ML20155G475

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Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively,modifying Tech Specs to Provide for Uniform Addresses for Listed Classes of Repts for Plants
ML20155G475
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 09/28/1988
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20155G472 List:
References
TAC-68286, NUDOCS 8810170099
Download: ML20155G475 (27)
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!" n NUCLEAR REGULATORY COMMISSION 3 E WASHINGTON, D. C. A13655

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_ CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK FLANT AMENDMENT TO FACILITY OPERATING LICENSE Anendment No.107 License No. DPR-61

1. The Nuclear Regulatory Comission (the Comission) hos found that:

A. The application for amendment by Connecticut Yankee Atomic Power (the licensee), dated May 25, 1988, complies with the standards and requiremerits of the Atomic Energy Act of 1954, as amended (the Act), and the Connission'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 Comission; C. There is reasonable assurance (1) 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 cunducted in compliance with the Comission's regulations; D. The issuance of this arnendtrent will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendnent is in accordance with 10 CFR Part 51 of the Comistion's regulations and all applicable requiren=nts have been satisfied.

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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. l and paragraph 2.C.(2) of Facility Operating License No. DFR-61 is he.eby j amended to read as follows.

I (2) Technical Specifications The Techni e l Specifications contained in Appendix A, as revised i through Amendment No. 107, are hereby incorporated in the license.  !

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

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3. This license amendment is effective as of the date of issuance, to be ,

implemented within 30 d;ys of issuance. 1 FOR THE NUCLEAR REGULATORY COMMISSION d 1 Joh *F. Stolz, Direct r i

,. Project Directorate I-4 iDivision of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical l Specifications l

, Date of Issuance: September 28, 1988 I

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ATTACHMENT TO LICENSE AMENOMENT 110.107_

FACILITY OPERATING LICENSE NO. OPR-61 DOCKET NO. 50-213 Rep 14ce the following pdges of the Appendix "A" Technical Specifications with the enclused pdges. The revised p6ges are identified by amendment number dnd COntdin Vertical lines ind1Cdting the areds of chdnge, Remove Insert 6-15 6-15 6-16 6-16 6-18 6-18 0

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6.9 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20553, one copy to the Regional Administrator, r.egion I, and one copy to the NRC Resident Inspector unless otherwise noted.

6.9.1 Routine Reports

a. Startup Report - A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the i

license involving a planned increase in power level, (3) j installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the l

' nuclear, therma!, or hydraulic performance of the pl ant.

The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured valuas of the operating conditions or cnaracterigtics obtained during the test program and a l comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall be described. Any i

additional specific details required in license conditions based on other commitments shall be included in this report.

Startup reports shall be submitted within (1) 90 days j following completion of the startup test program, (2) 90 i days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup 1 Report does not cover all three events (i.e., initial j criticality, completion of startup test program, and '

resumption or commencement of commercial power j operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

b. Steam Generator Tube Inspection - The complete results '

of the steam gener'. tor tube inservice inspection shall be reported within ninety days af ter completion of the l' inspection. This report shallincludes

!) number and extent of tubes inspected.

2) 1.oca:lon and percent of wall thickness penetration l

t for each indication of an imperfection.

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3) Identification of tubes plutted.

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Amendment No. 25, 19, 25, 107 l

c. Occupational Exposure Report The annual report shall be submitted prior ta March 1 of each year and shall cover the previous calendar year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

This annual report shall include a f.abulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr. and their associated man-rem exposure according to work and job functions, 4/ e.g., reactor operations and surveillance Inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing and refueling. The dcse assignment to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% c! the total whole body dose received from e; al sources shall be assigned to specific major <ork functions.

d. Monthly Opera ting Reports - 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, with a copy to the Regional Administrator, Region I, and one co e , to the NRC Resident inspector, no later than the 15th of each month following the calendar month covered by the report.

The monthly report shall include a narrative summary of operating experience during the report period relating to safe operation of the facility, including safety-related main enance.

e. Reports required as per 10 CFR 50.59b.

6-16 Aniendment No. 25, 79, 85, 107

ADMINISTRATIVE CONTROLS SPECIAL REPORTS l

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

Regulatory Commission, Document Control Desk, Washington, D.C. 20535, one copy to the Regional Administrator, Region I, and one copy to the NRC Resident inspector, within the time period specified for er.ch report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the app!! cable reference specifications

a. Inservice Inspection results, Specifications (4.10) and (4.12).
b. Primary Contair. ment Leak Rate Results, Specification (4.4),
c. Reactor Vessel Material Surveillance Specimen i Examination, Specification (4.10),
d. Stearn Generator Tube Report Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 13 days,
e. Post-Accident Instrumentation Opera o~ llity, Specification (3.23 A and B).
f. Fire. Protection Systems Operabi!!ty, Specification (3.22).

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

a. Records and logs of facility operation covering the time interval at each power level.
b. Records and logs of principal mahtenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c. All reportable events.
d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

i 6-13 Amend?4nt No. 20, 66. M. 107 i

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h0RTHEASTJUCLEARENERGYCOMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR COWER STATION, UNIT NO. 1 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 23 License No. OPR-21

1. The Nuclear Regulatory Comission (the Comission) has found that:

A.

The et al.appthe (lication for amendment licensee), dated May by 25,Northeast Nuclear Energy Company, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as anended (the Act), and the Connission's rules and regulations set forth in 10 CFR Chapter I;

8. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) that the activities authorized by this amendirent can be conducted without endangering the health and safety of tr.e public, and (ii) that such activities will be conducted in con.pliance with the Co mission's regulations;
0. The issuance of this arendment will not be iniinical to the conunon defen'.,e and security or to the health and safety of the public; and E. The issuance of this amendinent is in accordance with 10 CFR Part 51 ,

of the Cornnission's regulations and all applicable requirernents have '

been satisfied.

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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-21 is hereby  ;

amended to read as follows: ,

(2) Technical Specifications i The Technical Specifications contained in Appendix A, as revised through Amendment No. 23 , are hereby incorporated in the license. l 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 REG LATORY COMMISSION I

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J l7. Stolz, Direct (Project Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 28, 1983 l

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ATTACHMENT TO LICENSE AftENDMENT NO. n FACILITY OPERATING LICENSE NO. OPR-21 DOCKET NO. 50-245 Replace the following pages of tiie Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendirent number and contain vertical lines indicating tha areas of change. The curresponding overiv4f pages are provided to neintain document completeness.

Remove Insert 6-17 6-17 6-18 6-18 6-19 6-19 l

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ADMINISTRATIVE CONTROLS 6.8.5 *All procedures and procedure changes required for the Radiological Environe.sntal Monitoring Program of 6.8.4 above shall be reviewed by an individual (other than the author) from the Radiological Assessment Branch or the Production Operation Service Laboratory (POSL) and approved by appropriate supervision.

Temporary changes may be made provided the intent of the original orocedure is not altered and the change is documented and reviewed by an individual (other than the author) from the Radiological Assessment Branch or the POSL, within 14 days of implementation.

6.9 REPORTIhG REQUIREMENTS Routine Reoorts  ;

i 6.9.1 In addition to ?he applicable reporting requirements of Title 10, Code of Federal Regulatior.s, the following reports shall be submitted to the U.S. Nuc. lear Regulatory Comission Document Control Desk, Washington, D.C 20555, one copy to the Regional Administrator, Region I, and one copy to the NRC Resident inspector unless otherwise noted.

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

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions of characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other comitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or comencement of comercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or comencement of comercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

Millstone Unit 1 6 17 Amendment No. 23

ADMINISTRATIVE CONTROLS Annual Reoorts M -

6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.

6.9.1.5 A tabulation, on an annual basis, of the number of station, utility and other personnel (including contractors) receiving exposures greaterthan100 mrem /yrandtheiraspeiatedman-remexposure according to work and job functions, e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (described maintenance), waste processing and refueling.

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD or film badge measurements. Small expo-sures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

Monthly Ooeratina Reoort 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submittej on a monthly basis to the U.S. Nuclear Regulatory Comission, Document Control Desk, Washington, D.C. 20555, one copy to the Regional Administrator, Region I, and one copy to the Resident inspector no later than the 15th of each month following the calendar month covered by the report.

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

The Annual Radiological Environmental Operating Report shall include the information delineated in the REM 00CH.

Semiannual Radioactive Effluent Release keoort 6.9.1.8 Poutine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

A supplemental report containing dose as:,essments for the previous year shall be submitted annually within 90 days after January 1.

J/ A single submittal may "we made for a multiple unit station. The submittal should combine those sec*. ions that are comon to all units at the station.

f 2/ This tabulation supplements the requirements of 20.407 of 10 CFR Part 20. j j

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l Millstone Unit 1 6 18 Amendmelt No. I, 23

' ADMINISTRATIVE CONTROLS The report shall include th1t information delineated in the REM 00CM.

  • Any changes to the REM 00CM shall be submitted in the Semiannual Radioactive Effluent Release Report.

6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission Document Control Desk, Washington, D. C. 20555, one co /

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 activr,tes identified below pursuant to the raquirement of the applica> ie reference specification:

a. In-service Inspection Results, Specification 4.6.F
b. Primary Containment Leak Rate Test Results, Sper. fica-tion 4.7.A.3.
c. Materials Radiation Surveillance Specimen F 4mination and Reruits, Specification 4.6.8.3. l
d. Fire detection instrumentation, Spect'. cation (3.12.E.2)
e. Fire suppression systems, Specifi'.4tions (3.12.A.2, 3.12.B.2, j and 3.12.C.2).

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f. Radiological Effluent Reports required by Specifications in l 3.8.C.2, 3.8.0.2, 3.8.D.3, and 3.8.0.4.

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

a. Records and logs of facility operation covering time interval .

at each power level.

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b. Records and logs of principal maintenance activities, l inspections, repair and replacement of principal items of equipment related to nuclear safety.
c. All REPORTABLE EVENTS.
d. Records of surveillance activities, inspections, and calibra-tions required by these technical specifications,
e. Records of reactor tests and experiments,
f. Records of changes made to operating procedures.
g. Records of radioactive .nipments.

Millstone Unit 1 6 19 Amendment No. Z. 23

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l ADMINISTRATIVE CONTROLS

h. Records of sealed source leak tests and results.
i. Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the facility operating license:

a. Records and drawing changes reflecting facility design modifications moy to systems and equipmer.t described in the Final Sa uty Analysis Report,
b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories.
c. Records of facility radiation and contamination surveys.
d. Records of radiation exposure for all individuals entering radiation control areas.
e. Records of gaseous and liquid radioactive material released to the environs, f.

Records of transients or operational cycles for those facility components designed for a limited number of transients or cycles.

g. Records of training and qualification for current members of the plant staff.
h. Records of inservice inspectic.1s performed pursuant to these l Technical Specifications.

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i. Records of quality assurance activities required by the QA Manual,
j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR Part 50.$9.
k. Records of meetings of the PORC, the NRB, the 50RC and the SNRB.
1. Records for environmental qualification.

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

' Amen #ent No. 1 Millstone Unit 1 -

6-20 JAN 2 S 1%7

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4 . ,o,, UNITED STATES l

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NORTHEAST NUCLEAR E8E'tGY COMPANY l THE CONNECTICUT LIGHT AtID POWER COMPANY THE WESTERd MASSACHUSETTS ELECTRIC COMPANY l

DOCKET _NO. 50-336 P3LOTONENUCLEARPOWERSTATION,UNITNO.2 l

AMEhCMENT TO FACILITY OPERAT1HG LICENSE l Amenoment No. 132 License No. DPR-65

1. The huclear Regulatory Comission (the Connission) has found that: l i

A. The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated May 25, 1988, complies with the stancards and requirements of the Atomic Energy Act of 1954, es arended (the Act), and the Connission'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 Connission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conoucted without endangering the health and safety of the public, ono (ii) that such activities will be conducted in coropliance with the Connission's regulations; D. The issuance of this amendment will not be inimical to the ccanon defense and security or to the health and safety of the public; and E. The issuance of this amendtrent is in accordance with 10 CFR Part 51 i of the Connission's regulations and all applicable requirements have

been satisfied.

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2. Accordingly, the license is amended by changes to the Technical ,

Specifications as indicated in the attachment to this licen',e amendment, l and paragraph 2.C.(2) of Facility Operating License No. DPrr 65 is hereby 1 amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised l through Amendment No.132 , 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, j FOR THE NUCLEAR REGULAT RY COW!SSION n% ./-- /

John /E.Stolz. Director Project Directorate I-4 DWision of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications l

Date of Issuance: September 28, 1988 l

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ATTACHMENT TO LIC,E'4SE AMENOMENT NO. 3,9 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by anwndrent number and COntain VertiC8l lin85 indicating the dreds of change. The corresponding overleaf pages are provided to maintain document ccepleteness.

Rer.ov e insert 6-17 6-17 6-19 6-19

f ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a. The intent of original precedure is not altered,
b. The change is approved by two members of the plant manage-ment staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

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c. The change is documented, reviewed by the PORC/SORC, as applicable, and approved by the Unit Superintendent / Station Superintendent within 14 days of implementation.

, 6.8.4 Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the REM 00CM.

6.8.5 All procedures and procedure changes required for the Radiological Enviror. mental Monitoring Program of 6.8.4 above shall be reviewed by an individual (other than the authori from the Radiological Assessment Branch or the Production Operation Ser m s Laboratory (POSL) and approved by appropriate supervision.

Temporary changes may be made provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other than the author) from the Radiological Assessment Branch or the POSL, within 14 days of implementation.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS ,

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6.9.1 In addition to the a;,plicable reporting requirements of Title 10, I Code of Federal Regulations, the following reports shall be submitted to the ,

U.S. Nuclear Regulatory Comission Document Control Desk, Washington, D.C.

20555, one copy to the Regicnal Administrator, Region 1, and one copy to the NRC Resident Inspector, unless otherwise noted. .

STARTUP REPORT  !

, 6.9.1.1 A sumary report of plant startup and power escalation testing shall be submitted followtug (1) receipt of an operating license, (2) amendment to he licea.se involving a planned increase in power level, (3) installation of iuel the, eu a different design or has been manufactured by a different fuel l ;upol v , W (4) modifications that may have significantly altered +he .

er. w . e,m l or hydraulic performance of the plant, 1

i . 4 startup report sall address each of the tests identified in the

{ .h da include a description of the measursJ values of the operating I pt or characteristics obtained during the test program and a 4  %, *

)f these values with design predictions and specificatioas. Any add 9 ,..i spectfic details required in license conditions based on other consei: 'ts shall be included in this report, i a ndment No. 29,28,36,45, MILLSTONE UNIT 2 6-1l j 93,Z04,ZZZ,132

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1 AD'41NISTRATIVE CONTROLS 6.9.1.3 Startupreportsshallbesubmittedwithin(1)90daysfollowingcomple-tion of the startup test program, (2) 90 days following resumption or comence- J ment of comercial power operation, or (3) 9 months following initiM criticality, l whichever is earliest. If the Startup Report does not cover all thi.!e events I (i.e., initial criticality, completion of startup test program, and resumption or comencement of comercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

AN?.UAL REPORTSM 6.9.1.4 Annual reports covering the activities of the unit as described below for  !

the previous calendar year shall be suNnitted prior to March 1 of each year. The l initial report shall be submitted prior to March 1 of the year following initial c ri tica li ty.

6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility and other personnel (incleding contractors) receiving exposures greater than 100 mrem /vr and thgtr asso:13ted man-rem exposure according to 1 work and job functions 1/ e.g., reactor operations and surveillance, I inservice inspection, routine maintenance, special maintenance (describe  !

{ maintenance), waste processing and refueling. The dose assignment to various duty functions may be estimates based on po:ket dosimeter, TLD )

or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted fer. In the aggregate, at least 80% of the total whole body dose received from ey*?rnal sources shall be assigned to specific major work functions.

b. The complete results of steam generato" tube inservice inspections l perfomed during the report period (reference Speelfication 4.4.5.5.b). '
c. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2)Resultsofthe ,

j last isotopic analysis for radiciodine perfomed prior to exceeding the limit, results of analysis while limit was exceeded and results of one i analysis after the radiciodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function c.f time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit. .

1/ A single submittal may be made for a multiple unit station. The submittal l should combine those sections that are comon to all units at the station, l 1

y This tabulation supplements the requirements of 520.407 of 10 CFR Part 20.  ;

HILLSTONE - UNIT 2 6-18 Amendment No. 36,7JJ 115, FEB 3 1947

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ADMINISTRATIVE CONTROLS

. 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 velves.

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Document Cor. trol Desk, Washington. 0.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.

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 V.ime period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a. Inoperable Seismic Monitoring Instruinentation, Specification 3.J.3.3.
b. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.
c. Safety Class 1 Inservice Inspection Program Review, Specification 4.4.10.1.
d. ECCS Actuation, Specifications 3.5.2 and 3.5.3.
e. Fire Detection Instrumentation, Specifications 3.3.3.7.
f. Fire Suppression Systems, Specifications 3.7.9.1 and 3.7.9.2.
g. RCS Overpressure Mitigation, Specification 3.4.9.3
h. Radiological Effluent Reports required by Specifications 3.11.1.2, 3.11.2.2, 3.11.2.3 and 3.11.4.
i. Degradation of containment structure, Specification 4.6.1.6.4.

J. Steam Generator Tube Inspection, Specification 4.4.5.1.5.

k. Accident Monitoring Instrumentation, Specification 3.3.3.8. j
1. Radiation Monitoring Instrumentation, Specification 3.3.3.1.
m. Reactor Coolent System Vents, Specification 3.4.11.

MILLSTONE - UNIT 2 6-19 Amendment No. 36,93,Z04,III, IZ5,IZ9,Z20,132

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l ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION -

6.10.1 The following records shall be retained for at least five years:

a.

Records each and power logs 'of facility operation covering time interval at level. -

b.

Records and logs of principal mafr.tenance activities, inspections, repair and replacement of principal items of equipment related to nutie. safety.

c. All REl1RTABLE EVENTS.
d. .

Records i f surveillance activities, inspections and calibrations required by these Technical Specifications. l

e. Records of reactor tests and experiments.
  • 1 f.

Records of changes made to operating proceduras,

g. Records of r3dioactive shipments.

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Records of sealed source leak tests and results. l i.

Records of record.of annual physical inventory of all sealed source material 6.10.2 .

facility operating license:The following records shall be retained for the duration a.

Records and drawing changes reflecting facility design modifications made to systems and equipment deserthed it Report, the Final Safety Analysis b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories,

c. ,,Pecords of facility radiation and contamination surveys.
d. ,

Re' cords of radiation exposure for all individuals entering radiation control areas.

e.

'Recor'ds' of gaseou's and liquid radioactive uterial released to the environs.

f.

Records of transient or operational cycles for those facility components destgrad for a limited number of transients or cycles.

MILLSTONE - UNIT 2 6-20 Amenenent No. f,33,M/,111,

na q% l o, UNITED STATEh

[e kt NUCLEAR REGULATORY COldMISSION W ASHINGTota, D. C. 20668

\....}

NORTHEAST ll0 CLEAR ENERGY COMPANY, ET AL.*

DOCKET NO. 50-423 H_!LLSTONE NUCLEAR POWER STATION, UNIT NO. 3

]

AMEN 0HENT TO FACILITY OPERATINS LICENSE Amendment No. 24 License No. NPF-49

1. The Nuciter Regulatory Cossnission (the Coonission) has found that: I A. The application for uendment by Northeast Nuclear Energy Company, l et 41 (the licensee) dated May 25, 1988, complies with the i standards and requirements of the Atomic Energy Act of 1954, 1 as emnded (the Act), end the Comission's rules ano regulations ,

i set forth in 10 CFR Chapter I; i l E. The facility will operate in conformity witn the application, the provisions of the Act, and the rules anc regulations of the

, Corsaission;

.\ \

l C. There is reasonable assurance (i) that the activities authorized by l this omendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in corpliance with the Comission's regulations;

0. The issuance of this esendment will not be inimical to the coninon j defense and security or to the health and safety of the pblic; and i

E. The issuance of this amendrent is in accordance with 10 CFR Part 51 of the Cosmission's regulations eno all applicable requires =nts have I been settsfied.

~

1

  • Northeast Nucitar Energy Company is authorized to act es agent and represent-stive for the folluwing Owners: Central Heine Power Company, Central Vermont Public Service Corporation, Chicopes Municipal Lighting Plant, City of Burlington, Vermont, Connecticut Municipal Electric Light Company, Messachusetts Municipal Wholesale Electric Corpeny, Monteup Electric Company, flew England power Company, The Villege of Lyndonville Electric Department Western
Massachusetts Electric Company, and Vermont Electric Generation and Transanssion Cooperetive, Inc., and has exclusive responsibility end control s

over the physical construction, operation and maintenance of the facility.

-2

__  ?. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachtnent to this license amereent, 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. 24 , and the Environmental Protection Plan contained in APoendix 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.

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

FOR THE NUCLEAR REGUL TORY CCW ISSION

/

J6h F. Stoir, Director Project Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 28, 1988

j MTACHFENT 70_ LICENSE AMENDHENT NO. 24 FACILT!Y OPERATING LICENSE NO. NPF-49 DOCKET N0._50-423 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by arnendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages era provided to maintain document completeness.

Reseve Insert 6 19 6-19 6-21 6-21 6-22 6-22 F

- _ _ _ _ _ _ _ . _ _ _ . - _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' '~'"

, ADMINISTRATIVE CONTROLS 6.8.5 Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the REM 00CM.

6.8.6 All procedures and procedure changes required for the Radiological Environmental Monitoring Program of Specification 6.8.5 above shall be reviewed by an individual (other than the author) from the Radiological Assessment Branch or the Production Operation Services Laboratory (POSL) and approved by appro priate supervision.

Temporary changes may be made provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other i than the author) from the Radiological Assessment Branch or the POSL, within 14 days of implementation.

6.9 REPORTING REQUIREMQLi ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Faderal Regulations, the following reports shall be submitted to the U.S.

Nuclear Regulatory Comission, Document Control Desk, Washington, D.C. 20555, one copy to the Regional Administrator, Region 1, and one copy to the NRC Resident Inspector, unless otherwise noted.

STARTUP REPORT 6.9.1.1 A sumary report of plant startup and power escalation testing shall be submitted following: (1) receipt of an Operating License, (2) amendment to the license involving a planned increase iri power level, (3) installation of fuel that has a different design or has been manufactured by a differwnt fuel supplier, and (4 nuclear, thermal), or hydraulic performance of the unit. modifications that may have sig The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program

, and a comparison of these values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license I conditions bised on other comitments shall be included in this report.

Startup Reports shall be submitted within: (1) 90 days following completion of l the Startup Test Program, (2) 90 days following resumption or comencement of '

comercial power operation, or (3) 9 months following initial criticality, I whichever is earliest. If the Startup Report does not cover all three events I i (i.e., initial criticality, completion of Startup Test Program, and resumption or comencen,ent of comercial operation), supplementsry repnrts shall be submitted at least every 3 months until al' threa events have been completed.

4

$ NUAL REPORTS

  • 6.9.1.2 Annual Reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each I
  • A single submittal may be made for a multiple unit station. The submittal should combine those sections that are comon to all units at the station.

i MILLSTONE - UNIT 3 6 19 Amendment No. 24

AD,MINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures ,

greater than 100 mrem /yr and their associated man-rem exposure '

j according to wc- and job functions" (e.g., reactor operations and surveillance. . arvice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling).

3 The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accourited for. In the aggregate,

at least 80% of the total whole-body dose received from external t sources should be assigned to specific major work functions; '
b. The results of specific activity analyses in which the reactor toolant exceeded the limits of Specificatien 3.4.8. The following informa-tion shall be included: (I) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in whic's the limit was exceeded (in
graphic and tabular format); (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit. ' '

results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than 1

limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up flow history starting

, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; ,

l (4) Graph of the I-131 concentration (pCi/gm) and one other radio- i i idine isotope concentration (pCi/gm) as a function of time for the l i 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.

, c. Documentation of all challenges to the pressurizer power-operated relief valves (PORVs) and safety valves; and I

1 ANNUAL PADIOLOGICAL ENVIRONMENTA' OPERATING REPORT **

6.9.1.3 Routine Annual Radic*ogical 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 Reports shall include that information delineated in the REM 00CM.

  • This tabuiation supplements the requirements of 520.407 of 10 CFR Part 20.
**A single submittal may be made for a multiple unit station.
MILLSTONE - UNIT 3 6-20

ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

  • 6.9.1.4 Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

A supplemental report containing dose assessments for the previous year shall be submitted annua?ly within 90 days after January 1.

The report shall include that information delineated in the REM 00CM.

Any changes to the REM 00CM shall be submitted i r. the Semiannual Radioactive Effluent Release 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.

RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.6 The F,y limits for RATED THERMAL POWER (F, ) shall be provided to I the U.S. Nuclear Regulatory Comission, Document Control Desk, Washington, i

D.C. 20555, one copy to the Regional Administrator Region I, and one copy to the NRC Resident inspector, for all core planes containing Bank "D" control rods and all unrodded core planes and the plot of predicted (Ff .Pg ,)) y, Axial Core Height with the limit envelope at least 60 days prior to each cycle initial triticality unless otherwise approved by the Comission by letter. In addition, in the event that the limit should change requiring a new substan-tial or an amended submittal to the Radial Peaking Factor Limit Report, it will be submitted 60 days prior to the date the limit would become effective unless otherwise approved by the Commission by letter. Any information needed tosupportFI}P will be by request from the NRC and need not bt included in this report.

  • 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 21 Amendment No. 24

ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Comission, Document Control Desk, Washington 0.C. 20555, one copy to the Regional Administrator Region I, and one copy to the NRC Resident Irspector, within the time period specified for each report, 2 6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10 Code of Federal Regulations, the following records shall be retained i 4 for at least the minimum period indicated.

6.10.2 The following records shall be retained for at least 5 years:

a. Records and logs of unit operation covering time interval at each power level;
b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety;
c. All REPORTABLE EVENTS;
d. Records of surveillance activities, inspections, and calibrations required by these Technical Specifications;
e. Records of changes made to the procedures required by Specification 6.8.1;
f. Records of radioactive shipinents;
g. Records of sealed source and fission datector leak tests and rt ,lts; and
h. Records of annual phytical inventory of all sealed source material of record.

6.10.3 The following records shall be retained for the duration of the unit Operating License:

a. Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report;
b. R6 cords of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories;
c. Records of radiation exposure for all individuals entering radiation control areas; MILLSTONE - UNIT 3 6 22 Amendment No. 24
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