ML20127N338

Amends 55 & 34 to Licenses NPF-68 & NPF-81,respectively, Modifying TSs in Accordance W/Generic Ltr 89-01, Implementation of Programmatic Controls for Rets..

ML20127N338
Person / Time
Site:	Vogtle
Issue date:	01/05/1993
From:	Matthews D Office of Nuclear Reactor Regulation
To:	Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA
Shared Package
ML20127N342	List: ML20127N338 ML20127N421
References
GL-89-001, NPF-68-A-055, NPF-81-A-034 NUDOCS 9301290176
Download: ML20127N338 (61)

Text

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'i NUCLEAR REGULATORY COMMISSION t

W ASHING TON, D, C. 2.,555

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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. NPF-68 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Facility Operating License No. NPF-68 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated March 4,1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as se.t forth in 10 CFR Chapter I; B.

The facility will operate 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 Commission's regulations set forth in 10 CFR Chapter I; 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 Commission's regulations and all applicable requirements have been satisfied.

-9301290176 930105

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Accordingly, the license is hereby amended by page 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-68 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 55, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.

GPC shall operate the facility in accordance with the Technical Spe:ifications and the Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY' COMMISSION 13f/acdk David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance: January 5, 1993 l.

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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WA$HINoTON, D, C 20555

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GEORGIA POWER COMPANY-OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA

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V0GTLE ELECTRIC GENERATING PLANT. UNIT ~2 AMENDMENT TO FACILITY OPERATING LICENSE o

Amendment No.34-License No. NPF-81L

-1.

The Nuclear Regulatory Commission (the Commission) has found that:-

A.

The application for amendment to-the Vogtle Electric; Generating..

Plant,- Unit 2 (the facility) Facility Operating-License No. NPF-811 filed by the Georgia-Power Company,- acting for itself," Oglethorpe:.

Power Corporation, Municipal Electric Authority of Georgia, 'and City?

of Dalton, Georgia (the licensees), dated March 4_,

1992,. complies-with the standards and requirements of.the_ Atomic Energy Act of

=1954,-as. amended (the Act),:and the Commission's rules and-regulations as set forth in 10 CFR Chapter _I;.

B.

The facility will operate 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 thel activities-authorized by this amendment can'be conducted without. endangering the2 health and--'

' safety of the public,.and (ii) that such. activities. will be conducted in compliance with the: Commission's regulations-setiforthi in 10 CFR Chapter I;

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-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{

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E.

1The issuance of this' amendment is in accordance with 10 CFR Part 51l l:

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

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er 2.

Accordingly, the license is hereby amended by page changes to the Technical-Specifications as irdicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-81 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 34, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.

GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance: January 5, 1993

d ATTACHMENT ~TO LICENSE ~ AMENDMENT NO. 55 FACILITY OPERATING LICENSE N0. NPF-68 DOCKET NO. 50-424 88Q TO LICENSE AMENDMENT NO. 34 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 Replace the following pages of the Appendix "A" Technical-Specifications with; the enclosed pages. The revised pages are identified by Amendment number and contain vertical. lines indicating the areas of change.

Remove Paoes Insert Paaes-II VI VI XIII XIII XIV XIV XX XX XXIV XXIV l-4 1-4 1-5 1-5 1-6 1-6 3/4 3-35 3/4 3-35 3/4 3-65 3/4 3-65 3/4 3-66 3/4 3-67 3/4 3-68 3/4 3-69 3/4 3-70 s

3/4 3-71 3/4 3-66 3/4 3-72 3/4 3-67 3/4 3-73

-3/4 3-74 3/4 3-68 3/4 3-75 3/4 3-76 3/4 3-69 3/4 3-77 3/4 3-78 3/4 3-70

• 3/4 3-79 3/4 3-71

• 3/4 3-80 3/4 3-72

• 3/4 3-81 3/4 3-73

• page number change only

- I Bemove Paaes (cont'd)

Insert Paaes (cont'd) 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-3 3/4 11-4 3/4 11-5 3/4 11-2 3/4 11-6 3/4.11-3

• 3/4 11-7 3/4 11-4 3/4 11-8 3/4 11-5 3/4 11-9 3/4 11-10 3/4 11-11 3/4 11-12 3/4 11-6 3/4 11 3/4 11-7 3/4 11-14 3/4 11-8

• 3/4 11-15 3/4 11-9

• 3/4 11-16 3/4 11-10 3/4 11-17 3/4 11-11 3/4 11-18 3/4 11-12 3/4 12-1 3/4 12-1 3/4 12-2 3/4 12-3 3/4 12-4 3/4 12-5 3/4 12-6 3/4 12-7 3/4 12-8 3/4 12-9 3/4 12-10 3/4 12-11 3/4 12-12

-3/4 12-13 3/4 12-2 3/4 12-14 3/4 12-3 8 3/4 3-5 8.3/4 3-5 B 3/4 3-6 B 3/4 3-6 B 3/4 11-1 B 3/4 11-1 B 3/4 11-'2 B 3/4 11-2 B 3/4 11-3 B 3/4 11-3 B 3/4 11-4 8 3/4 11 B 3/4 11-5 B 3/4 11-5 B 3/4 11-6 B 3/4 11-6 B 3/4 12-1 B 3/4 12-1 B 3/4 12-2 8 3/4 12-2

- '8122ye Phaes (cont'd)

Insert Paaes (cont'd) 5-2a 5-2a-6-16 6-16 6-18 6-18

~6-19 6-19 6-20 6-21 6 *6-21a 6-21 6-23 6-23 6-24 6-24 6-25 6-25 6-26

-f

INDEX DEFINITIONS SECTION PAGE 1.32 SLAVE RELAY TEST.............................................

1-5 1.33 SOLIDIFICATION (DELETED).....................................

1-6 l

1.34 SOURCE CHECK.....<...........................................

1-6 1.35 STAGGERED TEST BASIS.........................................

1-6 1.36 THERMAL P0WER.........................................

la6 I

1.37 '91P ACTUATING DEVICE OPERATIONAL TEST.'......................

1-6 1.38 UNIDENTIFIED LEAKAGE.........................................

1-6 1,39 UNRESTRICTED AREA............................................

1-6 1.40 VENTILATION EXHAUST TREATMENT SYSTEM.........................

1-6 1.41 VENTING......................................................

1-7 TABLE 1.1 FREQUENCY N0TATION......................................

1-8 TABLE 1.2 OPEkATIONAL H0 DES.......................................

1 l F

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V0GTLE UNITS - 1 & 2 II Amendment No, 55 (Unit 1)

Amendment No. 34-(Unit 2)-

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 1

SECTION PAGE TABLE 3.3-5 SEISMIC MONITORING INSTRUMENTATION....................

3/4 3-51 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................................

3/4 3-52 Meteorological Instrumentation (Common System)...........

3/4 3-53 TABLE 3.3-6 METEOROLOGICAL MONITORING INSTRUMENTATION.............

3/4 3-54 Remote Shutdown System...................................

3/4 3-55 TABLE 3.3-7 REMOTE SHUTOOWN SYSTEM MONITORING INSTRUMENTATION.....

3/4 3-56 Accident Monitoring Instrumentation......................

3/4 3-58 TABLE 3.3-8 ACCIDENT MONITORING INSTRUMENTATION...................

3/4 3-59 Chlorine Detection Systems (Deleted).....................

3/4 3 63 Loose Parts Detection System (Deleted)..................

3/4 3-64 Radioactive Liquid Effluent Monitoring Instrumentation (Deleted)................................

3/4 3-65 Explosive Gas Effluent Monitoring Instrumentation........

3/4 3-66 TABLE 3.3-10 EXPLOSIVE GAS MONITORING INSTRUMENTATION..........................................

3/4 3-67 TABLE 4.3-6 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/4 3-69 High-Energy Line Break Isolation Sensors.................

3/4 3-71 TABLE 3.3-11 HIGH-ENERGY LINE BREAK INSTRUMENTATION...............

3/4 3-72 3/4.3.4 TURBINE OVERSPEED PROTECTION..............................

3/4 3-73 l

l V0GTLE UNITS - UNITS 1 & 2 VI Amendment No.

55 (Unit 1)

Amendment No.

34. (lInit. 2)

_INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 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 3/4.10.3 PHYSICS TESTS............................................

3/4 10-3 3/4.10.4 REACTOR COOLANT L00PS....................................

3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUTD0WN....................

3/4 10-5 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration (DELETED)..................................

3/4 11-1 Dose (DELETED)...........................................

3/4 11-2 Liquid Radwaste Treatment System (DELETED)...............

3/4 11-3 Liquid Holdup Tanks......................................

3/4 11-4 3/4.11.2 GASEOUS EFFLUENTS Dose Rate (DELETED)......................................

3/4 11-5 Dose - Noble Gases (DELETED).............................

3/4 11-6 Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form (DELETED)...................

3/4 11-7 Gaseous Radwaste Treatment System (DELETED)..............

3/4 11-8 Explosive Gas Mixture....................................

3/4 11-9 Gas Decay Tanks..........................................

3/4 11-10 3/4.11.3 SOLID RADI0 ACTIVE WASTES (DELETED).......................

3/4 11-11 3/4.11.4 TOTAL DOSE (DELETED).....................................

3/4 11-12 V0GTLE UNITS - UNITS 1 & 2 XIII Amendment No.

55 (Unit 1)

Amendment No.

34 (Unit 2)

1 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.12 RADIOLOGICAL ENVIRONMENTAL HONITORING (DELETED) 3/4.12.1 MONITORING PROGRAM (DELETED).............................

3/4 12-1 3/4.12.2 LAND USE CENSUS (DELE 1ED)................................

3/4 12-2 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM (DELETED).............

3/4 12-3 V0GTLE UNITS - UNITS 1 & 2 XIV Amendment No. 55 (Unit 1)-

Amendment No. 34 (Unit 2)

INDEX l

BASES 3/4.11 RADI0 ACTIVE EFFLUENTS i

3/4.11.1 LIQUID EFFLUENTS........................................

B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS.......................................

B 3/4 11-3 3/4.11.3 SOLID RADI0 ACTIVE WASTES (DELETED).......................

B 3/4 11-6 3/4.11.4 TOTAL DOSE (DELETED)....................................

B 3/4 11-6 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING (DELETED) l 3/4.12.1 MONITORING PROGRAM (DELETED)............................

B 3/4 12-1 3/4.12.2 LAND USE CENSUS (DELETED)...............................

B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM (DELETED)............

B 3/4 12-2 l

V0GTLE UNITS - UNITS 1 & 2 XX Amendment-No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

INDEX ADMINISTRATIVE CONTROLS SECTION 6.10 RADIATION PROTECTION PR0 GRAM...............................

6-23 6.11 HIGH RADIATION AREA........................................

6-23 6.12 PROCESS CONTROL PROGRAM (PCP)..............................

6-24 0FFSITEDOSECALCULATIONhufpfs,j!)gM1.....................

6-25 6.13 f

6.14 MAJOR CHANGES TO LIQUID, GASEOUS. AND SOLID

^

RADWASTE TREATMENT SYSTEMS (DELETE 0).......................

6-25 V0GTLE UNITS - UNITS 1 & 2 XXIV Amendment No. 55 - (Unit 1)

Amendment No. 34 (Unit 2)

DEFINITIONS MEMBER (S) 0F THE PUBLIC 1.18 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant.

This category does not include employees of the licensee *, its contractors, or vendors.

Also excluded from this category 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.

OFFSITE DOSE CALCULATION MANUAL 1.19 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioac-l tive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program.

The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Pro-grams required by Section 6.7.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Surveillance and Semiannual Radioactive Effluent Release Reports required by Specifica-tions 6.8.1.3 and 6.8.1.4.

OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL MODE - MODE 1.21 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor-coolant temperature specified in Table 1.2.

PHYSICS TESTS 1.22 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation:

(1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.23 PRESSURE B0UNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

PROCESS,0NTROL PROGRAM 1.24 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas,.

sampling, analyses, tests, and determinations to be made to ensure that process-ing 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 Darts 20, 61, and 71, State regulaticas, l

V0GTLE UNITS --1 & 2 1-4 Amendment No.

55 (Unit 1)-

Amendment No.

34 (Unit 2)

DEFINITIONS burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

l PURGE - PURGING i

1.25 PURGE or PURGING shall be any controlled process of discharging air or gas fr:m a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

QUADRANT POWER TILT RATIO 1.26 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.

With one excore detector inoperable, the remaining three detectors shall be used for computing the average.

RATED THERHAL POWER 1.27 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.28 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENT 1.29 A REPORTABLE EVENT shall be any of those conditions specified in Sections 50.72 and 50.73 of 10 CFR Part 50.

SHUTDOWN MARGIN 1.30 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all rod cluster assemblies (shutdown and control) are fully inserted i

except for the single rod cluster assembly of highest reactivity worth which is l

assumed to be fully withdrawn.

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SITE BOUNDARY 1.-31 The SITE B0UNDARY shall be the exclusion boundary line as shown in Figure 5.1-1.

SLAVE RELAY TEST 1.32 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERAdILITY of each relay.

The SLAVE RELAY TEST shall include -

I a continuity check, as a minimum, of associated testable actuation devices.

V0GTLE UNITS - 1 & 2 1-5 Amendment No.

55 (Unit 1)

Amendment No.-

34 (Unit 2)

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i DEFINITIONS SOLIDIFICATION 1.33 Deleted.

SOURCE CHECK 1.34 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

STAGGERED TEST BASIS 1.35 A STAGGERED TEST BASIS shall consist of:

a.

A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, and b.

The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.

THERMAL POWER 1.36 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRIP ACTUATING DEVICE OPERATIONAL TEST 1.37 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm. interlock and/ur trip functions.

The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.

UNIDENTIFIED LEAKAGE 1.38 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or-CONTROLLED LEAKAGE.

UNRESTRICTED AREA 1.39 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of 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.

V0GTLE UNITS - 1 & 2 1-6 Amendment No.

55

.(Unit.1)

Amendment No.-

34

-(Unit 2)-

i TABLE 3.-3-3 (Continued)

TABLE NOTATIONS

" Time constants utilized in the lead-lag controller for Steam Line Pressure-Low i

y > 50 seconds and T2 1 5 seconds.

CHANNEL CALIBRATION shall are t ensure that these time constants are adjusted to these values.

• • The time constant utilized in the rate-lag controller for Steam Line Pressure-Negative Rate-High is greater than or equal to 50 seconds.

CHANNEL CALIBRATION shall ensure that this time constant is adjusted to this value.

1. Feedwater isolation only.

Turbine trip occurs on reactor trip.

a0uring refueling operations.

60uring power operation.

This is an initial setpoint only.

The trip setpoint will be set at 50 times background icvel.

Background level should be deter-mined at or near the end of the first fuel cycle, cSetpoints will not exceed the limits of Specification 6.7.4.f.

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V0GTLE UNITS - 1 & 2 3/4 3-35.

Amendment.No. 55 (Unit 1)'

Amendment No. 34 (Unit 2) y-:

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INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Specification 3/4.3.3.9 Deleted l

l V0GTLE UNITS - 1 & 2 3/4 3-65 Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

INSTRUMENTATION EXPLOSIVE GAS HONITORING INSTRUMENTATION l-LIMITING CONDITION FOR OPERATION 3.3.3.10 The explosive gas monitoring instrumentation channels shown in l

Table 3.3-10 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded.

APPLICABILITY:

As shown in Table 3.3-10 ACTION:

a.

With an explosive gas monitoring instrumentation channel Alarm / Trip.

l Setpoint less conservative than required by the above specification, declare the channel inoperable and take the ACTION shown in Table 3.3-10.

b.

With less than the minimum number of explosive gas monitoring instru-l mentation channels OPERABLE, take the ACTION shown in Table 3.3-10.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.8.2 to explain why this inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-6.:

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V0GTLE UNITS - 1 & 2 3/4 3-66 Amendment No. 55 - (Unit 1)

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Amendment No. 34 (Unit 2)L p

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TABLE 3.3-10

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. p EXPLOSIVE GAS MONITORING INSTRUMENTATION l

m E

MINIMUM CHANNELS Z--

INSTRUMENT OPERABLE APPLICABILITY ACTION i

1.

(NOT USED) 2.

GASEOUS WASTE PROCESSING SYSTEM Explosive Gas Monitoring System N

a.

Hydrogen Monitor 1/recombiner

'50 b.

Oxygen Monitor 2/recombiner 49 j

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TABLE 3.3-10 (Continued)

TABLE NOTATIONS (Not Used) l

• • During GASEOUS WASTE PROCESSING SYSTEM operation.

• • • (Not Used)

1. (Not Used)

ACTION STATEMENTS ACTION 41-48 (Not Used) l ACTION 49 -

a.

With the outlet oxygen monitor channel inoperable, opera-tion of the system may continue provided grab samples are taken and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.and the oxygen concentration remains less than 1 percent.

b.

With the inlet oxygen monitor inoperable, operation may con-tinue if the inlet hydrogen monitor is OPERABLE.

c.

With both oxygen channels or both of the inlet oxygen and inlet hydrogen monitors inoperable, suspend oxygen supply to the recombiner.

Addition of waste gas to the system may continue provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations or at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations and the oxygen concentration remains less than 1 percent.

ACTION 50 -

With the number of channels OPERABLE one less than required'by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiner.

Addition of waste gas to the system may con-tinue provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations or at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations and the oxygen concentration remains less than 1 percent.

f V0GTLE UNITS - 1 & 2 3/4 3-68 Amendment No. 55 (Unit 1) l.

Amendment No. 34 (Unit 2)

TABLE 4.3-6

<8

-f EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l

m E

q ANALOG m

CHANNEL MODES FOR WHICH CHANNEL CHANNEL' OPERATIONAL SURVEILLANCE 9

INSTRUMENT CHECK CALIBRATION TEST IS REQUIRED j

co 1.

(Not Used) l 2.

GASEOUS WASTE PROCESSING SYSTEM Explosive Gas Monitoring System

a. Hydrogen Monitors D

Q(4)

M b

b. Oxygen Monitors D

Q(5)

M b

5 w

tr-a*

RR l

ae en-(*)

22 Ab 3C 1

TABLE 4.3-6 (Continued)

TABLE NOTATIONS a Not used.

l b During GASEOUS WASTE PROCESSING SYSTEM operation.

c Not used.

I (1) Not used.

(2) Not used.

(3) Not used.

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples in accordance with the manufacturer's recommendations.

In addition, a standard gas sample of nominal four volume percent hydrogen, balance nitrogen, shall be used in the calibration to check linearity of the hydrogen analyzer.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples in accordance with the manufacturer's recommendations.

In addition, a standard gas sample of nominal four volume percent oxygen, balance nitrogen, shall be used in the calibration to check linearity of the oxygen analyzer.

1 V0GTLE UNITS - 1 & 2 3/4 3-70 Amendment No. 55 (Unit 1) l Amendment No. 34 (Unit 2)

I

INSTRUMENTATION HIGH-ENERGY LINE BREAK ISOLATION SENSOR $

LIMITING CONDITION FOR OPERATION 3.3.3.11 The high energy line break instrumentation listed in Table 3.3-11 shall be OPERABLE.

APPLICABILITY:

As noted in Table 3.3-11.

ACTION:

a.

With the number of OPERABLE electric steam boiler isolation instruments less than the Minimum Channtls OPERABLE as required by Table 3.3-11, re-store the inoperable instruments to OPERABLE status within 7 days or sus-pend operation of the electric steam boiler until the inoperable sensors are restored to OPERABLE status.

The provisions of Specification 3.0.4 are not applicable.

b.

With the number of OPERABLE steam generator blowdown line isolation instru-ments or letdown line isolation instruments less than the Minimum Channels OPERABLE as required by Table 3.3.11, restore the inoperable instruments to OPERABLE status within 7 days or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 1

4.3.3.11 Each of the above high energy line break isolation instruments shall be demonstrated OPERABLE by the performance of an ANALOG CHANNEL OPERATIONAL-TEST at least once per IB months.

i H

i V0GTLE UNITS - 1 & 2 3/4 3-71 Amendment No. 55 (Unit 1) l' Amendment No. 34 (Unit 2)

I i

TABLE 3.3-11 HIGH-ENERGY LINE BREAK INSTRUMENTATION Isolation Instrument Minimum Applicable Function Channel Channels Operable Modes 1.

Electric Steam

/" 19722A (RD52) 1 Boiler Isolation i! :1723A (RD52)

~

(Common Instrumentation)

A.c 197220 (RC65) 1 ATE 19723C (RC64)

ATE 19722D (RC67) 1 ATE 19723D (RC66)

AFT 19722 1

AFT 19723 ATE 19722E (RC95) 1 ATE 19723E (RC95)

Minimum Isolation Instrument Instrument Channels Applicable Function Channel (Unit 1)

Channel (Unit 2) Operable Modes 2.

Steam Generator TE 15212A (RBOB)

TE 15212A(RB131) 1 1,2,3,4 Blowdown Line TE 15216A (RB08)

TE 15216A(RB131)

IS I" TE 152128 (RC106) TE 152128(RC103) 1 1,2,3,4 TE 15216B (RC106) TE 15216B(RC103)

TE 15212C (RC107) TE 15212C(RC101) 1 1,2,3,4 TE 15216C (RC107) TE 15216C(RC101)

TE 15212D (RC108) TE 152120(RC102) 1 1,2,3,4 TE 152160 (RC108) TE 15216D(RC102)

FT 15212A (Loop 1) FT 15212A(Loop 1) 3 1,2,3,4 FT 15216A FT 15216A FT 152128 (Loop 2) FT 15212B(Loop 2) 1 1,2,3,4 FT 15216B FT 15216B FT 15212C (Loop 3) FT 15212C(Loop 3) 1 1,2,3,4 FT 15216C FT 15216C FT 152120 (Loop 4) FT 15212D(Loop 4) 1-1,2,3,4 FT 15216D FT 152160 3.

Letdor.' Line TC 15214A (A07)

TE 15214A(A100) 1 1,2,3,4 Isolation TE 15215A (A07)

TE 15215A(A100)

TE 152148 (A08)

TE 15214B(A101) 1 1,2,3,4 TE 15215B (A08)

TE 15215B(A101)

TE 15214C (A09)

TE 15214C(A103) 1 1,2,3,4 TE 15215C (A09)

TE 15215C(A103)

• Required during all MODES when electric steam boiler is in operation.

V0GTLE UNITS - 1 & 2 3/4 3-72 Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

~.

INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be OPERA 2!E.

APPLICABILITY:

H0 DES 1, 2*, and 3*.

ACYION:

a.

With one stop valve or one control valve per high pressure turbine steam line inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one valve in the affected steam lines, or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.

SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.

4.3.4.2 The above requirid Turbine Overspeed Protection System shal! be demonstrated OPERABLE:

a.

At least once per 7 days while in H0DE 1 and while in H0DE 2 with the turbine operating, Ly cycling each of the following valves through at least one complete cycle from the running position:

1)

Four high pressure turbine stop valves, 2)

Six low pressure turbine intermediate stop valves, and 3)

Six low pressure turbine intercept valves, b.

At least once per 31 days while in H00E 1 and while in H0DE 2 with the turbine operating, by direct observation of the movement of each of the above valves and the four high pressure turbine control velves, through one complete cycle from the running position, c,

At least once per 18 months by performance of a CHANNEL CALIBRATION on the Turbine Overspeed Protection Systems, and d.

At least once per 60 months by disassembling each of the above valves (including the four high pressure turbine control valves) and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.

• Not applicable in H0DE 2 or 3 with all main steam line isolation valves and associated bypass valves in the closed position and all other steam flow paths to the turbine isolated.

V0GTLE UNITS - 1 & 2 3/4 3-73 Amendment No. 55(Unit 1)

Amendment No. 34(Unit 2)

3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION Specification 3/4.11.1.1 Deleted.

V0GTLE UNITS - 1 & 2 3/4 11-1 Amendment No.

55 (Unit 1)

Amendment No.

34 (Unit 2)

1 RADI0 ACTIVE EFFLUENTS i

DOSE Specification 3/4.11.1.2 Deleted 1

\\

V0GTLE UNITS - 1 & 2 3/4 11-2 Amendment No. 55 (Unit 1) l Amendment No. 34 (Unit 2)

RADI0 ACTIVE EFFLUENTS L10VID RADWASTE TREATMENT SYSTEM Specification 3/4.11.1.3 Deleted V0GTLE UNITS - 1 & 2 3/4 11-3

. Amendment No. 55

'(Unit 1) l Amendment No. 34 (Unit 2)-

RADI0 ACTIVE EFFLUENTS LJ0VID HOLDUP TANKS LlHITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each outside temporary tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICADILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any of the outside temporary tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, 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 Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.8.1.4.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVElllANCE 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 either the tank's contents at least once 3er 7 days when radioactive materials are being added to the tank or each aatch of radioactive material prior to its addition to the tank.

V0GTLE UNITS - 1 & 2 3/4 11-4 Amendment No. 55 (Unit-1) l Amendment No. 34 (Unit 2):

1 RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENIS DOSE RATE Specification 3/4.11.2.1 Deleted V0GTLE UNITS - 1 & 2 3/4 11-5 Amendment No. 55 (Unit 1) l Amendment No. 34.(Unit-2) i m

y t--9 y

w-m-

+-*+

m w.

RADI0 ACTIVE EFFLUENTS DOSE - N0BLE GASES Specification 3/4.11.2.2 Deleted i

i I

V0GTLE UNITS - 1 & 2 3/4 11-6 Amendment No. 55 (Unit _1) l Amendment-No. 34 (Unit 2)

fM010 ACTIVE EFFLUENTS EQ$E - 10DJffE-131. 10 DINE-133. TRITIUM AND RAD 10ACTI.YE MATERIAL IN PARTICULATE f0E6 Specification 3/4.11.2.3 Deleted V0GTLE UNITS - 1 & 2 3/4 11-7 Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

V /

I RADI0 ACTIVE EFFLUENTS GASLQUS RADWASTE TREATHENT SYSTEM Specification 3/4.11.2.4 Deleted V0GTLE UNITS - 1 & 2 3/4 11-8 Amendment No. 55 (Unit 1) l Amendment No. 34 (Unit 2)

1 RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE llMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the CASE 0VS WASTE PROCESSING SYSTEM sFall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILIll: At all times.

ACTION:

a.

With the concentration of oxygen in the GASEOUS PROCESSING SYSTEM greater than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, b.

With the concentration of oxygen in the GASE0US WASTE PROCESSING SYSTEM greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend oxygen addition and all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 4% by volume, then take ACTION a.,

above.

c.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVElllANCE RE0VIREMENTS 4.11.2.S The concentrations of hydrogen and oxygen in the GASEOUS WASTE PROCESSING SYSTEM shall be determined to be within the above limits by continuously monitoring the waste gases in the GASEOUS WASTE PROCESSING SYSTEM with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-10 of Specification 3.3.3.10.

V0GTLE UNITS - 1 & 2 3/4 11-9 Amendment No. 55 (Unit 1) l Amendment No. 34 (Unit 2)-

RADI0 ACTIVE EFFLUENTS GAS DECAY TANKS LIMITING CONDITION FOR OPERATION 3.11.?.6 Thequantityofradioactivitycontainedjneachgasdecaytank shall be limited to less than or equal to 2.0 x 10 curies of noble gases (considered as Xe-133 equivalent).

APELLC_AJILITY:

At all times.

ACTION:

a.

With the quantity of radioadive material in any gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank, 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 Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.8.1.4.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radie4ctive material contained in each gas decay tank shall be determined to be within the abovc limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materir.ls have been added to the tank during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, r<

V0GTLE UNITS - 1 & 2 3/4 11-10 Amendment No. 55 (Unit 1) l Amendment No. 34 (Unit 2)

RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0 ACTIVE WASTES Specification 3/4.11.3 Deleted V0GTLE UNITS - 1 a 2 3/4 11-11 Amendment No. 55 (Unit 1) l Amendment No. 34 (Unit 2)

RADI0 ACTIVE EFFlVENTS 3/4.11.4 TOTAL DOSE Specification 3/4.11.4 Deleted l

V0GTLE UNITS - 1 & 2 3/4 11-12 Amendment No. 55 (Unit 1) l Amendment No. 34 (Unit 2)

1

3/4.12= RADIOLOGICAL ENVIRONMENTAL MONITORING k

3/4.12.1 MONITORING PROGRAM Specification 3/4.12.1 Deleted-V0GTLE UNITS - 1 & 2 3/4 12-1 Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

RADIOLOGICAL ENVIRONMENTAL HONITORING 3/4.12.2 LAND USE CENSUS Specification 3/4.12.2 Deleted-

+

V0GTLE UNITS - 1 & 2 3/4 12-2 Amendment No. 55.(Unit 1)

[

Amendment No. 34 (Unit 2)

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM Specification 3/4.12.3 Deleted 1

l:

V0GTLE UNITS - 1 &'2 3/4 12-3 Amendment No. 55 (Unit 1) l Amendment No. 34 -(Unit 2)

INSTRUMENTATION BASES REMOTE-SHUTOOWN SYSTEM-(Continued) outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR Part 50.

The OPERABILITY of the Remote Shutdown System ensures that a fire will.

not preclude achieving safe shutdown.

The Remote 5'iutdown. System instrumenta-tion, control, and transfer switches necessary to aliminate effects of the

'fre and allow operation of instrumentation, and control circuits required to dChieVe and maintain a safe shutdown Condition are independent of areas Where a fire could damage systems normally used to shut down the reactor.

This capability is consistent with General Design Criterion 3'and CMEB 9.5.1.

3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitori_ng instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

This capability is consis-tent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and =

Following an Accident, Revision 2, December 1980 and NUREG-0737, " Clarification of TMI Action Plan Requirements," November 1980.

The instrumentation listed in Table 3.3-8 corresponds to the Category 1-instrumentation for which selection, design, qualification and display criteria are described in Regulatory Guide 1.97, Rev. 2.

3/4.3.3.7 CHLORINE DETECTION SYSTEMS The OPERABILITY of the Chlorine Detection Systems 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, Revision 1, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," January 1977.

This capability will not be required if the quantity of chlorine gas

< 20 lbs.) and utilized for laboratory and calibration stored on site is small (Tity is consistent with the exclusions and recommenda-purposes.

This applicabi tions of Regulatory Guide 1.95, Revision 1, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," January 1977.

3/4.3.3.8 LOOSE PARTS DETECTION SYSTEM Not used.

3/4.3.3.9 RADI0 ACTIVE LIQL'ID EFFLUENT MONITORING INSTRUMENTATION Not used.

V0GTLE UNITS - 1 & 2 8 3/4 3-5 Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

1 INSTRUMENTATION BASES 3/4.3.3.10 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the GASE0US WASTE PROCESSING SYSTEM.

The OPERABILITY and use of this instrumentation is consis-tent with the requirements of General Design Criteria 60 and 63 of Appendix A to 10 CFR Part 50.

3/4.3.3.11 HIGH ENERGY LINE BREAK ISOLATION SENSORS The operability of the high energy line break isolation sensors ensures that the capability is available to promptly detect and initiate protective action in the event of a line break.

This capability is required to prevent damage to safety-related systems and structures in the auxiliary building.

3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.

Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment or structures.

V0GTLE UNITS - 1 & 2 B 3/4 3-6 Amendment No. 55 (Unit 1)

)

Amendment No. 34 (Unit 2)

,,ns+

n 5

3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION Not used.

3/4.11.1.2 00SE Not used.

4 l

l V0GTLE UNITS - 1 & 2 B 3/4 11-1 Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM Not used.

3/4.11.1.4 LIQUID HOLOUP TANKS The tanks listed in this specification include all those outdoor radwaste 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.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

/

V0GTLE UNITS - 1 & 2 B 3/4 11-2 Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 DOSE RATE Not used.

3/4.11.2.2 DOSE - NOBLE GASES Not used.

V0GTLE UNITS - 1 & 2 B 3/4 11-3 Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.3 DOSE - IODINE-131, 10 DINE-133, TRITIUM, AND RADI0 ACTIVE MATERIAL IN PATTICilLATE FORM Not used.

V0GTLE UNITS - 1 & 2 8 3/4 11-4 Amendment No. 55 (Unit 1)'

Amendment No. 34 (Unit 2)

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.4 GASE0US RA0 WASTE TREATMENT SYSTEM Not used.

3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of poten-tially explosive gas mixtures contained in the GASEOUS WASTE PROCESSING SYSTEM is maintained below the flammability limits of hydrogen and oxygen.

Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits.

These automatic control features include isolation of the source of hydrogen and/or oxygen.

Maintaining the concentration of hydrogen and oxygen 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 11.2.6 GAS DECAY TANKS The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification.

Restricting the quantity of radioactivity contained in each gas decay tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting whole body exposure to a MEMBER OF THE PUBLIC at the nearest SITE B0UNDARY will'not exceed 0.5 rem.

This is consistent with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, " Postulated Radioactive Releases Due to a Waste Gas System Leak or failure," in NUREG-0800, July 1981.

V0GTLE UNITS - 1 & 2 B 3/4 11-5 Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

RADI0 ACTIVE-EFFLUENTS BASES 3/4.11.3 SOLID RADI0 ACTIVE WASTES Not used.

3/4.11.4 TOTAL DOSE Not used.

1 V0GTLE UNITS - 1 & 2 8 3/4 11-6 Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM Not used.

3/4.12.2 LAND llSE CENSUS 3

Not used.

l 1

i i

i i

V0GTLE UNITS - 1 & 2 B 3/4 12-1 Amendment No.

55 (Unit 1)

Amendment No.

34 (Unit 2)

RADIOLOGICAL ENVIRONMENTAL MONITORING-BASES 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM Not used.

V0GTLE UNITS - 1 & 2 B 3/4 12-2 Amendment No. 55 (Unit 1)

- Amendment No. 34' (Unit 2)

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ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 1)

Identification of a sampling schedule for the critical variables and control points for these variables, 2)

Identification of the procedures used to measure the values of the critical variables, 3)

Identification of process sampling points, 4)

Procedures for the recording and management of data, 5)

Procedures defining corrective actions for all off-control point chemistry conditions, and 6)

A procedure identifying:

(a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action, d.

Post-Accident Sampling 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:

1)

Training of personnel, 2)

Procedures for sampling and analysis, and 3)

Provisions for maintenance of sampling and analysis equipment.

e.

A program which will ensure the capability to monitor plant variables and systems operating status during and following an accident.

This program shall include those instruments provided to indicate system operating status and furnish information regarding the release of radioactive materials (Category 2 and 3--instrumentation as defined-in Regulatory Guide 1.97 Revision 2) and provide the following:

1) preventive maintenance and periodic surveillance of instrumentation.

2) pre planned operating procedures and back-up instrumentation to be used if one or more monitoring instruments become inoperable.

3) administrative procedures for returning inoperable instruments-to OPERABLE status as soon as practicable.

f.

Radioactive Effluent Controls Program i

A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents alv. f or maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably V0GTLE UNITS - 1 & 2 6-16 Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS-(Continued) achievable.

The program (1) shall be contained in the ODCH, (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 set-point determination in accordance with the methodology in the

ODCM, 2)

Limitations on the concentrations of radioactive material re-leased in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 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 in 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 from each unit to UNRESTRICTED AREAS conform-ing to Appendix I to 10 CFR Part 50, 5)

Determination of cumulative and projected dose contributions from radioactive effluents for 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 portions of these systems are used to reduce releases of radioactivity when the projected-doses in a 31-day period would exceed 2 per-cent 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, Appen-dix B, Table II, Column 1, 8)

Limitations on the annual and quarterly air doses.resulting from noble gases released in gaseous effluents from each unit 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 from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and V0GTLE UNITS - 1 & 2 6-16a Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

ADMINISTRATIVE CONTROLS

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.

g.

Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.

The program shall provide (1) represen-tative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent moni-toring 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 methodol-ogy and parameters in the ODCM, 2)

A Land ilse Census to ensure that changes in the use of areas at and beyond the SITE B0UNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3)

Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accurecy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program j

for environmental monitoring.

I V0GTLE UNITS - 1 & 2 6-16b Amendment No. 55 (Unit 1) l l

Amendment No. 34 (Unit 2)

ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) surveillance, inservice inspection, routine maintenance, special maintenance [ describe maintenance], waste processing, and refueling).

The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements.

Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80%

of the total whole-body dose received from external sources should be assigned to specific major work functions; b.

The results of specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4.8.

The following information shall be included:

(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radio-iodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit.

Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration (pCi/gm) and one other radioidine isotope concentration (pCi/gm) as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

c.

A report shall be prepared and submitted to the commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination.

ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT ***

6.8.1.3 The Annual Radiological Environmental Surveillance 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 summaries, 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.

• • • A single submittal may be made for Units 1 and 2.

V0GTLE UNITS - 1 & 2 6-18 Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ****

l-6.8.1.4 The Semiannual Radioactive Effluent Release Report covering the opera-tion of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year.

The report shall in-clude a summary of the quantities of radioactive liquid and gaseous effluents-and solid waste released from the unit.

The material provided shall_be (1) con'*

sistent 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.

• • • • A single submittal may be made for Units 1 and 2.

The submittal should combine those sections that are common to both units at the plant; however, the submittal shall specify the releases of gaseous and liquid radioactive material from each unit and of solid radioactive material from the site.

V0GTLE UNITS - 1 & 2 6-19 Amendment No. 55 (Unit 1)

Amendment.No. 34 (Unit 2)-

i ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORTS 6.8.1.5 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs-or safety valves, shall be-submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with' a copy to the Regional Administrator of the Regional Office of the NRC, no later-than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT 6.8.1.6 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR) before each reload cycle or any remaining part of a reload cycle for the following:

a.

SHUTDOWN MARGIN LIMIT FOR MODES 1 and 2 for Specification 3/4.1.1.1, b.

SHUTOOWN MARGIN LIMITS FOR MODES 3, 4 and 5 for Specification 3/4.1.1.2, c.

Moderator temperature coefficient BOL and E0L limits and 300 ppm surveillance-limit for Specification 3/4.1.1.3, d.

Shutdown Rod Insertion Limit for Specification 3/4.1.3.5, e.

Control Rod Insertion Limits for Specification 3/4.1.3.6, f.

Axial Flux Difference Limits for Specification 3/4.2.1, g.

Heat Flux Hot Channel Factor, K(Z) and W(Z), for Specification 3/4.2.2, h.

Nuclear Enthalpy Rise Hot Channel Factor Limit-and the Power Factor Multiplier for-Specification 3/4.2.3.

The analytical methods used to determine the core operating limits shall be those previously approved by the NRC in:

V0GTLE UNITS - 1 & 2 6-20 Amendment No. 55 (Unit 1) l Amendment No. 34 (Unit 2).

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) a.

WCAP 9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY",

July 1985 (y for Specifications 3.1.1.3 - Moderator _ Temperature -

W Proprietary).

(Methodolog Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3,1.3.6 -

Control Bank Insertion Limits and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)

WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONT b.

SURVEILLANCE TECHNICAL SPECIFICATION", June 1983_(W Proprietary (Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(Z) surveillance requirements for F Methodology).)

q c.

WCAP-9220-P-A, Rev. 1, " WESTINGHOUSE ECCS EVALUATION M00EL-1981 VERSION", February 1982 (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions-or supplements thereto, 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 6.8.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

l l

l V0GTLE UNITS - 1 & 2 6-21 Amendment No. 55 (Unit 1) l Amendment No. 34 (Unit 2)

ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) h.

Records of inservice inspections performed pursuant to these Technical Specifications; i.

Records of quality assurance activities required by the Final Safety Analysis Report; j.

Records of reviews performed for changes made to proceduras or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59; k.

Records of meetings of the PRB and the SRB; 1.

Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the ser-vice life commences and associated installation and maintenance records; m.

Records of secondary water sampling and water quality; and n.

Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date.

This should include procedures effective at specified times and QA records showing that these procedures were followed.

o.

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

6.10 RADIATION PROTECTION PROGRAM 6.10.1 Procedures for personnel radiation prctection 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.

6.11 HIGH RADIATION AREA 6.11.1 Pursuant to paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the "cora rol device" or " alarm signal" required by paragraph 20.203(c),each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radia-tion is greater tnan 100 mrem /hr but less than 1000 mR/h at 45 cm (18 in.)

from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).

Individuals qualified in radiation protection procedures (e.g.,

Health Physics Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates greater than 100 mrem /hr but less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area; or V0GTLE UNITS - 1 & 2 6-23 Amendment No. 55 (Unit 1) l Amendment No. 34 (Unit 2)

ADMINISTRATIVE CONTROLS 6.11 HIGH RADIATION AREA (Continued) b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or c.

An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Health Physics Superintendent in the RWP.

6.11.2 In addition to the requirements of Specification 6.11.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.)

from the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift Foreman on duty and/or health physics supervision.

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area.

In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

For individual high radiation areas accessible to personnel with radiation levels of greater.than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.

6.12 PROCESS CONTROL PROGRAM (PCP) 6.12.1 The PCP shall be approved by the Commission prior to implementation.

6.12.2 Licensee-initiated changes to the PCP:

a.

Shall be-documented and records of reviews performed shall be retained as required by Specification 6.9.30.

This documentation shall coni.ain:

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 con-formance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

V0GTLE UNITS - 1 & 2 6-24 Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

ADMINISTRATIVE CONTROLS 6.12 PROCESS CONTROL PROGRAM (PCP) (Continued) b.

Shall become effective after review and acceptance by the PRB and the approval of the General Manager-Nuclear Plant.

6.13 0FFSITE DOSE CALCULATION MANUAL (00CM) 6.13.1 The ODCM shall be approved by the Commission prior to implementation.

6.13.2 Licensee-initiated changes to the' ODCH:

a.

Shall be documented and records of reviews performed shall-be retained as required by Specification 6.9.30. -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 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 adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations, b.

Shall become effective after-review and acceptance by the PRB and the approval of the General Manager-Nuclear Plant.

c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCH as a part of or concu'rrent with the Semiannual 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.

6.14 MAJOR CHANGES TO LIQUID, GASE0US, AND SOLID RADWASTE TREATMENT SYSTEMS Not used.

V0GTLE UNITS - 1 & 2 6-25 Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

,