ML20058F110

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Amends 170,69,169 & 86 to Licenses DPR-61,DPR-21 DPR-65 & NPF-49,respectively,revising TS to Change Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual
ML20058F110
Person / Time
Site: Millstone, Haddam Neck  File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 11/23/1993
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20058F094 List:
References
NUDOCS 9312070326
Download: ML20058F110 (31)
v • d • e


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UNITED STATES j [! A j

NUCLEAR REGULATORY COMMISSION l

WASHINGTON. D.C. 20555-0001

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i CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 170 License No. DPR-61 f

1.

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

A.

The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated July 16, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as r

amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; i

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i

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; j

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 I

51 the Commission's regulations and all applicable requirements havt sen satisfied.

i 9312070326 931123 i

PDR ADOCK 05000213' P

PDR

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I 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-61 is hereby t

amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 170, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION r

J hn

. Stolz, Directo P oj ct Directorate I-4 Di 1sion of Reactor Projects - 1/II Office of Nuclear Reactor Regulation l

Attachment:

Changes to the Technical l

Specifications Date of Issuance: November 23, 1993 i

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i ATTACHMENT TO LICENSE AMENDMENT N0.170 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 t

Replace the following pages of the Appendix A Technical Specifications with The revised pages are identified by amendment number and the enclosed pages.

contain vertical lines indicating the areas of change.

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i Insert Remove

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5 XIX XIX 3/4 3-44 3/4 3-44 3/4 3-49 3/4 3-49 6-15 6-15 6-20 6-20 i

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INDEX T

ADMINISTRATIVE CONTROLS

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PAGE SECTION 6-9 Audits...................................................

6-10 l

Authority...............................................

6-10 l

Records.................................................

5 6-11 6.6 REPORTABLE EVENT ACT10N.................................

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

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

6.9 REPORTING REOUIREMENTS 6-13 6.9.1 Routine Reports.........................................

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

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

6-14 Annual Radiological Environmental Operating Report......

6-15 Annu al Radioactive. Ef fl uent Report......................

6-15 l

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

6-15 Technical Report Supporting Cycle Operation.............

6-17 Special Reports.........................................

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

6-18 6.11 RADIATION PROTECTION PR0 GRAM............................

6-19 6.12 HIGH RADIATION AREA.....................................

3 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE 6.13 6-20 CALCULATION MANUAL (REM 0DCM)............................

6-20

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

6-21 6.lS SYSTEMS INEGRITY........................................

i a

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

6.16 XIX Amendment No. JJE, JJE, JEE, t

HADDAM NECK

170,

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INSTRUMENTATION

-l RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATf0N LIMITING CONDITION FOR'0PERATION The radioactive liquid effluent monitoring instrumentation i

3.3.3.7 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 (ODCM).

APPLICABILITY: At all times *.

ACTION:

With a radioactive liquid effluent monitoring instrumentation a.

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.

With the number of channels less than the minimum channels operable b.

requirement, take the ACTION shown in Table 3.3-9.

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

Reit.ases 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 REQUIREMENTS Each radioactive liquid effluent monitoring instrumentation 4.3.3.7.1 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.

HADDAM NECK 3/4 3-44 Amendment No. //E,170.

0178 a

INSTRUMENTATION f

RADIDACTIVE GASE0US EFFLUENT MONITORING INSTRUMENT LIMITING CONDITION FOR OPERATION 1

The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE with applicable A 3.3.3.8 Setpoints set to ensure that the limits of Specification 3.11.2.1 are no The setpoints shall be determined in accordance with the exceeded.

methodology and parameters as described in the ODCM.

APPLICABILITY: At all times *.

t ACTION:

With a radioactive gaseous effluent monitoring a.

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

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

b.

efforts to restore the inoperable monitor to OPERABLE status w 30 days and, if unsuccessful, explain in the next Annual Effluen 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.

The provisions of Specification 3.0.3 are not applicable.

c.

SURVEILLANCE RE0dintMENTS Each radioactive gaseous effluent munitoring instrumentation

ECK, channel shall be demonstrated OPERABLE by performance of the 4.3.3.8.1 SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG CHA operations at the frequencies shown in Table 4.3-8.

At all times means that the channel shall be OPERA f

continuous basis, except that outages are per required tests, checks, calibrations.

l Amendment No. J/E 170, 3/4 3 49 HADDAM NECK 0179 i

s ADMINISTRATIVE CONTR0E6 ANNUAL RADI0 ACTIVE EFFLUENT REPORT 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 REMODCM shall be submitted in the Annual Radioactive Effluent Report.

1 MONTHLY OPERATING REPORTS i

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 Office of the NRC, and one copy to the appropriate NRC Resident Inspector, no later than the 15th of each month following the calen-dar month covered by the report.

i 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:

j 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.

i 8.

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

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HADDAM NECK 6-15 Amendment No. J2E, JE),

JJJ,170, olen I

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l ADMINISTRATfVE CONTROLS

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1 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE

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CALCULATION MANUAL (REMODCM)

Section I,

Radiological Effluents Monitoring Manual, shall outline the i

sampling and analysis programs to determine the concentration of radioactive j

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

It shall also specify operating guidelines for RADIOACTIVE 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 doses due to radioactive gaseous and liquid effluents and in the _ calculations of i

gaseous and liquid effluent monitoring instrumentation Alarm / Trip Setpoints

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consistent with.the applicable 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 6.10.3.m.

This documentation shall l

contain-l 1)

Sufficient information to support the change together with the i

appropriate analyses or evaluations justifying the change (s), and l

2)

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR i

Part 190, 10 CFR 50.36a, and Appendix I to 10CFR Part 50 and not adversely impact the accuracy or reliability of ' effluent, dose, or i

setpoint calculations.

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b.

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

l 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 the report in which any change was made.

Each change shall be identified i

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 RADIOACTIVE WASTE TREATMENT Procedur_es for liquid and gaseous radioactive effluent discharges from the facility shall be prepared, approved, maintained and adhered to for all j

operations involving offsite releases of radioactive effluents.

These j

procedures shall specify the use of appropriate RADI0 ACTIVE WASTE TREATMENT ~

SYSTEMS utilizing the guidance provided in the REMODCM.

The Solid RADI0 ACTIVE WASTE TREATHENT' SYSTEM shall be operated in accordance

-l with the PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet

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shipping and burial ground requirements.

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AmendmentNo.g.,JEE,JJE-HADDAM NECK 6-20

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0181

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9 UNITED STATES h

, ?+g NUCLEAR REGULATORY COMMISSION j. !{g& J j WASHINGTON. D C. 20555 0001

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\\... ; y NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 lilLLSTONE NUCLEAR POWER STATION. UNIT _1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. DPR-21 The Nuclear Regulatory Commission (the Commission) has found that:

1.

The application for amendment by Northeast Nuclear Energy Company A.

(the licensee), dated July 16, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the 8.

provisions of the Act, and the rules _ and regulations of the Commission; There is reasonable assurance (1) that the activities authorized C.

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; The issuance of this amendment will not be inimical to the common D.

defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part E.

51 of the Commission's regulations and all applicable requirements have been satisfied.

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i 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. DPR-21 is hereby amended to read as follows:

I (2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 69, are hereby incorporated in the license.

i The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION i

J hn F. Stolz, Directo roj ct Directorate I iv ion of Reactor Projects - 1/II ice of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

Novenber 23, 1993

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ATTACHMENT TO LICENSE AMENDMENT N0. 69 j

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FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 l

Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and l

contain vertical lines indicating the areas of change.

I 1

Remove Insert l

3/4 8-1 3/4 8-1 3/4 8-6 3/4 8-6 6-18 6-18 6-23 6-23 i

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LIMITING CONDITION FOR OPERATION 3.8 RADI0 ACTIVE KATERIALS A.

Radioactive Liourd Effluent Instrumentation 1.

The radioactive liquid effluent monitoring instrumentation channels i

shown in Table 3.8-1 shall be OPERABLE with applicable alarm / trip t

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.

t Acolicability 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 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 unsuccessful, explain in the next Annual 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.

SURVEILLANCE REOUIREMENTS l

4.8 RADI0 ACTIVE MATERIALS A.

Radioactive Liouid Effluent Instrumentation 1.

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

l l

Millstone Unit 1 3/4 8-1 Amendment No. JJ. 69, 0104

tIMfTING 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.

i With a radioactive gaseous effluent monitoring 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 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 Report why the inoperability was not corrected in a timely manner.

Release need not be terminated after 30 days provided the specified J

actions are continued.

SURVEIll ANCE REOUIREMENTS 4.8 RADI0 ACTIVE MATERIALS B.

Radioactive Gaseous Effluent Instrumentation 1.

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.

i i

Hillstone Unit 1 3/4 8-6 Amendment No. #,69 0105 I

ADMINISTRATIVE CONTROL.S Annual Radiolooical Environmental Operatino Reoort 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 REMODCH.

Annual Radioactive Effluent Report 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 REMODCM.

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

Supolemental 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 rentaing 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.

Soecial Re90rts Special reports shall be submitted to the U.S. Nuclear Regulatory 6.9.2 Comission 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 These reports shall be submitted covering the activities report.

identified below pursuant to the requirement of the applicable reference specification:

In-service Inspection Results, Specification 4.6.F.

a.

Millstone Unit 1 6-18 Amendment No. J, EE, ES, /E, EE,EE,69, 0285

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

Section I, Radiological Effluents Monitoring 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 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 (ODCM), 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.iang/ trip setpoints consistent with the applicable LCO's contained in these te.chnical specifications.

Changes to the REMODCH:

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 50RC and the approval of the Nuclear Station Director.

Shall be submitted to the Commission in the form of a complete, c.

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 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.

i Millstone Unit 1 6-23 Amendment No. JJ, JJ,69, 0107

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u UNITED STATES

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NUCLEAR REGULATORY COMMISSION

[\\i;Cf.t* 4j V,j WASHINGTON. D.C. 20556-0001 f

r s, ss.....a NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE

.c Amendment No.169 License No. OPR-65 1.

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

A.

The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated July 16, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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; i

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; 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.

l j

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.169, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

R THE NUCLEAR REGULAT RY COMMISSION

/7 oh 'F.

Stolz, Director Pr ject Directorate I-4 vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical l

Specifications Date of Issuance:

November 23, 1993 t

1 i

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.. =,

0 i

ATT_ACHMENT TO LICENSE AMENDMENT NO.169 FACILITY OPERATING LICENSE NO. OPR-65 l

DOCKET NO. 50-336 Replace the following pages of. the Appendix A Technical Specifications with The revised pages are identified by amendment number-and the enclosed pages.

contain vertical lines indicating the areas of change.

t Insert Remove i

XVIII

.XVIII 3/4 3 3/4 3-50 3/4 3-56 3/4 3-56 6-18 6-18 6-18a 6-24 6-24 i

I I

a INDEX ADMINISTRATIVE CONTR0lS SECTION f2EE 6.9 REPORTING RE0VIREMENTS 6-16 6.9.1 ROUTINE REPORTS.......................................

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

6-17 ANNUAL REPORTS.......................................

ANNUAL RADI0 ACTIVE EFFLUENT REP 0RT.....................

6-18 MONTHLY OPERATING REPORT..............................

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

6-19 6.9.2 SPECIAL REPORTS.......................................

\\

6-20 6.10 RECORD RETENTION.......................................

6.11 RADIATION PROTECTION PROGRAM...........................

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

l 6-23 l

6.13 SYSTEMS INTEGRITY......................................

6-23 6.14 I0 DINE MONITORING......................................

l 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) 6-24 6-24 6.16 RADI0 ACTIVE VASTE TREATMENT............................

6-25 6.17 S ECONDARY V AT ER CHEMISTRY...............................

6.18 PASS / SAMPLING AND ANA!.YSIS OF PLANT EFFLUENTS..........

6-25 MILLSTONE - UNIT 2 XVIII Amendment No.17, JE, JJ, EE, JSJ, 19/,111,if5,151,

    • n JJJ,169,

~

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 ODCH.

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 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.

^

The provisions of Specification 3.0.3 are not applicable.

c.

SURVEILLANCE RE0UIREMENTS Each radioactive liquid effluent monitoring instrumentation channel i

4.3.3.9 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.

i i

MILLSTONE - UNIT 2 3/4 3-50 Amendment No. Jff, JEI 169, i

0092

INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION tiMITING 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 t

described in the ODCM.

I 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 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.

The provisions of Specification 3.0.3 are not applicable.

c.

SURVElttANCE 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 CHANNEL FUNCTIONAL TEST operations at the 1

frequencies shown in Table 4.3-13.

l MILLSTONE - UNIT 2 3/4 3-56 Amendment No. JJ/, /J/.169, coes l

k i

ADMINISTRATIVE CONTROLS d.

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

?

tolerances allowed' by the design bacis) and challenges to the pressurizer PDRVs or safety valves.

i i

t 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 submitted by Mhy I of each year, j

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

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

{

Radioactive Effluent Report.

MONTHLY OPERATING REPORT 1

6.9.1.7 Routine reports of operating statistics and shutdown experience shall

'I be submitted on a monthly basis to the U.S.

Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, one copy to i

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 6.9.1.8 a.

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

3/4.1.1.1 SHUTDOWN MARGIN - T

> 200*F l

avg 5 200*F 3/4.1.1.2 SHUTDOWN MARGIN - T 3/4.1.1.4 ModeratorTemperatuM9 Coefficient 3/4.1.3.6 Regulating CEA Insertion Limits 3/4.2.1 Linear Heat Rate T

l 3/4.2.3 Total Integrated Radial Peaking Factor - Fr o

3/4.2.6 DNB Margin 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 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.

1 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.

MILLSTONE - UNIT 2 6-18 Amendment Nos. JE, JJ JEf, 1/J, JJF, JJ9 Ji9, JJZ,195,-197.469, i

hv ADMINISTRATIVE 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 "Computati^nal 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.

t t

i MILLSTONE - UNIT 2 6-1Ba Amendnent Nos. JE, 77, J#f, JJJ, 115,119,129,169,-

lit,195,151, U

bDMINISTRATIVE CONTROES 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL fREMODCM)

Section I, Radiolcgical Effluents Monitoring Manual (REMM), shall outline the sampling and analysis progra'us to determine the concentration of radioactive materials released offsite as well as dose commitments to individuals in those exposure pathways and for those radionuclides relcased as a result of station operation.

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

Section II, the Offs 1M Dose Calculation Manual (ODCM), shall describe the methodology and parameter: 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 monitor.ng instrumentation AlarWTrip Setpoints consistent with the applicable LCO's contained in these Technical Specifications.

Changes to the REM 00CH:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 610.2m.

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 r.aintain 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 50RC and the approvt.' of the Nuclear Station Director.

i c.

Shall uitted to the Comission in the form of a complete, m

of the entire REMM or ODCM, as appropriate, as a part legible cm of or concurrent with the Annual Radioactive Effluent Report for the 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 q

indicate the date (e.g., month / year) the change was implemented.

i Millstone Unit 2 6-24 Amendment No. Jf), /f),169, DOS $

(

UNITED STATES j

+.

l

[.ki ! j NUCLEAR REGULATORY COMMISSION

'; pg> ' y WASHINGTON. O C. 20555 0001 I

N..v j

NORTHEAST NUCLEAR ENERGY COMPANY. ET AL, DOCKET NO. 50-423 M'LLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 j

License No. NPF-49

)

1.

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

A.

The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated July 16, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set i

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; D.

The issuance of this amendment will not be inimical to the common i

defense and security or to the health and safety of the public-i and J

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.

l

i,

. +

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment,-

and paragraph 2.C.(2) of facility Operating License No. NPF-49 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 86

, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION J in ?. Stolz, Directof Projkct Directorate U-DM'sion of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

)

Attachment:

Changes to the Technical Specifications i

Date of Issuance: fJovember 23, 1993 b

b 3

?

~

r~

9 ATTACHMENT TO LICENSE AMENDMENT NO. 86-FAClllTY OPERATING LICENSE NO. NPF-49 i

DOCKET NO. 50-423

[

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.

t 4

Remove Insert l

XX XX 3/4 3-69 3/4 3-69 3/4 3-74 3/4 3-74 6-19 6-19 i

6-24 6-24 i

)

t

?

l l

i

)

~

i

)

INDEX ADMINISTRATIVE CONTROLS SECTION E&EE 6.8 PROCEDURES AND PR0 GRAMS..........................................

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

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

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

6-17 An n u al R e p o rt s.................................................

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

6-19 Annual Radioactive Effluent Report.............................

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

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

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

6-21 6.10 RECORD RETENT10N,................................................

6-21 t

6.11 RADIATION PROTECTION PR0 GRAM....................................

6-22 6.I2 HIGH RADIATION AREA.............................................

6-23 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE

[alCULATION MANUAL (REM 02LBi.....................................-

6-24 6.14 RADIOACTIVE WASTE TREATHENT.....................................

6-24 Amendment No. J#, ES,86 MILLSTONE - UNIT 3 xx els:

3 b

INSTRUMENTATION 1

RADIOACTIVE LIOUID EFFLUENT MONITORING jNSTRUMENTATION LIMITING CONDITION FOR OPERATION The radioactive liquid effluent monitoring instrumentation channels 3.3.3.9 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.

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

e With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the a.

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, With less than the minimum number of radioactive liquid effluent b.

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.

The provisions of Specification 3.0.3 are not applicable.

c.

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

i MILLSTONE - UNIT 3-3/4 3-69 Amendment No. //, U. 86, 0153

~

INSTRUMENTATION

~

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION The radioactive gaseous effluent monitoring instrumentation channels 3.3.3.10 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:

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

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 accep'

, conservative.

With the number of OPERABLE radioactive gaseous effluent monitoring b.

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 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Report why the inoperability was not corrected in a timely 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 RE0UIREMENTS Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURC 4.3.3.10

CHECK, CHANNEL CAllBRATION and ANALOG CHANNEL OPERATIONA frequencies shown in Table 4.3-9.

9 I

MILLSTONE - UNIT 3 3/4 3-74 Amendment No. E/, 86.

0154

6DMINISTRATIVE CONTRJLS 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 j

coolant exceeded the radiciodine limit.

Documentation of all challenges to the pressurizer power-operated l

c.

relief valves (PORVs) and safety valves; and ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

prior to May 1 of each year.

The Annual Radiological Environmental Operating Reports shall include that information delineated in the REMODCM.

ANNUAL RADIOACTIVE EFFLUENT REPORT **

A routine Annual Radioactive Effluent Report covering the operation 7

6.9.1.4 of the unit during the previous calendar year of operation shall be submitted by May 1 of each year.

i The report shall include that information delineated in the REMODCH.

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

MONTHLY OPERATING REPORTS Routine reports of operating statistics and shutdown experience shall 6.9.1.5 be submitted en a monthly basis to the U.S. Nuclear Regulatory Commission, 20555, one copy to the Regional Document Control Desk, Washington, D.C.

i 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.

I CORE OPERATING LIMITS REPORT 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 a reload cycle for the following-Moderator Temperature Coefficient BOL and E0L limits and 300 ppm 1.

surveillance limit for Specification 3/4.1.1.3, i

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

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

submittal should combine those sections that are common to all units the station; however, for units with separate radwaste systems, the s Jbmittal shall specify the releases of radioactive material from each unit.

Amendment No. Jf, 77, M,86, 6-19 MILLSTONE - UNIT 3 0255

o

&OMINJSTRATIVE CONTROLS 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUA

~

(REMODCM)

Section I, Radiological Effluent Monitoring 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 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 (ODCM), 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 REMODCM:

Shall be documented and records of reviews performed shall be retained as a.

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 1 to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective af ter review and acceptance by SORC and the approval of the Nuclear Station Director.

Shall be submitted to the Commission in the form of a complete, legible c.

copy of the entire REMM or ODCM, as appropriate, as a part of or concur-rent with the Annual Radioactive Effluent Rept,rt for the period of the report in which any cha' ige 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 REMODCH.

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.

MILLSTONE - UNIT 3 6-24 Amendment No. /#, Q,86.

i 0156

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