ML20056C747

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Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual
ML20056C747
Person / Time
Site: Millstone, Haddam Neck  File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 07/16/1993
From:
CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20056C746 List:
References
NUDOCS 9307220324
Download: ML20056C747 (47)
v • d • e


Text

rs Docket No. 50-213 814532

.t Haddam Neck Plant Proposed Revision to Technical Specifications.

1 Radioactive Effluent Release Report Markup Pages 9

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July 1993 9307220324 930716 ~

PDR ADOCK 05000213

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May 27, 1993 ADMINISTRATIVE CONTROLS SECTION f.gl 6-9 Audits..................................................

6-10 Authority...............................................

6-10 Records.................................................

6.6 REPORTABLE EVENT ACTI0N.................................

6-11 6.7 SAFETY LIMIT VIOLATION..................................

6-11 6.8 PROCEDURES AND PR0 GRAMS.................................

6-11 6.9 REPORTING RE0VIREMENTS 6-13 6.9.1 Routine Reports.........................................

6-13 Startup Report..........................................

6-13 An n u al R e p o r t s..........................................

Annual Radiological Environmen 1 Operating Report......

6-14

=i:nnue, adioactive Effluen

...le::. Report..........

6-15

^ MonthfyOperatingReports...............................

6-15

~

Technical Report Supporting Cycle Operation.............

6-15 S p e c i al Re p o rt s.........................................

6-17 6.10 RECORD RETENTION........................................

6-17 6.11 RADIATION PROTECTION PR0 GRAM............................

6-18 6.12 HIGH RADIATION AREA.....................................

6-19 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM)............................

6 6.14 RADI0 ACTIVE WASTE TREATMENT.............................

6-20 6.15 SYSTEMS INEGRITY........................................

6-21 6.16 PASS / SAMPLING AND ANALYSIS OF PLANT EFFLUENTS...........

6-21 HADDAM NECK XIX Amendment No. J U, J g,158 e ea i

i

INSTRUMENTATION RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with applicable Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The Alarm / Trip Setpoints shall be determined in accordance with-methodology and parameters described in the OFFSITE DOSE CALCULATION MANUAL (0DCM).

APPLICABILITY: At all times *.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the Alarm / Trip Setpoint so it is acceptably conservative.

b.

With the number of channels less than the minimum channels operable requirement, take the ACTION shown in Table 3.3-9.

Exert best efforts to restore the inoperable monitor to OPERABLE status in days, and, if unsuccessful, explain in the next-knaual # Lic. i - ;..r = Effluent Report why the inoperability.was not

~ "co e in a timely manner.

Releases need not be terminated after 30 days provided the specified actions are continued.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUIREMENTS 4.3.3.7.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK' CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-7.

At all times means that channel shall be OPERABLE and in service on a continuous, uninterrupted basis, except that outages are permitted for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> each time for the purpose of maintenance and performance of required tests, checks, calibrations or sampling.

s HADDAM NECK 3/4 3-44 Amendment No. 125

APR 2 61990 INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION' LIMITING CONDITION FOR OPERATION 3.3.3.8-The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE with applicable Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.

The setpoints shall be determined in accordance with the methodology and parameters as described in the ODCM.

APPLICABILITY: At all times *.

ACTION:

With a radioactive gaseous effluent mo'nitoring instrumentation a.

channel Alarm / Trip Setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the Alarm / Trip Setpoint so it is acceptably conservative.

b.

With the number of channels less than the minimum channels operable requirement, take the ACTION shown in Table 3.3-10.

Exert.best efforts to restore the inoperable. monitor to OPERABLE at t in 30 days and, if unsuccessful, explain in the next kuuk 22.i =n=1 Effluent Report why the inoperability was not

- - ^

rrec in a timely manner. Releases need not be terminated after 30 days provided the specified actions are continued.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.3.3.8.1 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-8.

At all times means that the channel shall be OPERABLE and in service on a continuous basis, except that outages are permitted for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> each time for the purpose of maintenance and performance of required tests, checks, calibrations.

i HADDAM NECK 3/4 3-49 Amendment No.-125

e no/25/92 i

ADMINISTRATIVE CONTROLS

~

P SEMIAN"UAl-RADI0 ACTIVE EFFLUE RELEASE REPORT

)

6.9.1.7houtine YnIval-Radioactive Efflyenbe4 ease-Report [ covering the-operation of the facility during the previoushyhs-of operation shall be 7-submitted ::ithin 50 days--arf 4er--January I :nd hly I of each year.

g caknde qw AA--sup:lemental--report-contraining-dese-assec: ent: for-the-prev 4eu: ye:r :ha -9 bc :u =iited :nnua14y-*Fthin 00 day: :f-ter-January-h The report shall include that information delineated in the REMODCM.

A Any changes to the REMODCM shall be submitted in the%mw annual Radioactive Effluent -Releas Report.

MONTHLY OPERATING REPORTS 6.9.1.8 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commis-i sion, Document Control Desk, Washington, D.C. 20555, with one copy to the appropriate Regional Office of the NRC, and one copy to the appropriate NRC i

Resident Inspector, no later than the 15th of each month following the calen-1 dar month covered by the report.

TECHNICAL REPORT SUPPORTING CYCLE OPERATION 6.9.1.9.a Core operating limits shall be established and documented in the TECHNICAL REPORT SUPPORTING CYCLE OPERATION before each reload cycle or any remaining part of a reload cycle for the following:

1.

Moderator Temperature Coefficient for Specification 3.1.1.5.

2.

Moveable Control Assemblies--Bank Height for Specification 3.1.3.1.

3.

Control Group Insertion Limits--Four Loops Operating, control banks for Specification 3.1.3.6.1.

4.

Control Group Insertion Limits--Three Loops Operating, control banks for Specification 3.1.3.6.2.

5.

Axial Offset--Four Loops Operating for Specifications 3/4.2.1.1.

6.

Axial Offset--Three Loops Operating for Specifications 3/4.2.1.2.

7.

Linear Heat Generation Rate--Four Loops Operating for Specifica-tions 3/4.2.2.1.

8.

Linear Heat Generation Rate--Three Loops Operating for Specifica-tions 3/4.2.2.2.

HADDAM HECK 6-15 Amendment No. J #, 153,155 core

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W M,-'* ADMIN 1STRATIVE CuhTROLS' 4

RADIOLOGICAL EFFLUENT MONITORING'AND OFFSITE DOSE

' 6.13

- CALCULATION MMUAL -(REM 00CM):

the

)

7 I,= - Radiological! Effluents Menitoring. Manual, shall. -outline sampling and-analysis programs" to dr/cernine the concentration of'

~

~

Section materials? released. offsite.: as wulthose exposure pathwa facility ~ operation.

-It: - sh11 also J

RADIDACTIVE WASTE TREATMENT. SYSTEMS and report content'.-

Section II, the Offsite Dose Calculation Manual, shall describe the

?

methodology and parameters to be used in the calculation of offsite. dose 1

due to radioactive gaseous. and liquid effluents and in the -calculationsJ o gaseous and liquid effluent monitoring instrumentation : AlarnVTrip Se

'?

consistent with the applicable LCO's cont'ained - in these ' Technical-

l Specifications.

1 Changes to the REMODCM:

l Shall be documented and records of reviews performed shall-b'e. retai as required by Specification 6.10.3.m.

This documentation. shall l

s a.

1

-contain:

f Sufficient information to. support the change together with 1 the-j appropriate analyses or evaluations justifying the' change (s), Land 1)

A determination that the change will'_ maintain the-level :of' l

radioactive. effluent' control required by 10 CFR 20.106c 40: CFR; 2)

Part 190,10 CFR 50.36a, and Appendix I to.10CFR Part : 50 and~ not' - ::

adversely impact the accuracy or reliability of: effluent,idose, or l

setpoint calculations.

the'.~

become effective after review and acceptance by _PORC and t

li l b.

Shall Haddam Neck.

approval of the Vic

.3 Auuum_

Shall be submitte t the Commissi n in the form of om lete, legible l

copy of the ent r REMM or_ ' 0DCM T asD appropriate as rt : of or; j

c.

concurrent with L;M=P R ioactive Effluent., h=

port : for-D ch any change was

.A

_ ach change.'

the period of the shall be identified by' markings in the margin' of Lthe' affected pages, clearly indicating the area of. the page; that.. was-changed, a and.sha; indicate the date (e.g., month / year) the change wa's implemented.

6.14 RADIDACTIVE WASTE-TREATMENT

j Procedures for liquid and gaseous radioactive-effluent Edischarges from. th maintained
and. ' adhered to M for' all
facility shall be prepared,. approved, releases of radioactive 1 effluents.-

These 1

operations : involving' offsiteprocedures shall specify the use. of a j

' SYSTEMS utilizing the guidance.provided~in=the REMODCM..

- The' SoliG RADI0 ACTIVE WASTE TREATMENT SYSTEM shall' be ope trith the PROCESS CONTROL PROGRAM to process-wet radioactive wastes shipping and burial ground requirements.

Amendment _ No. JJJ,'. JJJ.158 6-20' HADDAM NECK-y 0142' 1

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Dock'et No. 50-245

--gjf532 Millstone Unit No. 1 Proposed Revision to Technical Specifications Radioactive Effluent Release Report-Markup Pages July 1993

November 8, 1989 t

LIMITING CONDITION FOR OPERATION 3.8 RADIDACTIVE MATERIALS A.

Radioactive Liouid Effluent Instrumentation 1.

The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.8-1 shall be OPERABLE with applicable alarm / trip setpoints set to ensure that the limits of Specification 3.8.C.1 are not exceeded. The setpoints shall be determined in accordance with methods and parameters as described in the ODCM.

Applicability As shown in Table 3.8-1.

Action:

1.

In the event of a limiting condition for operation and/or associated action requirement cannot be satisfied, this shall not require unit shutdown or prevent a change in operational modes.

2.

With a radioactive liquid effluent monitoring instrunicntation channel alarm / trip setpoint less conservative'than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

3.

With the number of channels less than the minimum channels OPERABLE requirement, take the action shown in Table 3.8.1.

Exert best efforts to restore the inoperable monitor NRABLr tatus within 30 days and, if unsuccessful, explain in the nef 1 i m u2.

ffluent Report why the inoperability was not correcte in a kimely man er.

Releases need not be terminated after 30 days provi th specifie actions are continued.

SUEVEILLANCE REQUIREMENTS 1

4.8 RADI0 ACTIVE MATERIALS 4

A.

Kadioactive Liauid Effluent Instrumentation 1.

Each radioactive liquid effluent monitoring instrumentation channel

-i shall be demonstrated OPERABLE by performance of the INSTRUMENT CHECK, INSTRUMENT CAllBRATION, INSTRUMENT FUNCTIONAL TEST, and SOURCE CHECK operations at the frequencies shown in Table 4.8-1.

Millstone Unit I s/4 B-2 Amendment No. 39

November 8, 1989 LIMITING CONDITION FOR OPERATION 3.8 RADI0 ACTIVE MATERIALS B.

Radioactive Gaseous Effluent Monitorino Instrumentation 1.

The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.8-2 shall be OPERABLE with applicable alarm / trip setpoints set to ensure that the limits of Specification 3.8.D.1 are not exceeded. The setpoints shall be determined in accordance with methods and parameters as described in the ODCM.

Acolicability: As shown in table 3.8-2.

Action:

1.

In the event of a limiting condition for operation and/or associated action requirement cannot be satisfied, this shall not require unit shutdown or prevent a change in operational modes, except for Table 3.8-2 action B statement for SJAE off-gas monitor.

With a radioa:tive gaseous effluent monitoring instrumentation u.

cnannel alarm : 1: setpoir.1 less conservative than required by the above ' Specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpiont so it is acceptably conservative.

b.

With the number of channels less than the minimum channels operable requirements, take the action shown in Table 3.8-2.

Exert best efforts to restore the inoperable' monitor to OPERA s te ithin 30 days and, if unsuccessful, explain in the nex Ged = :1 -

Effluent Report why the inoperability was not co ecthd in a time manner.

Release need not be terminated after 30 ys provided th specified actions are continued.

SOMUAL l

SURVEILLANCE REQUIREMENTS q

4.8 RADIDACTIVE MATERIALS B.

Radioactive Gaseous Effluent Instrumentation 1.

Each radioactive gaseous effluent monitoring instrumentation channel j

shall be demonstrated OPERABLE by performance of the INSTRUMENT CHECK, INSTRUMENT CAllBRATION, INSTRUMENT FUNCTIONAL TEST, and SOURCE CHECK operations at the frequencies shown in Table 4.8-2.

i Millstone Unif 1, 3/4 8-6 Amendment No. 39

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~ ADMINISTRATIVE CONTROLS Annual Radiolooical~ Environmental Doeratino Report

'6.9.1.7 Routine > Annual-Radiological Environmental Operating reports covering the operation of the unit during the previous calendar year shall be submitted. prior to.May 1 of each year. -

The Annual Radiological Environmental Operating Report shall include-that=information delineated in the-REMODCM.:

kuuum A ain=Q adioactive Effluen_

4sso Reno SMage ;

S W

"youtine Np.ortIc.overing the operation adioactive fluent 6.g.1.

of the unit during the previous 0 n:th:-of operation shall be submittedf

{ hy: fter Junry I' nd J ly I of each year.

D ;sppl. natal i gert centeining de;; e;;es.;n at; fer the pra in; By er th:11 5: er itt M e re:11y eithir 90 h y: efter hertry 1.

The report shall include that~ information delineated in the REMODCM.

Any changes'to the RE hall be submitted in th inh--@ > -

Radioactive Effluent "einn ort.

b Suoolemental Reload-Licensina Submi ta 6.9.1.9 Core power distribution 11.;;.ls (MCPR, LHGR, and-APLHGR);shall bei established and documented in the Supplement Reload Licensing' Submittal before each reload cycle or any remaining part ofJa reload cycle. The analytical methods used to determine these 11mits.shall' be those previously reviewed and approved by the NRC in NEDE-240ll,.

General Electric Standard Application for Reactor Fuel, latest approved revision. Thel core power distribution limits shall' be determined so that all' applicable limits (e.g., fuel thermal-mechanical;11mits, ECCS limits,.~ nuclear limits such as shutdown margin, and transient 1and accidents analysesL11mits) of the safety analysis are met.. The Supplemental Reload Licensing.-

Submittal, including any mid-cycle revisions or supplements thereto, shall be submitted upon issuance.

Special Reoorts

6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission Document Control Desk. Washington,- D.C. 120555,'one copy to the Regional ~ Administrator, Region I, and one copy:to the NRC -

Resident Inspector, within the. time period specified for each, report. ' These reports shall. be' submitted ~ covering the-activities-identified below pursuant:to the requirement of the. applicable-

' reference specification:

-a.

In-service Inspection Results. Specification-4.6.F.

= Millstone Unit 1 6-18 Amendment No. J. 27,'JS, ff, c

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' August? 28,H 1992 -

2 ADMINISTRATIVE ONTROLS-j

~

. 6;15 RADIOLOGICAL EFFLUENT " MONITORING' AND-': OFFSITE : DOSE J CALCULATION. ' MANUAL.

1 (REMODCM)!

r 1

SectionIIL Radiological ~ Effluents Monitoring: Manual: (REffi), shall outline the.

J

. sampling andt analysis-- programs to determine the concentration. of radioactive;

~

. materials released offsite as well as dose commitments to individuals in those exposure pathways andxfor those radionuclides released as a res' ult:of' station operation.: 'It shall also specify operating guidelines forL radioadtive waste 1

-)

' treatment systems.and report content.

Section II the.0ffsite Dose Calculation Manual -(ODCM),ishall - de' scribe the-

- methodology and-ptrameters to be -used in the' calculation of offsite dosesJdue' q

to radioactive gaseous and liquid effluents and-in the calculations of gaseous' and liquid effluentt monitoring instrumentation alars/ trip setpoints consistent--

with the applictble.LCO's contained in these technical; specifications. -

Changes to the REMODCM:

+

a.

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

This documentation =

shall contain:

,j 1)

Sufficient information to support the change together with the"

>u At Effluent Report why the inoperability was not corrected in a t me manner. Releases need not be terminated after 30 days provided the specified actions are continued.

The provisions of Specification 3.0.3 are not applicable.

c.

SURVEILLANCE REOUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL ' CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12.

l 1

i MILLSTONE

. UNIT 2 3/43-50 Amendment No. Jgf,151

v; February 26, 1991 e

INSTRUMENTATION

' RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION

~

3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels

.sh:wn in Table 3.3-13 shall be OPERABLE with applicable alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 a're not exceeded. The setpoints shall be determined in accordance with' methods and parameters as described in the ODCH.

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation l

channel alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or l

declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With the number of channels less than the minimum channels (OPERABLE requirement, take the ACTION shown in Table 3.3-13.

Exert best efforts to restore the inoperable monitor to OPERABLE st 30 days and, if unsuccessful, explain in the next Semiannt L*-

ou na-Effluent Report why the inoperability was not corrected.in u.

Releases need not be terminated after 30 days provided the manner.

specified actions are continued.

The provisions of Specification 3.0.3 are not applicable.

c.

SURVEILLANCE REOUIREMENTS 4.3.3.10 Each ' radioactive gaseous effluent. monitoring instrumentation channel l

shall ' be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

9 Y

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.HILLSTONE - UNIT 2 3/4 3-56 Amendment No. JEf,151

August 28, 1992 4 ' ADMINISTRATIVE CONTROLS d.

Documentation of all failures (inability to lift or reclose within the

'o tolerances allowed by the design basis) and challenges to the pressurizer PORVs or safet valves.

MMk MONTHLYJ)PERATING REPORT 6.g..[

utine reports of operating statistics and shutdown experience shall i

submitted on. a monthly basis to the U.S. Nuclear Regulatory e

Commission, Document Control Desk, Washington, D.C. 20555, one copy to the Regional Administrator, Region I, and one copy to the NRC Resident Inspector, no later than the 15th of each month following' the calendar month covered by the report.

CORE OPERATING LIMITS REPORT Core operating limits shall be established and documented in the 6.g.

8 CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle.

3/4.1.1.1 SHUTDOWN MARGIN - T*V9 > 200*F 3/4 1.1.2 SHV DOWN MARGIN - T s 200'F 3/4.1.1.4 ModeratorTemperatuM9oefficient C

3/4.1.3.6 Regulating CEA Insertion Limits 3/4.2.1 Linear Heat Rate T

3/4.2.3 Total Integrated Radial Peaking Factor - Fr 3/4.2.6-DNB Margin b.

The analytical methods-used to detemine - the core. operating.

limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1)

XN-75-27(A),

latest Revisions and Supplements,

" Exxon Nuclear Neutronics Design-Methods for Pressurized Water Reactors,' Exxon Nuclear Company.

2)

XN-NF-84-73(P), latest Revision and Supplements, ' Exxon Nuclear. Methodology for Pressurized Water Reactors:-

Analysis of Chapter 15 Events," Exxon Nuclear Company.

3)

XN-NF-82-21(A),

latest Revision and Supplements,

" Application of Exxon Nuclear Company PWR Thermal Margin-Methodology to Mixed Core Configurations,' Exxon Nuclear Company.

4)

XN 84-g3(A), latest Revision _and Supplements, 'Steamline Break Methodology for PWR's, Exxon Nuclear Company.

S)

XN-75-32(A), Supplements 1, 2, 3, and 4,

' Computational Procedure for Evaluation Rod Bow," Exxon Nuclear Company.

6)

XN-NF-82-49(A), latest Revision,

" Exxon Nuclear - Company Evaluation Model EXEM PWR Small Break Model,' Exxon Nuclear Company.

MILLSTONE - UNIT 2 6-18 Amendment Nos. 75,'JJ, Jpf, 111, 115, 119, 63 Jgp, J)), JJg,1

INSERT A F

i ANNUAL RADIOACTIVE EFFLUENT REPOlT 6.9.1.6' A routine Annual Radioactive Effluent Report covering the operation of'the unit during the previous calendar year of operation shall be submitted by May 1 of~each year.

The report shall include that information delineated in the REMODCM.

Any changes to the REMODCM shall be submitted in the Annual Radioactive Effluent Report.

5 7

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Docket No.'50-423-B14532 p;

I

. Millstone Unit No. 3 Proposed Revision to Technical Specifications Radioactive Effluent Release Repo'rt Markup Pages b

i r

. July.1993

t 09/28/92 INDEX

= ADMINISTRATIVE CONTROLS SECTION Eaff 6.8 PROCEDURES AND PROCRAM5......................................'....

6-14 6.9 REPORTING RE0VIREMENTS...........................................

6-17 6.9.1 ROUTINE REP 0RTS................................................

6-17 6-17 Startup Report.................................................

6-18 An n u al R e p o rt s.................................................

nnual Radiological Environmental Operating Report.............

6-19 bauo%+an Radioactive Effluent 61 h:e Report.................

6-19 Monthly Operating Reports......................................

6-19 Core Operating Limits Report...................................

6-19 6.9.2 SPECIAL REP 0RTS................................................

6-21 6.10 R E C ORD R ET E NT I ON................................................

6-21

~

6.11 RADIATION PROTECT 10N PR0 GRAM....................................

6-22 6.12 HIGH RADIATION AREA.............................................

6-23 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM)....................................

6-24 6.14 RADI0 ACTIVE WASTE TREATMENT.....................................

6-24 MILLSTONE - UNIT 3 xx Amendment No. Ep,69 OC75 C

Octoost 25, 1990 INSTRUMENTATION RADIOACTIVE L10VID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The Alarm / Trip Setpoints of these channels shall be determined in accordance with the methodology and parameters as described in the REMODCM.

APPLICABILITY: As shown in Table 3.3-12 ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so' it is acceptably conservative.

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPEPABLE, take the ACTION shown in Table 3.3-12.

Exert best efforts to restore the inoperable instrumentation to OPERABLE sta 30 days

and, i f-Qgsful, explain in the next S=itanue7 adioactive Effluent Release-eport why the inoperabili y was not co etted in a timely ma e.

Releases need not be term ted aftir 30 ays provided the specified actions are continued.

Qg c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE001REMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPEPATIONAL TEST at~ the frequencies shown in Table 4.3-8.

MILLSTONE - UNIT 3 3/4 3-69 AmendmentNo.//,_57 L

M :[

+

- C October 25, 1990

~ INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be' 0PERABLE with their Alarm / Trip Setpoints set-to ensure that the limits of Specifications 3.11.2.1 'are not exceeded.

The Alarm / Trip Setpoints of these channels shall be determined in accordance with the methodology and parameters in the REMODCH.

APPLICABILITY: As shown in' Table 3.3-13 ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, without l delay suspend the release of radioactive gaseous effluents monitored by-the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With the number of OPERABLE radioactive gaseous effluent monitoring instrumentation channels less than the Minimum Channels. OPERABLE, take the ACTION shown in Table 3.3-13.

Exert best Lefforts J to restore the inoperable instrumentation to ' OPERABLE state HmueM oog 30 days and, if-explain in the next c

Radioactive Efflue

& h ::c-port why the inoperability wa n

corrected in a timel Releases need not be' terminated' after-30 ' days provided the specified actions are continued.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVElttANCE REOUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE

CHECK, CHANNEL-CALIBRATION and ANALOG CHANNEL ~ OPERATIONAL -TEST at the frequencies shown in Table 4.3-9.
h. -

l l MILLSTONE - UNIT 3 3/4 3-74 AMENDMENT NO. 57 L

upm ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued 1-duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the reactor coolant exceeded the radiciodine limit.

c.

Documentation of all challenges to the pressurizer power-operated relief valves (PORVs) and safety valves; and ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

The Annual Radiological Environmental Operating Reports shall include tpformation delineated in the REMODCH.

RADI0 ACTIVE EFFLUEN REPORT **

X"R W W ~

W 6.9.1.4 goutine4emtenual Radioactive EffluentMcle::e ReportIcovering the operation of the unit during the previous h'onths-of operation shall be submitted witMn 50 d:ys :f4cr J:nuary 1 :nd July 1 Of each year.

bw % 1.

Lcneuong q w A 50ppliaintti iEpart cGnt&ining dG5E E53E55 mint 5 TGi the prEVIOU5 ytef A sh:ll be submRted :nnu:lly dthin 90 day 3 after Jamery+.-

The report shall include that information delineated i he REM 0DCM.

auno Any change t the REMODCM shall be submitted in the nut Radioac-tive Effluen 4eha eport.

MONTHLY OPERATING REPORTS 6.9.1.5 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C.

20555, one copy to the Regional Administrator Region I, and one copy to the NRC Resident Inspector, no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS RFPORT 6.9.1.6.a Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

1.

Moderator Temperature Coefficient BOL and E0L limits and 300 ppm surveillance limit for Specification 3/4.1.I.3, A single submittal may be made for a multiple unit station.

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

-MILLSTONE - UNIT 3 6-19 Amendment No. M, y,69 0072

~

~

q

~

"09/28/92-

  • (

.7 ADMINISTRATIVE CONTROLS' i

4

~j 6.13 ~itAD10 LOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL' IREMODCM)

)

Section I,. Radiological ~ Effluent Monitoring Manual (REM), shall outlin't the j

sampling.and analysis programs to determine the concentration off radioactive.

materials released offsite as.well as dose constitments to individuals in those-exposure pathways and for those radionuclides released as a result of station O

operation. It shall= also specify operat' J guidelines for radioactive waste.

treatment systems and' report content, j

Section II, the offsite Dose Calculation Manual (ODCM), shall describe the :

methodology and parameters to be used in the calculation of offsite doses due e

to radioactive gaseous and liquid effluents and in the calculations of gaseous-and liquid effluent monitoring instrumentation alam/ trip setpoints. consistent with the applicable LCOs contained in these technical specifications.

4 Changes to th'e REMODCM:

Shall be documented and records of reviews perfomed shall be retained as' required by Specification 6.10.30. This documentation shall contain:

}

a.

1)

Sufficient information to_ support the change.together with the.

-l appropriate analyses or evaluationsjustifying the change (s), and' 2)

A determination that the change will maintain the--level of radioac -

tive effluent contro1~ required by 10 CFR 20.106, 40 CFR Part 1g0,.

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-1 calculations.

b.

Shall become effective after review and acceptance by SORC'and the o

approval of t t tion Director.

Mwn c.

Shall be su ittedftotheCo ssion in the form of a complete,' legible copyoftheAntireyREMMor CM, as appropr m> art of or concur-rent with thr r '. = :'

ioactive.Efflue hk=:

port for-the; J

period of the

. hich any change was h change shall' be U

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 RAD 10 ACTIVE WASTE TREF lTMENT a

Procedures for 1_iquid and gaseous _ radioactive effluent discharges from the 1

Unit shall be prepared, approved, maintained and adhered to for all. operations --

involving offsite releases of radioactive affluents.. These procedures ~ shall specify the use of appropriate waste treatment systems utilizing the guidance provided in the REMODCM.-

l The Solid Radioactive Waste Treatment System 'shall be operated in accordance with the-Process Control Program to process wet radioactive wastes to meet j

shipping and burial ground requirements.

1j MILLSTONE - UNIT 3 6-24

_ Amendment No. JS 69 0072

.1

~

Docket No. 50-213 B14532 P

f i

Haddam Neck Plant r

Proposed Revision to Technical Specifications Radioactive Effluent Release Report Retyped Pages

')

I July 1993 l

u INDEX

' ~*

4 ADMINISTRATIVE' CONTROLS SECTION PEaE Audits..................................................

.6-9 Authority...............................................

6-10 Records.................................................

6-10 1,6 REf0RTABLE EVENT ACTI0N.................................

6-11:

6.7 SAFETY LIMIT VIOLATION..................................

6-llL i

Lj 6.8 PROCEDURES AND PR0 GRAMS.................................

6 l 6.9 REPORTING RE0UIREMENTS 6.9.1 Routine Reports.........................................

6-13 Startup Report..........................................

6-13 Ann u al Rep o rt s..........................................

.6-13 Annual Radiological ~ Environmental Operating Report......

6-14.

- Annual Radioactive Effluent Report......................

6-15Il' i

Monthly Operating Reports..............................

6-15

' Technical Report Supporting Cycle Operation.............

6-15' Sp e c i al Re p o rt s.........................................

6-17 6.10 RECORD RETENTION........................................'

6-17 d

l

. 5 11 RADIATION PROTECTION PR0 GRAM............................

6 - 6.12 HIGH RADIATION AREA.....................................

6-19 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE:

~

CALCULATION MANUAL (REM 0DCM)..... <.....................

'6-20 6.14 RADI0 ACTIVE WASTE TREATMENT.............................

6-20 6.15 SYSTEMS INEGRITY........................................,

~6-21

- 6.16 PASS / SAMPLING AND ANALYSIS OF PLANT EFFLUENTS...........

6-21 HADDAM NECK.

XIX' Amendment No. //J, JJJ; JJJ, 0177 p;

v ;

Gh-_____--_____.__________

_ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _

r_

INSTRUMENTATION u

RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION

]

LIMITING CONDITION FOR OPERATION j

q I

3.3.3.7 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with applicable Alarm / Trip

~-

Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The Alarm / Trip Setpoints shall be determined in accordance with methodology and parameters described in the OFFSITE DOSE CALCULATION MANUAL (0DCM).

APPL.ICABILITY: At all times *.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, without delay suspend the release of l

radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the Alarm / Trip Setpoint so it is acceptably conservative.

b.

With the number of channels less than the minimum channels operable requirement, take the ACTION shown in Table 3.3-9.

Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days, and, if unsuccessful, explain in the next Annual Effluent-l Report why the inoperability was not corrected in a timely manner.

Releases need not be terminated after 30 days provided the specified actions are continued.

l c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.3.3.7.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-7.

At all times means that channel shall be OPERABLE and in service on a continuous, uninterrupted basis, except that outages are permitted for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> each time for the purpose of maintenance and performance of required tests, checks, calibrations or sampling.

l q

l HADDAM NECK 3/4 3-44 Amendment No. J U,

0178 i

w

~

a INSTRUMENTATION

.RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION

-3.3.3.8 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE with applicable Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The setpoints shall be determined in'accordance.with the methodology and parameters as described in the ODCM.

APPLICABILITY: At all times *.

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above Specification, without delay suspend-the release of radioactive gaseous effluents monitored by the affected channel, or-declare the channel inoperable, or change the Alarm / Trip Setpoint so it is acceptably conservative, b.

With the number of channels less than the minimum channels operable requirement, take the ACTION shown in Table 3.3-10.

Exert best efforts to restore the inoperable monitor to OPERABLE. status within 30 days and, if unsuccessful, explain in the next Annual Effluent j.

Report why the inoperability was not corrected in a timely manner.

Releases need not ce terminated after 30 days provided the specified actions are continued.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.3.3.8.1 Each radioactive gaseous effluent monitorbg instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-8.

At all times means that the channel shall be OPERABLE and in service on a continuous basis, except that outages are permitted for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> each time for the purpose of maintenance and performance of required tests, checks, calibrations.

HADDAM NECK 3/4 3-49 Amendment No. JD,

0179' t

v.

ADMINISTRATIVE CONTROLS ANNUAL RADI0 ACTIVE' EFFLUENT REPORT' ll' 6.9.1.7 - A routine Annual Radioactive Effluent Report covering'the operation of the facility during the previous calendar year of operation-shall be submitted by May 1-of each year.

The report shall include that information delineated in the REMODCM.

Any changes to the REM 0DCM shall be submitted in the Annual Radioactive -

Effluent Report.

RQRIHLY OPERATING REPORTS 6.9.1.8 Routine reports.of. operating statistics and shutdown experience-shall be submitted on a monthly: basis to the U.S. Nuclear Regulatory Commis-sion, Document Control Desk,' Washington, D.C.-20555, with one copy to the appropriate Regional 0ffice of the NRC, and one copy to the-appropriate NRC-Resident Inspector,' no later than the 15th of each month following the calen-L dar month covered by the report.

TECHNICAL REPORT SUPPORTING CYCLE OPERATION 6.9.1.9.a Core: operating limits shall.be established.and documented in the TECHNICAL REPORT SUPPORTING CYCLE OPERATION before-each reload cycle or any remaining part of a reload cycle for the following:

1.

Moderator Temperature Coefficient for Specification 3.1.l.5.

2.

Moveable Control Assemblies--Bank Height for Specification 3.1.3.1.

3.

Control Group Insertion-Limits--Four Loops _0perating, control' banks for' Specification 3.1.3.6.1.

4.

Control Group Insertion. Limits--Three Loops' Operating, control banks' for Specification 3.1.3.6.2.

y 5.

Axial Offset--Four Loops Operating for: Specifications 3/4.2.1.1.

6.

Axial Offset--Three Loops- 0perating for Specifications 3/4.2.1.2.

7.

. Linear Heat Generation Rate--Four Loops Operating for Specifica-

)

tions 3/4.2.2.1.

~

j 8.

. Linear Heat Generation Rate--Three Loops Operating for Specifica-tions 3/4.2.2.2.

j

.HADDAM NECK 6-15 Amendment No. JJE, JJJ, i

aseo jpg t

= __

~

n

.C

/ ' ADMINISTRATIVE CONTROLS i

J 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) j i

Section I,

Radiological Effluents.. Monitoring Manual, shall outline the j

sampling and analysis programs to determine-the. concentration of radioactive E

materials released offsite ' as well at dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of

-l

- facility. operation.

It shall also specify operating guidelines '.for RADI0 ACTIVE WASTE TREATMENT SYSTEMS.and report content.

Section II, the.0ffsite Dose Calculation - Manual,. shall' describe. the methodology.and' parameters. to be used in the calculation..of offsite doses-due to radioactive gaseous and liquid effluents and in the calculations. of.

A gaseous - and liquid effluent monitoring instrumentation Alarm / Trip 'Setpoints consistent with the applicable LC0's contained in-these Technical Specifications.

Changes to the REM 0DCM:

l a.

Shall be documented and records of reviews performed shallibe retained as required by Specification 6.10.3.m.

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 10CFR Part '50 and not adversely impe::t the accuracy or reliability of effluent,: dose, or -

setpoint calculations.

b.

Shall become effective after review and acceptance by PORC and the approval of the Vice President - Haddam Neck.

c.

Shall be submitted to the Commission in-the form of 'a complete,. legible' copy of the entire REMM or ODCM, as appropriate, as a part of or concurrent with the Annual Radioactive' Effluent Report for the period of -l the report in which any change 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 RADI0 ACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive. effluent discharges 'from the-facility shall be - prepared, approved, maintained and adhered to ;for-all operations involving offsite releases of radioactive effluents.

These:

procedures shall 'specify the use. of appropriate RADI0 ACTIVE WASTE TREATMENT-SYSTEMS utilizing the guidance provided in the'REMODCH.

l The Solid RADI0 ACTIVE WASTE TREATMENT SYSTEM shall be operated in accordance with~ the PROCESS CONTROL PROGRAM to process wet radioactive wastes 'to meet shipping-and burial ground requirements.

.HADDAM NECK 6-20 Amendment No. JJJ, JJJ, JJJ

'0181 i

~

1 g,

3.

j Docket No. 50-245 B1453R t

t B

i Millstone Unit No. 1 Proposed Revision to Technical Specifications Radioactive Effluent Release Report Retyped Pages 1

,f

-)

I j

July 1993 L

LIMITING CONDITION FOR OPERATION 3.8 RADI0 ACTIVE MATERIALS A.

Radioactive Liouid Effluent Instrumentation 1.

The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.8-1 shall be OPERABLE with' applicable alarnVtrip setpoints set to ensure that the limits of Specification.3.8.C.1 are not exceeded. The setpoints shall-be determined in accordance with methods and parameters as described in the ODCM.

Acolicability As shown in Table 3.8-1 Action:

1.

In the event a limiting condition for operation and/or associated action -

requirement cannot be satisfied, this shall not require unit shutdown or prevent a change in operational modes.

2.

With a radioactive liquid effluent monitoring instrumentation. channel alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

3.

With the number of channels less than the minimum channels OPERABLE requirement, take the action shown in Table 3.8.1.

Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days and, if i

unsuccessful, explain in the next Annual Effluent Report why the I

inoperability was not corrected in a timely manner.

Releases need not be terminated after 30 days provided the specified actions are continued.

SURVEILLANCE RE0UIREMENTS 4.8 RADI0 ACTIVE MATERIALS A.

Radioactive Liauid Effluent Instrumentation 1.

Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the INSTRUMENT-CHECK, INSTRUMENT CALIBRATION, INSTRUMENT FUNCTIONAL TEST, and SOURCE CHECK operations at the frequencies shown in Table 4.8-1.

i Millstone Unit 1 3/4 8-1 Amendment No. JJ 0104 j

i L

( --

LIMITING CONDITION FOR OPERATION 3.8 RADI0 ACTIVE MATERIALS-B.

Radioactive Gaseous Effluent Monitorina Instrumentation 1.

The radioactive gaseous ~ effluent monitoring instrumentation channels shown in Table 3.8-2 shall be OPERABLE with applicable alarm / trip setpoints set to ensure that the limits of Specification 3.8.D.1 are not exceeded..The setpoints shall be determined in accordance with methods and parameters as described in the ODCM.

Aeolicability: As shown in table 3.8-2.

Action:

1.

In the event of a limiting condition for operation 'and/or associated action requirement cannot be satisfied, this shall not require unit shutdown or prevent a change in operational modes, except for Table 3.8-2 action B statement for SJAE off-gas monitor.

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With the number of channels less than the minimum channels operable requirements, take the action shown in Table 3.8-2.

Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent l

Report why the inoperability was not corrected.in a timely manner.

Release need not be terminated after 30 days provided the specified actions are continued.

SURVEILLANCE RE0UIREMENTS 4.8 RADI0 ACTIVE MATERIALS B.

Radioactive Gaseous Effluent Instrumentation I.

Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the INSTRUMENT CHECK, INSTRUMENT CALIBRATION,' INSTRUMENT FUNCTIONAL TEST, and-SOURCE CHECK operations at the frequencies shown in Table 4.8-2.

Millstone Unit 1-3/4 8-6 Amendment No. A9, 0105 k-

ADMINISTRATIVE CONTROLS Annual Radioloaical Environmental Ooeratina Reoort 6.9.1.7 Routine Annual Rad 1ological Environmental Operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The Annual Radiological Environmental Operating Report shall include that information delineated in the REM 0DCM.

Annual Radioactive Effluent Report l

6.9.1.8 A routine Radioactive Effluent Report covering the operation of the unit during the previous calendar year of operation shall be submitted by May 1 of each year.

The report shall include that information delineated in the REM 0DCM.

Any changes to the REMODCH.shall be submitted in the Annual Radioactive Effluent Report.

Supplemental Reload licensino Submittal 6.9.1.9 Core power distribution limits (MCPR, LHGR, and APLHGR) shall be established and documented in the Supplement Reload Licensing Submittal before each reload cycle or any remaining part of a reload cycle. The analytical methods used to determine these limits shall be those previously reviewed and approved by the NRC'in NEDE-24011, General Electric Standard Application for Reactor Fuel, latest approved revision. The core power distribution limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analyses limits) of the safety analysis are met. The Supplemental Reload Licensing Submittal, including any mid-cycle revisions or supplements thereto, shall be submitted upon issuance.

Special Reports 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory.

Commission Document Control Desk, Washington, D.C.

20555, one copy to the Regional Administrator, Region. I, and one copy to the NRC Resident Inspector, within the time period specified for each-report. These reports shall be submitted covering the activities-identified below pursuant to the requirement of the applicable reference specification:

a.

In-service Inspection Results, Specification 4.6.F.

H111 stone Unit 1 6-18 Amendment No. J, JJ, #, M,

M, M, 4

q ADMINISTRATIVE CONTROLS 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)

'Section I, Radiological Effluents Menitoring Manual (REMM), shall outline the sampling and analysis programs to determine-the concentration of radioactive materials released offsite as well as dose commitments to individuals in those exposure pathways and for those radionuclidee released as a result of station operation.

It shall also specify operating guidelines for radioactive waste treatment systems and report content.

Section II, the. 0ffsite Dose Calculation Manual (0DCM), shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculations of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LC0's contained in these technical specifications.

Changes to the REM 0DCM:

a.

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

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 SORC and the approval of the Nuclear Station Director.

c.

Shall be submitted to. the, Commission-in the form of a complete, legible copy of the entire REMM or ODCM, as appropriate, as a part of or concurrent with the Annual Radioactive Effluent Report for the l period of the report in which any change 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.

Millstone Unit 1 6-23 Amendment No. 55, EE, 0107 i

5 Docket No. 50-336 B14532~

Millstone Unit No. 2 Proposed Revision to Technical Specifications:

Radioactive Effluent Release Report Retyped Pages n

July 1993 t

I INDEX ADMINISTRATIVE CONTROLS SECTION EAE 6.9 REPORTING REOUIREMENTS 6.9.1 ROUTINE REPORTS.......................................

6-16 STARTUP REPORTS.......................................

6-16 ANNUAL REPORTS........................................

6-17 ANNUAL RADI0 ACTIVE EFFLUENT REP 0RT.....................

6-18 l

MONTHLY OPERATING REPORT..............................

6-18 CORE OPERATING LIMITS REPORT..........................

6-18 6.9.2 SPECIAL REPORTS.......................................

6-19 6.10 RECORD RETENTION....................................... 20 6.11 RADIATION PROTECTION PROGRAM...........................

6-22 6.12 HIGH RADIATION AREA....................................

6-22 6.13 SYSTEMS INTEGRITY......................................

6-23 6.14 IODINE MONITORING......................................

6-23 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM) 6-24 6.16 RADI0 ACTIVE WASTE TREATMENT............................

6-24 6.17 SECONDARY WATER CHEMISTRY...............................

6-25 6.18 PASS / SAMPLING AND ANALYSIS OF PLANT EFFLUENTS..........

6-25.

MILLSTONE - UNIT 2 XVIII Amendment No. 79, JE,=El, EE, l#7,

    • M Iff,111,1/S,JEl,
IEl, km j
i. -

INSTRUMENTATION RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with applicable alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The setpoints shall be determined in accordance with methods and parameters as described in the ODCM.

APPLICABILITY: As shown in Table 3.3-12.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the -

above specification, without. delay suspend-the release of radioactive liquid effluents monitored by the affected. channel, or declare the channel inoperable, or ' change the setpoint so it is acceptably conservative.

b.

With the number of channels less than the minimum channels operable requirement, take the ACTION shown in Table 3.3-12.

Exert best efforts to restore the inoperable monitor to OPERABLE = status within 30 days and, if unsuccessful, explain in the next Annual Effluent l

Report why the inoperability was not corrected in a timely manner.

Releases need not be terminated after 30 days provided the specified actions are continued.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0UIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12.

a i

MILLSTONE - UNIT 2 3/4 3-50 Amendment No. J9f, JEJ 0092

7 O

INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONIT0 RING INSTRUMENTATION-LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with applicable alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. _The setpoints shall. be determined in accordance with methods and parameters as described in the ODCM.

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is -

acceptably conservative.

b.

With the number of channels less than the minimum channels (OPERABLE requirement, take the ACTION shown in Table 3.3-13.

Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual. Effluent l

Report why the inoperability was not corrected.in a timely manner.-

Releases need not-be terminated after 30 days provided the specified actions are continued.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and' CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

J 4

MILLSTONE - UNIT 2 3/4 3-S6 Amendment No. JEf, JEJ 0091 IL

a I

. ADMINISTRATIVE CONTROLS

)

'd.-

Documentation of all failures (inability to lift or reclose within the tolerances allowed ^ by the design basis) and challenges ~ to the' pressurizer PORVs or safety valves. -

ANNUAL RADI0 ACTIVE EFFLUENT REPORT 6.9.1.6 A routine Annual Radioactive Effluent Report covering.the ' operation of the unit during - the previous ' calendar year of operation shall be.

i submitted by May 1 of each year..

1 The report shall include that information delineated.in the REMODCM.

Any changes to -the -REM 0DCM shall be submitted in -the Annual' Radioactive Effluent Report.

MONTHLY OPERATING' REPORT 6.9.1.7 Routine reports of operating statistics and shutdown experience shall- -l be submitted on. a monthly basis to the U.S.

Nuclear Regulatory j

Commission, Document Control Desk,: Washington, D.C. 20555, one copy to the Regional Administrator, Region I, and one copy to the NRC Resident-Inspector, no later than the 15th of each month following the calendar.-

month covered by the report..

CORE OPERATING LIMITS REPORT j

6.9.1.8 a.

Core operating limits shall be established and documented in the l.

'i CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle.

F 200*F l

3/4.1.1.1.

SHUTDOWN MARGIN - T*V9 > 200*F 3/4.1.1.2 SHUTDOWN MARGIN - T 1

3/4.1.1.4-ModeratorTemperatuPE9 Coefficient 3/4.1.3.6 Regulating'CEA Insertion Limits 3/4.2.1 Linear Heat Rate

]

T 3/4.2.3 Total Integrated. Radial Peaking Factor - F I

~r 3/4.2.6 DNB Margin i

l b.

The analytical methods used to determine the core operating.-

i limits shall be those previously : reviewed and approved by the:

NRC, specifically those described in the following documents:

.l U

1)

XN-75-27(A),

latest Rovisions and

' Supplements,

" Exxon

-Nuclear Neutronics Design-Methods-for Pressurized-Water-Reactors," Exxon Nuclear Company.

2)

XN-NF-84-73(P), latest Revision and Supplements, "Exxo'n Nuclear.. Methodology-for Pressurized Water Reactors:

l Analysis of Chapter 15 Events'," Exxon Nuclear Company..

j 3)

XN-NF-82-21(A),

latest

.. Revision-and-Supplements, a

" Application of-Exxon ? Nuclear, Company PWR Thermal Margin '

- Methodology to ' Mixed Core Configurations," Exxon Nuclear Company.

q 6

MILLSTONE - UNIT 2 6-18 Amendment Nos. 75, 77, J#f, JJ/,.

j 115,JJ9,JJ0, JJJ,JfE,JEJ.

j a

b

  • ADMINfSTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Con't.)

4)

XN-84-93(A), latest Revision and Supplements, "Steamline Break Methodology for PWR's, Exxon Nuclear Company.

5)

XN-75-32(A), Supplements 1,

2, 3,

and 4,

" Computational Prot.edure for Evaluation Rod Bow," Exxon Nuclear Company.

6)

Xil-NF-82-49(A),

latest Revision,

" Exxon Nuclear Company Evaluation Model EXEM PWR Small Break Model," Exxon Nuclear

Company, i

I l

MILLSTONE - UNIT 2 6-18a Amendment Nos. JJ, SJ, J#1, JJJ, JJ5,JJ9,JJ9, JJJ,Jff,JpJ,

E.

ADMINISTRATIVE-CONTROLS 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL fREM0DCM)

Section I, Radiological Effluents Monitoring Manual (REMM), -shall outline the L sampling and analysis programs to determine the concentration of radioactive.

materials released offsite as well as dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of station operation.

It shall also specify operating guidelines for radioactive waste treatment systems and report content.

Section II, the Offsite-Dose Calculation Manua"I (0DCM), shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculations of gaseous and liquid effluent monitoring instrumentation Alarm / Trip Setpoints consistent with the applicable LC0's contained in these Technical Specifications.

Changes to the REM 0DCM:

a.

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

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 SORC and the approval of the Nuclear Station Director.

c.

Shall be submitted to the Commission in the form of a. complete, legible copy of the entire REMM or ODCM, as appropriate, as a part of or concurrent with the Annual Radioactive Effluent Report for the l

period of the report in which any change 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.

Millstone Unit 2 6-24 Amendment No. //J, JEJ, 4

0095 L'

p'

~

~

[..

r Docket No. 50-423 B14532 R

Millstone Unit No. 3 Proposed Revision to Technical Specifications.

Radioactive Effluent Release Report.

Retyped Pages i

' July 1993) u o

p q

.i g

INDEX y

i ADMINISTRATIVE CONTROLS SECTION PME 6.8 PROCEDURES AND PR0 GRAMS..........................................

6-14 6.9 REPORTING RE0VIREMENTS...........................................

6-17 6.9.1 ROUTINE REP 0RTS................................................

6 Startup Report.................................................

~6-17 An n u a l Re p o r t s.................................................

6-18 Annual Radiological Environmental Operating Report.............

6-19 Annual Radioactive Effl uent Report.............................

6-19 l'

Monthly Operating Reports......................................

6-19 Core Operating Limits Report...................................

6-19 6.9.2 SPECIAL REP 0RTS................................................

6-21 6.10 RECORD RETENTION................................................

6-21 6.11 RADIATION PROTECTION PR0 GRAM....................................

6-22 6.12 HIGH RADIATION AREA.............................................

6-23' 6.13 RADIOLOGICAL EFFLUENT MONITORING AND'OFFSITE DOSE CALCULATION MANUAL (REM 0DCM)....................................

6-24 i

6.14 RADIDACTIVE WASTE TREATMENT.....................................

6-24 HILLSTONE - UNIT 3 xx Amendment No. JJ, ES, 0152 0

l INSTRUMENTATION RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The Alarm / Trip Setpoints of these channels shall be determined in accordance with the methodology and parameters as described in the REM 0DCM.

i APPLICABILITY: As shown in Table 3.3-12 ACTION:

I a.

With a

radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the l

above specification, without delay suspend the release of I

radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Exert best efforts to restore the inoperable instrumentation to OPERABLE status within 30 days

and, if unsuccessful, explain in the next Annual Radioactive Effluent

)

Report why the inoperability was not corrected in a timely manner.

Releases need not be terminated after 30 days provided the specified actions are continued.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEIll ANCE RE0VIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-8.

l l

i MILLSTONE - UNIT 3 3/4 3-69 Amendment No. //, #

0153 L-

INSTRUMENTATION RADI0ACIlyf;_ GASE0US EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specifications 3.11.2.1 are not exceeded.

The Alarm / Trip Setpoints of these channels shall be determined in accordance with the methodology and parameters in the REMODCM.

APPLICABILITY: As shown in Table 3.3-13 ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the o

above specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservati.e.

j i

b.

With the number of OPERABLE radioactive gaseous effluent monitoring instrumentation channels less than the Minimum Channels OPERABLE, take the ACTION shown in Table 3.3-13.

Exert best efforts to restore the inoperable instrumentation to OPERABLE status within j

30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Report why the inoperability was not corrected in a timely manner.

Releases need not be terminated after 30 days provided the specified actions are continued.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0UIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-9.

I MILLSTONE - UNIT 3 3/4 3-74 Amendment No. E7, 0154 L

ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the reactor coolant exceeded the radiciodine limit.

c.

Documentation of all challenges to the pressurizer power-operated relief valves (PORVs) and safety valves; and ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

The Annual Radiological Environmental Operating Reports shall include that information delineated in the REM 0DCM.

ANNUAL RADI0 ACTIVE EFFLUENT REPORT **

l-6.9.1.4 A routine Annual Radioactive Effluent Report covering the operation of the unit during the previous calendar year of operation shall be submitted.

by May 1 of each year.

The report shall include that information delineated in the REM 0DCM.

Any changes to the REMODCM shall be submitted in the Annual Radioactive Effluent Report.

MONTHLY OPERATING REPORTS 6.9.1.5 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C.

20555, one copy to the Regional Administrator Region I, and one copy to the NRC Resident Inspector, no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT H

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

1.

Moderator Temperature Coefficient 80L and E0L limits and 300 ppm i

surveillance limit for Specification 3/4.1.1.3, 1

A single submittal may be-made for a multiple unit' station.

A single submittal may be made for a multiple unit sr Mon. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

MILLSTONE - UNIT 3 6-19 Amendment No. U, #, M,

0155 C

p f

k o-ADMINISTRATIVE CONTROLS 6.13 ' RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) 1 Section I, Radiological Effluent Monitoring Manual (REMM), shall outline the R

sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as. dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of station operation. It shall also specify operating guidelines for radioactive waste treatment systems and report content.

Section II, the Offsite Dose Calculation Manual-(0DCM), shall describe the -

methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculations of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCOs contained in these technical specifications.

Changes to the REMODCH:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.30.

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 radioac-tive 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 SORC-and the approval of the Nuclear Station Director.

c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire REMM or ODCM, as appropriate, as a part of or concur-rent with the Annual Radioactive Effluent Report for the period of the l

report in which any change 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 RADI0 ACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the Unit shall be prepared, approved, maintained and adhered to for all operations involving offsite releases of radioactive effluents. These. procedures shall specify the use of appropriate waste treatment systems utilizing the guidance provided in the REM 0DCM.

The Solid Radioactive Waste Treatment System shall be operated in accordance with the Process Control Program to process wet radioactive wastes to meet shipping and burial ground requirements.

i MILLSTONE - UNIT 3 6-24 Amendment No. fp, ES, 0156 h _1

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