ML20058K128

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Amend 193 to License NPF-1,relocating RETS to ODCM & PCP in Accordance W/Gl 89-01 & Changing Required Frequency for Submittal of Radioactive Effluent Release Rept from Semiannual to Annual
ML20058K128
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 12/06/1993
From: Dudley R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20058K122 List:
References
GL-89-01, GL-89-1, NUDOCS 9312140423
Download: ML20058K128 (73)
v • d • e


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UNITED STATES 5

NUCLEAR REGULATORY COMMISSION y $[. //

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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE. OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 193 License No. NPF-1 l

1.

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

A.

The application for amendment by Portland General Electric Company, I

et al. (PGE or licensee) dated April 1,1993, as supplemented on June 9,1993, 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; 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 t

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.

1 l

9312140423 931206 PDR ADOCK 05000344 P

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, 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-1 is hereby l

amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.193, 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.

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 Richard F. Dudley, Acting Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation Attachment.

Changes to the Technical Specifications l

Date of Issuance: December 6, 1993 e

l 8

ATTACHMENT TO LICENSE AMENDMENT NO. 193 FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Replace the following pages of the Appendix A Technical Specifications with the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert la la IV IV VIII VIII Villa VIIIa XIV XIV XVII XVII l-Sa 1-Sa 1-5b l-5b 3/4 3-54 3/4 3-54 3/4 3-55 3/4 3-55 3

3/4 3-56 3/4 3-56 3/4 3-57 3/4 3-57 l

3/4 3-58 3/4 3-58

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3/4 3-59 3/4 3-59 3/4 3-60 3/4 3-60 3/4 3-61 3/4 3-61 3/4 3-62 3/4 3-62 3/4 3-62a 3/4 3-62a 3/4 3-63 3/4 3-63 3/4 3-65 3/4 3-65 3/4 3-66 3/4 3-66 3/4 3-66a 3/4 3-66a 3/4 3-67 3/4 3-67 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-2 l

3/4 11-3 3/4 11-3 l

3/4 11-4 3/4 11-4 3/4 11-5 3/4 11-5 3/4 11-6 3/4 11-6 3/4 11-7 3/4 11-7 i

3/4 11-8 3/4 11-8 3/4 11-9 3/4 11-9 3/4 11-10 3/4 11-10 j

3/4 11-11 3/4 11-11 3/4 11-12 3/4 11-12 3/4 11-13 3/4 11-13 3/4 11-14 3/4 11-14 3/4 11-15 3/4 11-15 3/4 11-17 3/4 11-17 3/4 12-1 3/4 12-1 l

3/4 12-2 3/4 12-2 i

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Remove Insert j

3/4.12-3 3/4 12-3 3/4 12-4 3/4 12-4 3/4 12-5 3/4 12-5 3/4 12-5a 3/4 12-Sa 3/4 12-6 3/4 12-6 3/4 12-7 3/4'12-7 3/4 12-8 3/4 12-8 3/4 12-9 3/4 12-9 B3/4 3-4 B3/4 3-4 B3/4 3-5 B3/4 3-5 B3/4 11-1 B3/4 11-1 B3/4 11-2 B3/4 11-2 1

B3/4 11-3 B3/4 11-3 B3/4 11-4 83/4 11-4 83/4 11-5 B3/4 11-5 B3/4 11-6 B3/4 11-6 6-14a 6-14a 6-14b 6-14c 6-15a 6-15a 6-15b 6-15b 6-15c 6-15c 6-18 6-18 6-19 6-19 6-21 6-21 6-22 6-22 l

6-23 6-23 B3/4 12-1 B3/4 12-1 i

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INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS Source Check 1-Sa Process Control Program.....................

1-Sa DELETED.............................

1-Sal Offsite Dose Calculation Manual.................

1-Sa DELETED.............................

1-Sa l DELETED.............................

1-Sa,

Purge-Purging..........................

1-5b DELETED.............................

1-5bl Core Operating Li. nits Report (COLR)...............

1-5b Member (s) of the Public.....................

1-5b Site Boundary..........................

1-5b Unrestricted Area........................

1-5b 9

TROJAN-UNIT 1 la Amendment No. pp,177, JS7,193

. e INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTIO' Pace 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 2-3 j

3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor.........

3/4 2-7 3/4.2.4 Quadrant Power Tilt Ratio 3/4 2-11 3/4.2.5 DNB Parameters......................

3/4 2-14 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 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 l

Chlorine Detection Systems................

3/4 3-47 Fire Detection Instrumentation..............

3/4 3-48 Decouple Switches 3/4 3-50 Accident Monitoring Instrumentation 3/4 3-51 DELETED 3/43-54[

Radioactive Gaseous Process and Explosive Gas l

Monitoring Instrumentation 3/4 3-59 50, Detection Systems 3/4 3-68 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS 3/4 4-1 TROJAN-UNIT 1 IV Amendment No. (S, ES, 7S, 99,

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19E, 17J. 177, 193

INDEX I

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION P3.gg 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION................'..

3/4 9-1 3/4.9.2 INSTRUMENTATION....................

3/4 9-2 3/4.9.3 DECAY TIME 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS...........

3/4 9-4 3/4.9.5 COMMUNICATIONS 3/4 9-5 3/4.9.6 MANIPULATOR CRANE OPERABILITY.............

3/4 9-6 t

3/4.9.7 CRANE TRAVEL - FUEL BUILDING 3/4 9-7 3/4.9.8 COOLANT CIRCULATION AND LOW WATER LEVEL........

3/4 9-8 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM 3/4 9-9 3/4.9.10 WATER LEVEL-REACTOR VESSEL 3/4 9-10 l

t 3/4.9.11 STORAGE POOL WATER LEVEL 3/4 9-11 i

3/4.9.12 SPENT FUEL POOL EXHAUST SYSTEM 3/4 9-12 3/4.9.13 CONTAINMENT PURGE EXHAUST SYSTEM OPERATION 3/4 9-15 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN....................

3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.

3/4 10-2 i

3/4.10.3 PRESSURE / TEMPERATURE LIMITATION-REACTOR CRITICALITY..

3/4 10-3 3/4.10.4 PHYSICS TESTS.....................

3/4 10-S 3/4.10.5 NATURAL CIRCULATION TESTS...............

3/4 10-6 1

i 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 through 3/4.11.1.3 DELETED...............

3/4 11-1 3/4.11.1.4 TEMPORARY RADWASTE STORAGE TANKS...........

3/4 11-7 i

TROJAN-UNIT 1 VIII Amendment No. JS, pp, 193

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.. o lEl LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION fiLqt 3/4.11.2.1 through 3/4.11.2.5 DELETED..............

3/4 11-8 3/4.11.2.6 EXPLOSIVE GAS MIXTURE 3/4 11-16 3/4.11.3 DELETED........................

3/4 11-17 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 DELETED........................

3/4 12-1 3/4.12.2 DELETED........................

3/4 12-8 3/4.12.3 DELETED..................

3/4 12-9 M

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TROJAN-UNIT 1 VIIIa Amendment No. 99, 193

INDEX BASES SECTION

.P_eg i

3/4.9.6 MANIPULATOR CRANE OPERABILITY.............

B 3/4 9-2 3/4.9.7 CRANE TRAVEL - FUEL BUILDING B 3/4 9-2 i

i 3/4.9.8 COOLANT CIRCULATION..................

B 3/4 9-2 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND STORAGE POOL.....................

B 3/4 9-2 l

3/4.9.12 SPENT FUEL POOL EXHAUST SYSTEM B 3/4 9-3 r

3/4.9.13 CONTAINMENT PURGE / EXHAUST SYSTEM B 3/4 9-3 I

3/4.10 SPECIAL TEST EXCEPTIONS i

t 3/4.10.1 SHUTDOWN MARGINS B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.

B 3/4 10-1 3/4.10.3 PRESSURE / TEMPERATURE LIMITATIONS-REACTOR CRITICALITY B 3/4 10-1 3/4.10.4 PHYSICS TESTS.....................

B 3/4 10-1 f

3/4.10.5 NATURAL CIRCULATION TESTS...............

B 3/4 10-1 1

i

.3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 through 3/4.11.1.3 DELETED...............

B 3/4 11-1 3/4.11.1.4 TEMPORARY RADWASTE STORAGE TANKS...........

B 3/4 11-3 3/4.11.2.1 through 3/4.11.2.5 DELETED..............

B 3/4 11-3 3/4.11.2.6 EXPLOSIVE GAS MIXTURE B 3/4 11-6 3/4.11.3 DELETED........................

B 3/4 11-6 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 DELETED........................

B 3/4 12-1 3/4.12.2 DELETED........................

B 3/4 12-1 3/4.12.3 DELETED........................

B 3/4 12-1 TROJAN-UNIT 1 XIV Amendment No. 99, JE7e193

o ADMINISTRATfVE CONTROLS SECTION g

Consultants 6-9 Meeting Frequency 6-9 i

Quorum...........................

6-9 Review...........

6-10 I

i Audits.............................

6-11 I

i Authority 6-11 Records 6-12 i

6.5.3 TECHNICAL REVIEW AND CONTROL I

l l

Activities..........................

6-12 6.6 REPORTABLE EVENT ACTION 6-12a 6.7 SAFETY LIMIT VIOLATION.....................

6-13 l

6.8 PROCEDURES AND PROGRAMS 6-13 6.9 REPORTING RE0VIREMENTS 6.9.1 ROUTINE REPORTS 6-14cl 6.9.2 SPECIAL REPORTS 6-17 6.10 RECORD RETENTION........................

6-18 6.11 RADIATION PROTECTION PROGRAM..................

6-19 6.12 HIGH RADIATION AREA 6-19 6.13 ENVIRONMENTAL OVALIFICATION 6-20 6.14 PROCESS CONTROL PROGRAM 6-21 6.15 0FFSITE DOSE CALCULATION MANUAL 6-22 5.15 DELETED 6-23 l TROJAN-UNIT I XVII Amendment No. 77, 75, 97, 97, 195, JE7,193

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1.0 DEFINITIONS (Continued)

SOURCE CHECK 1.27 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to either an installed detector check source or to a background radiation level if background exceeds the installed check source strength.

PROCESS CONTROL PROGRAM 1.28 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

SOLIDIFICATION 1.29 DELETED l

OFFSITE DOSE CALCULATION MANUAL (0DCM) 1.30 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the annual Radiological Environmental Monitoring and annual Radioactive Effluent Release Reports required by Specifications 6.9.1.5.1 and 6.9.1.5.2.

i GASEOUS RADWASTE TREATMENT SYSTEM 1.31 DELETED j

3 VENTILATION EXHAUST TREATMENT SYSTEM 1.32 DELETED l

i TROJAN-UNIT 1 1-Sa Amendment No. 97,193

1.0 DEFINITIONS (Continued)

PURGE - PURGING 1.33 PURGE or PURGING is the process of discharging air from the Con-tainment utilizing the Containment Purge Supply and Purge Exhaust Systems LIOUID RADWASTE TREATMENT SYSTEM l.34 DELETED l

4 CORE OPERATING LIMITS REPORT - COLR 1.35 The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific e

document that provides core operating limits for the current reload cycle.

These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.

Plant operation within these core t

operating limits is addressed in individual specifications.

MEMBER (S) 0F THE PUBLIC 1.36 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-f tionally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category l

are persons who enter the site to service equipment or to make deliveries.

This category does include persons who use portions of the site for recre-ational, occupational, or other purposes not associated with the plant.

SITE BOUNDARY l

1.37 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

UNRESTRICTED AREA 1.38 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY l

access to which is not controlled by the licensee for the purposes of l

protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

t TROJAN-UNIT 1 1-Sb Amendment No. PP,177, JE7,193

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TROJAN-UNIT 1 3/4 3-54 Amendment No. 99, 193 i

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l INTENTIONALLY DELETED TROJAN-UNIT 1 3/4 3-55 Amendment No. 99, H) 193

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i TROJAN-UNIT 1 3/4 3-56 Amendment No. 99,. JJ),193

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1 TROJAN-UNIT 1 3/4 3-57 Amendment No. pp, JS7,193

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TROJAN-UNIT 1 3/4 3-58 Amendment No. SP. H7,193

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INSTRUMENTATION RADI0 ACTIVE GASEOUS PROCESS AND EXPLOSIVE GAS MONITORING INSTRUMENTATION l

LlM12JNG CONDITION FOR OPERATION 3.3.3.11 The radioactive gaseous process and explosive gas monitoring instru-1 mentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to comply with the requirements of Specifications 3.3.2, 3.4.6.1 and 3.9.9, as applicable.

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

With a radioactive gaseous process or explosive gas monitoring l

a.

instrumentation channel alarm / trip setpoint less conservative than the value shown in Table 3.3-13, adjust the setpoint to within the limit without delay or declare the channel inoperable.

b.

With less than the minimum number of radioactive gaseous process or explosive gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

With the explosive gas monitoring instrumentation channels identified in Table 3.3-13 not returned to OPERABLE status within 30 days, identify the cause of the inoperable channels in a Special Report submitted to the Commission pursuant to Specification 6.9.2.

The provisions of Specifications 3.0.3 and 3.0.4 are not c.

applicable -

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SURVEILLANCE RE0VIREMENTS t

DELETED l

4.3.3.11.1 Each radioactive process or explosive gas monitoring l

instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operation at the frequencies shown in Table 4.3-9.

1 TROJAN-UNIT 1 3/4 3-59 Amendment No. 97, J57,193

g TABLE 3.3-13 8

!E RADI0 ACTIVE GASEOUS PROCESS AND EXPLOSIVE GAS MONITORING INSTRUMENTATION l

MINIMUM ALARM

-d CHANNELS APPLICABLE TRIP INSTRUMENT OPERABLE MODES SETPOINT ACTION 1.

DELETED l

2.

Waste Gas Holdup System Explosive Gas Monitoring System Oxygen Monitor (a) 2(a)

N/A 29 3a. Containment Ventilation Isolation es a.

Particulate Activity Monitor 1

1,2,3,4, s 2 Times 33 ls (PRM-1A) and 6

Background

u d,

b.

Iodine Activity Monitor (PRM-18)

I 1, 2, 3, 4, s 2 Times 33 and 6

Background

c.

Low level Noble Gas Monitor 1

1, 2, 3, 4, s 2 Times 33 (PRM-lC) and 6

Background

d.

High Level Noble Gas Monitor 1****

1, 2, 3, 4, s 2 Times 33 (PRM-ID) and 6

Background

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a (a) For the purposes of oxygen monitor requirements, two channels shall be operable from sessing element to

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remote indicator on panel C-151. A single alarm shall be operable in the control room in order to satisfy the requirement of Specification 4.11.2.6.1 for continuous monitoring.

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TABLE 3.3-13 (Continued) y RADI0 ACTIVE GASEOUS PROCESS AND EXPLOSIVE GAS MONITORING INSTRUMENTATION l

C 5

MINIMUM ALARM l

CHANNELS APPLICABLE TRIP

~

INSTRUMENT OPERABLE MODES _

SETPOINT ACTION 3b.

RCS Leakage Detection

a. Particulate Activity Monitor 1

1, 2, 3, N/A 32 (PRM-1A) and 4

b. Low Level Noble Gas Monitor 1

1, 2, 3, N/A 32 (PRM-lC) and 4

c. High Level Noble Gas Monitor 1****

1, 2, 3, N/A 32 (PRM-10) w1 w

3c.

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5d TABLE 3.3-13 (Continued) 8 jE EADI0 ACTIVE GASEOUS PROCESS AND EXPLOSIVE GAS MONITORING INSTRUMENTATION l

C 25 MINIMUM ALARM

-d CHANNELS APPLICABLE TRIP INSTRUMENT OPERABLE MODES SETPOINT ACTION 6.

Post-Accident Monitoring Systems a.

Containment Noble Gas Effluent 1

1, 2, 3, 4 34 Monitor (PRM-lE) b.

Containment Effluent Iodine 1

1, 2, 3, 4 N/A 34 Sampler (High Range) c.

Auxiliary Building Noble Gas 1

1, 2, 3, 4 34 gd Effluent Monitor (PRM-20) d.

Auxiliary Building Effluent 1

1, 2, 3, 4 N/A 34 Iodine Sampler (High Range) c e.

Condenser Air Ejector Noble Gas 1

1, 2, 3, 4f 34 Effluent Monitor (PRM-6C) f.

Condenser Air Ejector Effluent 1

1, 2, 3, 4 #

N/A 34 Iodine Sampler (High Range) g.

Main Steam Line Noble Gas Activity 1/ steam 1, 2, 3, 4 N/A 34 Monitors (PRM-16A, -168, -16C, -160) line g.

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i TABLE 3.3-13 (Continued)

TABLE NOTATION i

  • DELETED l
    • During waste gas compressor operation.
      • DELETED l
        • Minimum channels operable requiren,ent does not apply if PRM-IC l

is on scale and operable.

          • Setpoint calculated in accordance with the ODCH.
  1. Only applicable in Modes 3 and 4 if the condenser has a vacuum.

ACTION 27 DELETED ACTION 28 DELETED ACTION 29 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of the waste gas compressors may continue provided grab samples are taken and analyzed once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. With both channels inoperable, opera-tion of the waste gas compressors may continue provided grab samples are taken and analyzed once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 30 DELETED ACTION 31 DELETED i

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l TROJAN-UNIT 1 3/4 3-63 Amendment No. SP, JPE, JpS 193

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TABLE 4.3-9 8

E RADI0 ACTIVE GASEOUS PROCESS AND EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l

.E.

CHANNEL MODES IN WillCH CllANNEL SOURCE

  • CHANNEL FUNCTIONAL SURVEILLANCE

~

INSTRUMENT CHECK CHECK CALIBRATION TEST REOUIRED 1.

DELETED l

2.

Waste Gas floldup System Explosive Gas Monitoring System a.

Oxygen Monitor D**

N/A Q(1)(b)

N/A N/A 3a.

Containment Ventilation Isolation S

N/A R

M(2)(4) 1, 2, 3, 4, (PRM-1A, IB, 10, ID) and 6 3b.

RCS Leakage Detection S

N/A R

M(2)(4) 1, 2, 3, 4, Y

(PRM-1A,-10, ID) and 6 8

3c.

DELETED l

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(a) DELETED l

3 (b) The staggered channel calibration of the oxygen monitors shall include those items of a functional M

check nature.

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TABLE 4.3-9 (continued)

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9 TABLE 4.3-9 (continued)

E 3E RADI0 ACTIVE GASEOUS PROCESS AND EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE RE0VIREMENTS l

C5 CHANNEL MODES IN WHICH

-4 CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CAllBRATION TEST REQUIRED 6.

Post-Accident Monitoring Systems a.

Containment Noble Gas S

N/A R

M(5) 1, 2,~3, 4 Effluent Monitor (PRM-lE) b.

Containment Effluent Iodine N/A N/A N/A M(3) 1, 2, 3, 4 Sampler (High Range) c.

Auxiliary Building Noble Gas S

N/A R

M(5) 1, 2, 3, 4

${

Effluent Monitor (PRM-20)

}l d.

Auxiliary Building Effluent N/A N/A N/A M(3) 1, 2, 3, 4 c?

Iodine Sampler (High Range) e.

Condenser Air Ejector Noble S

N/A R

M(5) 1, 2, 3, 4 Gas Effluent Monitor (PRM-6C) f.

Condenser Air Ejector Effluent N/A N/A N/A M(3) 1, 2, 3, 4 lodine Sampler (High Range)

![

g.

Main Steam Line Ncble Gas S

N/A R

H 1, 2, 3, 4 EL Activity Monitors (PRM-16A, 3

-16B, -16C, -160) a E.F w

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TABLE 4.3-9 (Continued)

TABLE NOTATION i

DELETED l

During waste gas compressor operation.

(1) The CHANNEL CALIBRATION shall include the use of standard calibration gas samples.

Each monitor shall be calibrated on a staggered test basis, with each channel being calibrated at least once per 92 days.

(2) CHANNEL FUNCTIONAL TEST does not include testing for Containment purge supply and exhaust valve closure in Modes 1-4.

(3) CHANNEL FUNCTIONAL TEST consists of verification of sampler flow through the sampler.

(4) The CHANNEL FUNCTIONAL TEST shall, where applicable, include verification that automatic isolation of the affected pathway and/or control room annunciator occurs if:

a)

Instrument indicates above the alarm trip setpoint b)

Instrument indicates downscale failure c) Controls not in OPERATE mode NOTE: The alarm trip setpoint verification for the waste gas holdup system, noble gas activity monitor (PRM-4A), and Containment purge effluent noble gas monitor (PRM-ID) will be accomplished by reducing the alarm trip setpoint below the level of the keep-alive source.

(5) CHANNEL FUNCTIONAL TEST includes verifying that the PRM shifts into the accident mode as required.

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TROJAN-UNIT 1 3/4 3-67 Amendment No. SP,195, Jg7,193

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i TROJAN-UNIT 1 3/4 11-6 Amendment No. 99, 193 1

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RADI0 ACTIVE EFFLUENTS TEMPORARY RADWASTE STORAGE TANKS

  • LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in temporary rad-waste storage tanks shall be limited to less than or equal to 10 Ci, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTION:

With the quantity of radioactive material in any of the above-a.

listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next annual Radioactive l

Effluent Release Report.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not i

applicable.

SURVEILLANCE RE0VIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above-listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

f i

  • Tanks included in this Specification are those outdoor temporary tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

t TROJAN-UNIT 1 3/4 11-7 Amendment No. pp,193 i

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INSTRUMENTATION BASES 3/4.3.3.8 DECOUPLE SWITCHES OPERABILITY of the decouple switches in the cable spreading room (CSR) ensures that the control cables passing through the CSR 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 INSTRUMENTATION i

~

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

3/4.3.3.10 DELETED l

3/4.3.3.11 RADIOACTIVE GASEOUS PROCESS AND EXPLOSIVE GAS INSTRUMENTATION The radioactive gaseous process and explosive gas instrumentation is provided for automatic isolation of Containment ventilation at two times Containment background readings in Modes I, 2, 3, 4, and 6; however, in no case will the limits of 10 CFR Part 20 be exceeded, to provide Containment activity levels for RCS leakage detection, to monitor potentially explosive mixtures in the Gaseous Radwaste System, and to monitor post-accident release levels.

The process and effluent radiological monitors for the Containment, Auxiliary Building and condenser air ejector effluents are equipped with an extended range designed to function during accident conditions.

Additionally, noble gas activity monitors have been installed on the main steam lines to monitor potential releases of activity through the main steam relief valves.

These monitoring capabilities are consistent with the requirements in NUREG-0737, " Clarification of TMI Action Plan Requirements."

TROJAN-UNIT 1 8 3/4 3-4 Amendment No. 50, E5, 93, SP,105, JEf,193

e i

i INSTRUMENTATION BASES (Continued) 3/4.3.3.12 S0, DETECTION SYSTEMS t

The OPERABILITY of the sulfur dioxide detection system ensures that sufficient capability is available to promptly detect and initiate protective action in the lent of an accidental sulfur dioxide release. This capability 1

is required t protect control room personnel in accordance with Regulatory Guide 1.78, ssumptions for Evaluating the Habitability of a Nuclear Power Plant Contro Room During a Postulated Hazardous Chemical Release," June 1974, and is consistent with the requirements of General Design Criterion 19 of Appendix A to 10 CFR Part 50.

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 sulfur dioxide release.

.i TROJAN-UNIT I B 3/4 3-5 Amendment No. pp, 195, 193

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RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1.3 DELETED l

3/4.11.1.4 TEMPORARY RADWASTE STORAGE TANKS This specification assures that outside temporary radwaste storage tanks will contain less than the number of curies which could result in excess i

of the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply in an unrestricted area.

For tanks of unknown size, the NRC staff has accepted 10 curies as a default value in cases where substantial dilution would occur before the spill could reach a potable water supply.

3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 DELETED 3/4.11.2.2 DELETED 3/4.11.2.3 DELETED j

3/4.11.2.4 DELETED i

TROJAN-UNIT 1 B 3/4 11-3 Amendment No. 99, 193 l

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i TROJAN-UNIT 1 B 3/4 11-5 Amendment No. 97, 193

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.5 DELETED l

3/4.11.2.6 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treat-ment system is maintained below the flammability-limits of hydrogen and oxygen mixture. Maintaining the concentration of hydrogen and oxy-gen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

3/4.11.3 DELETED l

)

i TROJAN-UNIT 1 B 3/4 11-6 Amendment No. 99, 193

1 r

1 ADMINISTRATIVE CONTROLS (iii) Identification of the various sampling points.

1 (iv) Procedures for recording and management of data.

(v) Procedures defining corrective actions for off control' point chemistry conditions.

(vi) A procedure identifying the authority and responsibility for the interpretation of the data and the sequence and timing of the administrative events required to initiate corrective action.

d.

Post-Accident Samplina A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and Containment atmosphere samples under accident conditions. The program shall include the following:

(i) Training of personnel, i

(ii) Procedures for sampling and analysis, (iii) Provisions for maintenance of sampling and analysis equipment, e.

Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to i

MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the
ODCM,
2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR 20, Appendix B, Table II, Column 2,
3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20:106 and with the methodology and parameters of the ODCM,
4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS conforming to Appendix 1 to 10 CFR Part 50, TROJAN-UNIT 1 6-14a Amendment No.195, JES,193

ADMINISTRATIVE CONTROLS

5) Determination of cumulative and projected dose contributions from radioactive effluents of the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days,
6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate e

portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1,
8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,
9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and
10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

f.

Radiolooical Environmental Monitorino Procram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,
2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and TROJAN-UNIT 1 6-14b Amendment No.193

e r

ADMINISTf3TIVE CONTROLS

3) Participation is an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality as'surance program for environmental monitoring.

6.8.5 Procedures for radiological environmental monitoring shall be approved and implemented in accordance with the PGE Nuclear Quality Assurance Program.

6.9 REPORTING RE0VIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, signed originals of the following reports shall be submitted to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555, with copies sent to the Regional Administrator, USNRC, Region V, and the USNRC Resident Inspector.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.

6.9.1.2 The Startup Report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions.

Any corrective actions that were required to obtain satisfactory TROJAN-UNIT 1 6-14c Amendment No. 7J, 97, JH,

M7, 193

ADMINISTRATIVE CONTROLS which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of the time for the duration of spec.ific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 6.9.1.5.1 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include sumaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.5.2 The annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted before May 1 of each year. The report shall include a sumary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

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TROJAN-UNIT 1 6-15a Amendment No. PP, J75, J35, j

JE7,193

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g ADMINISTRATIVE CONTROLS p.

Radioactive Gaseous Process and Explosive Gas Monitoring Instrumentation, l

Specification 3.3.3.11.

^

q.

Radiation Monitoring Instrumentation, Specification 3.3.3.1.

6.10 RECORD RETENTION 6.10.1 The following records shall be maintained for at least five years:

Records and logs of facility operation covering time interval a.

at each power level.

b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c.

All REPORTABLE EVENTS submitted to the Commission.

d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e.

Records of reactor tests and experiments.

f.

Records of changes made to Operating Procedures.

g.

Records of radioactive shipments.

h.

Records of sealed source leak tests and results.

1.

Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Facility Operating License:

Records and drawing changes reflecting facility design modifi-a.

cations made to systems and equipment described in the Final Safety Analysis Report, i

b.

Records of new and irradiated fuel inventory, fuel transfers l

and assembly burnup histories.

j Records of facility radiation and contamination surveys.

c.

TROJAN-UNIT I 6-18 Amendment No. ?J, 97, pp, J9s, JE7, J7E, 193

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i ADMINISTRATIVE CONTROLS d.

Records of radiation exposure for all individuals entering radiation control areas.

3 e.

Records of gaseous and liquid radioactive material released to the environs.

l f.

Records of transient or operational cycles for those facility components identified in Table 5.9-1.

g.

Records of training and qualification for current members of the plant staff.

i h.

Records of in-service inspections performed pursuant to these Technical Specifications.

i. Records of Quality Assurance activities required by the PGE Nuclear Quality Assurance Program.

J. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the PRB and the TNOB.

1.

Records of Environmental Qualification which are covered under the provisions of paragraph 6.13.

Records of analyses results required by the Radiological m.

Environmental Monitoring Program.

l n.

Records of the service lives of hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.

o.

Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20:

a.

Each High Radiation Area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and TROJAN-UNIT 1 6-19 Amendment No. 97, pp, Jp2, J77, JEl, 193 i

e a

L ADMINISTRATIVE CONTROLS 6.14 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.

This documentation shall contain:

1)

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)

A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.

Shall become effective after review and acceptance by the Plant Review Board and the approval of the Plant General Manager.

i i

TROJAN-UNIT 1 6-21 Amendment No. SP, JES 193

)

l

ADMINISTRATIVE _ CONTROLS 6,15 0FFSITE DQ1E_ CALCULATION MANUAL (ODCM)

Changes to the ODCH:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.

This documentation shall contain:

1)

Sufficient information to support the change together with the 3

appropriate analyses or evaluations justifying the change (s) and 2)

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adverpely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective after review and acceptance by the Plant Review Board and the approval of the Plant General Manager.

c.

Shall be submitted to the Commission in the form of a complete legible copy of the entire ODCM as part of er concurrent with the annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

i i

TROJAN-UNIT I 6-22 Amendment No. 99,193 i

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