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the regulations of the Commission; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the regulations of the Commission and all applicable requirements have been satisfied.

9310010073 930922 1

PDR ADOCK 05000344 P

PDR

, 2.

Accordingly, the license is amended by changes to the Technical Specifications as ir- 'sted in the attachment to this license amendment, and paragraph 2.C(2)

Facility Operating License No. NPF-1 is hereby amended to read as foisows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.192, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

The licensee shall maintain the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(8)

Fire Protection The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in PGE-1012,

" Trojan Nuclear Plant Fire Protection Plan" and as approved in the SER datedseptafer 22,1993 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 impact the safe storage of irradiated fuel or increase the likelihood of an offsite release of radioactive material due to a fire.

3.

This license amendment is effective as of the date of issuance. This amendment shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 22, 1993

ATTACHMENT TO LICENSE AMENDMENT N0.192 FACILITY OPERATING LICENSE N0. NPF-1 DOCKET NO. 50-344 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT IV IV VII VII XIII XIII 3/4 3-48 3/4 3-48 3/4 3-49 3/4 3-49 3/4 3-49a 3/4 3-49a 3/4 3-49b 3/4 3-49b 3/4 7-23 3/4 7-23 3/4 7-24 3/4 7-24 3/4 7-25 3/4 7-25 3/4 7-26 3/4 7-26 3/4 7-27 3/4 7-27 3/4 7-28 3/4 7-28 3/4 7-29 3/4 7-29 3/4 7-30 3/4 7-30 3/4 7-31 3/4 7-31 B 3/4 3-3 B 3/4 3-3 B 3/4 7-Sa B 3/4 7-Sa B 3/4 7-6 8 3/4 7-6 6-2 6-2 6-5 6-5 6-7 6-7 6-17 6-17

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0UIREMENTS SECTION EA,GE 3/4.2 POWER DISTRIBUTION LIMITS t

3/4.2.1 Axial Flux Di fference................... 3/4 2-1 3/4.2.?

Heat Flux Hot Channel Factor 3/4 2-3 t

3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor 3/4 2-7 l

3/4.2.4 Quadrant Power Tilt Ratio................. 3/4 2-11 I

3/4.2.5 DNB Parameters 3/4 2-14 af_4_J INSTRUMENTATION 4

3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION............ 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM 1

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 l

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 S0, Detection Systems 3/4 3-68 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS................... 3/4 4-I TROJAN-UNIT 1 IV Amendment No. 4, 55, 7S, PS, IM, ni, 177,192

l INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PEE 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.......................... 3/4 7-23.

3/4.7.9 DELETED.......................... 3/4 7-31 i

3/4.7.10 SNUBBERS 3/4 7-32 3/4.7.11 CONTROL BUILDING MODIFICATION CONNECTION BOLTS 3/4 7-38 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 3/4 8-1 Operating 38 8-5 Shutdown 1

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 8-8 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. JS, 77, 97, SP, 57,197,192 i

INDEX BASES SECTION PAlf 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE....................... B 3// 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 i-4 3/4.7.4 SERVICE WATER SYSTEM B 3/4 7-'-

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 1

3/4.7.8 DELETED.......................... B 3/4 7-6 3/4.7.9 DELETED.......................... B 3/4 7-6 3/4.7.10 SNUBBERS

.B 3/4 7-6 3/4.7.11 CONTROL BUILDING MODIFICATION CONNECTION BOLTS B 3/4 7-8 3/4.8 ELECTRICAL POWER SYSTEMS 1

3/4.8.1 A.C. SOURCES B 3/4 8-1 i

l 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS B 3/4 8-1 3/4.9 REFUELING OPERATIONS i

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........................

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. ;p, 77, J7,197, Jp7,192 4

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- TROJAN-UNIT I 3/4 3-48 Amendment No. JS, 59, 97, JSP,192

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9 TROJAN-UNIT 1 3/4 3-49 Amendment No. JS, 59, 59, JES 192

9 INTENTIONALLY DELETED TROJAN-UNIT 1 3/4 3-49a Amendment No. JE, Ep, pp, pg, ygg, 192

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TROJAN-UNIT 1 3/4 3-49b Amendment No. JE, pp, 59, pg, JSP, i

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TROJAN-UNIT I 3/4 7-27 Amendment No. JS, Jp, pg, p7 192

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TROJAN-UNIT 1 3/4 7-28 Amendment No. JS, pg 192

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TROJAN-UNIT 1 3/4 7-29 Amendment No. Jg, sp, pp, p7 192

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I TROJAN-UNIT 1 3/4 7-31 Amendment No. JS, 37, Sp, p7 192

i INSTRUMENTATION BASES 3/4.3.3.6 CHLORINE DETECTION SYSTEMS I

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.

The recirculation mode of operation is defined as stopping the control room normal ventilation system and maintaining the emergency control room ventilation system in a lineup capable of responding to a safety injection signal. This does not preclude operating the CB-1 fans with the outside air makeup dampers closed and/or performing the other required actions in the event of an actual chlorine release.

The compensatory actions necessary when providing periodic air exchanges for maintaining Control Room air quality per the footnote of Specification 3.3.3.6 shall include:

(1) restricting Control Room access to essential personnel to limit carbon dioxide, (2) suspending onsite activities which could generate chlorine gas, including receipt of chlorine shipments or chlorine producing materials, and i

(3) establishing continuous communication between the Control Room and personnel observing the railroad traffic on the tracks both east and west of the Plant. The personnel must alert the Control Room in sufficient time to allow outside air dampers to be closed whenever a train approaches and passes by the Plant.

3/4.3.3.7 DELETED t

TROJAN-UNIT 1 B 3/4 3-3 Amendment No. JS, 59, JSJ 192

PLANT SYSTEMS BASES (Continued) plutonium.

Leakage 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.

3/4.7.8 DELETED j

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1 TROJAN-UNIT 1 B 3/4 7-Sa Amendment No. JE, Ep, JER, JEJ 192

PLANT SYSTEMS BASES 3/4.7.9 DELETED 3/4.7.10 SNVBBERS All snubters 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-related system.

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TROJAN-UNIT 1 B 3/4 7-6 Amendment No. JS, 29, Jpg 192

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ADMINISTRATIVE CONTROLS i

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.

l b.

At least one individual qualified to stand watch in the control room (non-certified operator or a certified fuel handler) shall be in the control room when fuel is in the spent fuel pool, c.

(deleted) d.

An individual qualified in radiation protection procedures shall be onsite during fuel handling operations.

e.

All fuel handling operations shall be directly supervised by a certified fuel handler.

f.

(deleted) g.

Administrative procedures shall be developed and implemented to limit the working hours of shift personnel who perform functions important to the safe storage of irradiated fuel assemblies (i.e., certified fuel handlers, radiation protection personnel, non-certified i

operators), and key maintenance personnel of the unit staff.

Key maintenance personnel of the unit staff are those personnel whoare responsible for the correct performance of maintenance, repair, modification or calibration of structures, systems or components i

important to the safe storage of irradiated fuel assemblies, and who are personnel performing or immediately supervising the performance of such activities. This applies to key maintenance personnel whether on shift or not.

Adequate shift coverage shall be maintained without routine heavy use of overtime. The baseline for determining overtime use will be a 40-hour work week. However, in the event that unforeseen problems TROJAN-UNIT 1 6-2 Amendment No. JSJ, JS7 192

ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 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 the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, Rev. 2, April 1987.

6.4 TRAINING 6.4.1 The NRC-approved retraining and replacement training program for the certified fuel handlers shall be maintained under the direction of a General Manager.

6.5 REVIEW AND AUDIT 6.5.I PLANT REVIEW BOARD (PRB)

FUNCTION i

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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1 TROJAN-UNIT 1 6-5 Amendment No. 18, 37, 42, 56, 146, 199,IFF,151,191 192

ADMINISTRATIVE CONTROLS

c. Review of proposed tests or experiments which may involve an unreviewed safety question as defined in 10 CFR 50.59 or requires a change in Technical Specifications.

d. Review of proposed changes to Technical Specifications or the Operating License.

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 hazards.

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

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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:

a.

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

b. Render determinations in writing with regard to whether or not each I

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President 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.

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TROJAN-UNIT 1 6-7 Amendment No. J7, 57, ES, 97, J75, JM, JEE, JEJ, 192

ADMINISTRATIVE CONTROLS 6.9.1.7.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements shall be provided, upon issuance for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

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 Monitcring Instrumentation, Specification 3.3.3.4.

c.

Failed or inoperable safcty valve, Specifications 3.4.2 and 3.4.3.1.

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.

Deleted h.

Deleted i.

Accident Monitoring 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 n.

Instrumentation Decouple Switches, Specification 3.3.3.8.

o.

Containment Structural Integrity, Specification 4.6.1.6.4.

l TROJAN-UNIT 1 6-17 Amendment No. 55, 75, 75, SJ, pg, 97, 195, 191, 197, 177, 119, 157, 192

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