ML20207H955

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Proposed Tech Specs Section 6.0 Re Administrative Controls
ML20207H955
Person / Time
Site: Millstone  Dominion icon.png
Issue date: 03/05/1999
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20207H908 List:
References
NUDOCS 9903160150
Download: ML20207H955 (18)
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Text

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Docket No. 50-336 50-423 B17604 i

Attachment 2 Millstone Nuclear Power Station, Unit Nos. 2 and 3 Retyped Pages March 1999 I~

9903160150 990305 DR ADOCK O p

idDEX AfWTNT(TRATTWF rnMTDalC SECTION Eggg 6.I RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 6.2 ORGANIZATION .......................... 6-1 Offsite and Onsite .................... 6-1 Facility Staff ...................... 6-1 6.3 FACILITY STAFF OVALIFICATIONS .................. 6-2 6.4 TRAINING ............................ 6-5 121 DELETED 125 DELETED 5Z DELETED 6.8 PROCEDURES ........................... 6-14 NILLSTONE - UNIT 2 XVI Amendment No. JJe Jpfe JJJo J7Je Ifle 191,19(o 191, 0447

1 INDEX ADMINISTRATIVE CONTROLS SECTION EAGE 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS . . . . . . . ................. 6-16 STARTUP REPORTS . . . . . . ................. 6-16 ANNUAL REPORTS . . . . . . . ................. 6-17 ANNUAL RADI0 ACTIVE EFFLUENT REPORT .............. 6-18 MONTHLY OPERATING REPORT . . ................. 6-18 CORE OPERATING LIMITS REPORT ................. 6-18 ,

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

1212 DELETED I 6.11 RADIATION PROTECTION PROGRAM . ................. 6-22 6.12 HIGH RADIATION AREA . . . . . ................. 6-22 6.13 SYSTEMS INTEGRITY . . . . . . . . . . . . . . . . . . . . . . . . 6-23 6.14 IODINE MONITORING . . . . . . . . . . . . . . . . . . . . . . . . 6-23 l

6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) ................. 6-24 6.16 RADI0 ACTIVE WASTE TREATMENT . ................. 6-24 f2J7 SECONDARY WATER CHEMISTRY . . . ................. 6-25 6.18 PASF/ SAMPLING AND ANALYSIS OF PLANT EFFLUENTS . . . . . . . . 6-25 NILLSTONE - UNIT 2 XVII Amendment No. 79,79,97,99,191, wu, 199. 111, 199, 191, 191 199,

CONTAll9 TENT SYSTEMS SURVEILLANCE REQUIREMENTS i b. Removing one wire from a dome, a vertical and a hoop tendon checked for l

lift off force pursuant to Specification 4.6.1.6.1.a and determining that over the entire length of the removed wire that:

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1. The tendon wires are free of corrosion.

l 2. There are no changes in physical appearance of the sheathing filler grease.

3. A minimum tensile strength of 11,760 pounds for at least three wire samples (one from each end and one at mid-length) cut from each removed wire. Failure of any one of the wire samples to meet the minimum tensile strength test is evidence of abnormal degradation of the containment structure.

4.6.1.6.2 End Anchoraaes and Ad.iacent Concrete Surfaces The structural integrity of the end anchorages and adjacent concrete surfaces shall be demonstrated by determining through inspection that no apparent changes or degradation has occurred in the visual appearance of the end anchorage concrete exterior surfaces or as indicated by the concrete crack patterns adjacent to the end anchorages. Inspections of the concrete shall be performed concurrent with the containment tendon surveillance (reference Specification 4.6.1.6.1).

4.6.1.6.3 Liner Plate The structural integrity of the containment liner plate shall be determined in accordance with the Containment Leakage Rate Testing Program.

4.6.1.6.4 Reports In lieu of any other report required by Section 50.73 to 10 CFR Part 50, an initial report of any abnormal degradation of the containment structure detected during the above required tests and inspections shall be made within 10 days after completion of the surveillance requirements of this specification and the detailed report shall be submitted pursuant to Specification 6.9.2 within 90 days after completion. This report shall include a description of the condition of the concrete (especially at tendon anchorages), the inspection procedure, the tolerances on cracking, and the corrective actions taken.

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I 3/4 6-11 Amendment No. JJJ, JJJ, JJJ. i MIfLSTONE-UNIT 2

1 PLANT SYSTEMS

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unnvrtii nrr nrnistarurur (canammay If any snubber selected for testing either fails to lock-up or fails to move (i.e., frozen in place), the cause will be evaluated and if caused by manufacturer design deficiency, all snubbers of the same design subject to the same defect shall be tested regardless of location or difficulty or removal. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the test acceptance criteria.

For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snub-ber(s). The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order l to ensure that the supported component remains capable of meeting i

! the designed service.

e. Hydraulic Snubbert Functional Test Acceptance Criteria l

The hydraulic snubber functional test shall verify that:  !

1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and i Comprk;.sion.
2. Snubber bleed, or release rate, where required, is within the specified range in compression or tension.
f. Mechanical Snubbers Functional Test Acceptance Criteria
  • The mechanical snubber functional test shall verify that:
1. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.
2. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
g. Snubber Service Life Monitorina A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Quality Assurance Program Topical Report.

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  • Mechanical snubber functiona: test acceptance criteria shall become effective I upon installation of snubber testing equipment but not later than June 30,

! 1985.

NILLSTONE - UNIT 2 3/4 7-22a Amendment No. pp, JJp, Jpp 0443

ADMINISTRATIVE CONTROLS fJ._ TRAINING A retraining and replacement training program for the facility staff shall be maintained under the direction of the Senior Vice President and CN0 -

Millstone and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.59. The Director-Nuclear Training has the overall responsibility for the implementation of the Training Program.

5 J Deleted. l l

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I Millstone Unit 2 6-5 Amendment No. JpJ, J/J, J7J.

PAGES 6-6 THROUGH 6-13 HAVE BEEN INTENTIONALLY DELETED, Millstone Unit 2 6-6 Amendment No. # , # , M , 77, o<u 111,1H,1H,1H,1H,1H,FM

3 ADMINISTRATIVE CONTROLS 54t Deleted.

f l Deleted.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recomended in Appendix "A" of Regulatory Guide 1.33, February,1978.
b. Refueling operations.
c. Surveillance activities of safety related equipment.
d. Not used,
e. Not used.

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Millstone Unit 2 6-14 Amendment No. 17,17,77,77. I o<<< 111,191e 17f 199e 191e 191e 199

ADMINISTRATIVE CONTROLS 1

f. Fire Protection Program implementation. 1
g. Quality Control for effluent monitoring using the guidance in Regulatory Guide 1.21 Rev.1, June 1974.
h. Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REM 0DCM) implementation, except for Section I.E.,

Radiological Environmental Monitoring.

6.8.2 a. The Unit 2 Unit Director or Millstone Unit 2 Recovery Officer or Senior Vice Presidciit and CN0 - Millstone may designate specific procedures and programs, or classes of procedures and programs to be reviewed in accordance with the Station Qualified Reviewer Program in accordance with the Quality Assurance Program Topical Report.

b. Procedures and programs listed in Specification 6.8.1, and changes thereto, shall be approved by the Unit 2 Unit Director or Senior Vice President and CN0 - Millstone or by cognizant Manager or Directors who are designated as the Approval Authority by the Unit 2 Unit Director or Senior Vice President and CN0 - Millstone, as specified in administrative procedures. The Approval Authority for each procedure and proo-am or class of procedure and program shall be specified in administrative procedures.
c. Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed and approved in accordance with the Quality Assurance Program Topical Report, prior to implementation. Each procedure of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.

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

a. The intent of original procedure is not altered.

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b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's ,

License on the unit affected. I

c. The change is documented, reviewed and approved in accordance with the Quality Assurance Program Topical Report 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 0DCM.

Millstone Unit 2 6-15 Amendment Nos. J7, 77, jlp, JJJ, o*** 19), life 191,199,

1 ADMINISTRATIVE CONTROLS SPECIAL REPORTS (CONT.)

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. Deleted
f. Deleted
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.

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1. Degradation of containment structure, Specification j 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.
l. Radiation Monitoring Instrumentation, Specification 3.3.3.1.
m. Reactor Coolant System Vents, Specification 3.4.11.

QJO Deleted. I i

l Millstone Unit 2 6-20 Amendment No. 7, 17, 1p(,

o**s file 199 191, 191, Ifle

This page intentionally deleted.

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lstone Unit 2 6-21 Amendment No. 7, JJ, ypg, .

III,Iff,Ill, 191,191, \

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L AnMTMitTDATTWF rfwTDIM t I

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

6.12 HIGH RADIATION AREA 5.12.1 Pursuant to paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the

" control device" or " alarm signal" required by paragraph *Q.203(c),

each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mR/h at 45 cm (18 in.) froe. the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area; or
b. A radiation monit c. 4 Cevice whicn continuously integrates the ra.. ' dose rate in the area and alarms when a preset integeated dose is received. Entry into l such areas with this monitoring device may be made after i the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or I
c. An individual qualified in radiation protection procedures '

with a radiation dose rate monitoring device, who is responsible for previding positive control over the activities within &e area and shall perform periodic radiation surveillance at the frequency specified by the i Health Physics Manager in the RWP.

Millstone Unit 2 6-22 Amendment Mos. J. 77, Ipp, ous lil,lif,191,

)

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 i 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 LC0's contained in these Technical Specifications.

Changes to the REM 00CM:

a. Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Topical Report. 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 in accordance with the Quality Assurance Program Topical Report.
c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire REP #1 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.

Millstone Unit 2 6-24 Amendment No. J M , J M , / # , 177, 0446 JM,

i INDEX ADMINISTRATIVE CONTROLS SECTION PAGE l 1

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6.1 RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 l

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6.2 ORGANIZATION . . . . . . . . . . . . . . . . . . . . . . . . . .

6-1 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS . . . . . . . . . . . . . . . 6-1 6.2.2 FACILITY STAFF . . . . . . . . . . . . . . . . . . . . . . . . 6-1 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION . . . . . . . . . . . . 6-3 6.2.3 DELETED l 6.2.4 SHIFT TECHNICAL ADVISOR . . . . . . . . . . . . . . . . . . . 6-4 I

6.3 FACILITY STAFF OVALIFICATIONS . . . . . . . . . . . . . . . . . 6-5 6.4 TRAINING . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-5 ,

121 DELETED 115 DELETED fil DELETED MILLSTONE - UNIT 3 xviii Amendment No. JJ 77, JJ, 77, JJJ,  !

0637 life l

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INDEX ADMINISTRATIVE CONTROLS SECTION EAGE 6.8 PROCEDURES AND PROGRAMS . . . . . . . . . . . . . . . . . . . . . 6-14 6.9 REPORTING REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . 6-17 6.9.1 ROUTINE REPORTS . . . . . . . . . . . . . . . . . . . . . . . 6-17 Startup Report . . . . . . . . . . . . . . . . . . . . . . . 6-17 Annual Reports . . . . . . . . . . . . . . . . . . . . . . . 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 REPORTS . . . . . . . . . . . . . . . . . . . . . . . 6-21 fi1Q DELETED l 6.11 RADIATION PROTECTION PROGRAM . . . . . . . . . . . . . . . . . . 6-22 6.12 H I GH RAD I AT I ON AR EA . . . . . . . . . . . . . . . . . . . . . . . 6 - 23 6.13 RADIOLOGICAL FFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM) . . . . . . . . . . . . . . . . . . 6-24 6.14 RADI0 ACTIVE WASTE TREATMENT . . . . . . . . . . . . . . . . . . . 6-24 MILLSTONE - UNIT 3 xix Amendment No. 77, JJ, 77, pp, J77, 0637

2.0 SAFETY LINITS AM LIMITIM SAFETY SYSTEN SETTIMS 2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (T ) shall not exceed the limits shown in

' Figures 2.1-1 and 2.1-2 for four and three loop operation, respectively.

APPLICABILITY: MODES I and 2.

ACTION:

- Whenever the point defined by the combination of the highest operating loop average temperature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within I hour. I REACTOR COOLANT SYSTEN PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2750 psia.

APPLICABILITY:- MODES 1, 2, 3, 4, and 5.

ACTION:

MODES I and 2:

Whenever the Reactor Coolant System pressure has exceeded 2750 psia be in HOT STANDBY with the Reactor Coolant System pressure within its limit within I hour. I MODES 3, 4 and 5:

Whenever the Reactor Coolant System pressure has exceeded 2750 psia, reduce the Reactor Coolant System pressure to within its limit within 5 minutes. I i 1

l NILLSTONE - UNIT 3 2-1 Amendment No.

oeso

INSTRUNENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTION LINITING CONDITION FOR OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE.

APPICABILITY: MODES 1, 2,* and 3.*

ACTION:

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

SURVEILLAF AEQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.

4.3.4.2 The above required Turbine Overspeed Protection System shall be maintained, calibrated, tested, and inspected in accordance with the Millstone Unit No. 3 Turbine Overspeed Protection Maintenance and Testing Program.  !

Adherence to this program shall demonstrate OPERABILITY of this system. The l program and any revisions should be reviewed and approved in accordance with the Quality Assurance Program Topica'i Report. Revisions shall be made in accordance with the provisions of 10CFR50.59.

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  • Not applicable in Mode 2 or 3 with all main steam line isolation valves and associated bypass valves in the closed position and all other steam flow ,

paths to the turbine isolated. ]

I NILLSTONE - UNIT 3 3/4 3-81 Amendment No. # ,

0631 i.

I PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l l

h. Functional Testina of Repaired and Reolaced Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced. Replacement snubbers and snubbers which have repairs which might affect the functional test results shall be tested to meet the fune.tional test criteria before installation in the unit. Mechanical snubbers shall have met the acceptance criteria subsequent to their most recent service, and the freedom-of-motion test must have been performed within 12 months before being installed in the unit.
1. Snubber Service Life Procram 1

The service life of hydraulic and mechanical snubbers shal: ce I monitored to ensure that the service life is not exceeded between surveillance inspections. The maximum expected service life for ,

various seals, springs, and other critical parts shall be deter- )

mined and established based on engineering information and shall be  !

extended or shortened based on monitored test results and failure I history. Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber ,

is required to be OPERABLE. The parts replacements shall be docu- I mented and the documentation shall be retained in accordance with Quality Assurance Program Topical Repor.. I I I

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l i MILLSTONE - UNIT 3 3/47-26 Amendment No.

l 0632

I ADNINISTRATIVE CONTROLS 6.2.3 Deleted. l 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.

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NILLSTONE - UNIT 3 6-4 Amendment No. 7J, pp, J77, oess

ADNINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum l

qualifications of ANSI N181-1971 for comparable positions, except for:

a. If the Operations Manager does not hold a senior reactor operator license for Millstone Unit No. 3, then the Operations Manager shall have held a senior reactor operator license at a pressurized water reactor, and the Assistant Operations Manager shall hold a senior reactor operator license for Millstone Unit No. 3.
b. The Health Physics Manager shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1, May 1977.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility scm.t shall be maintained under the direction of the Senior Vice President and CN0 -

Millstone and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.59. The Director-Nuclear Training has the overall respoisibility for the implementation of the Training

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Program.

6.4.2 Deleted.

115 Deleted. I i

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i MILLSTONE - UNIT 3 6-5 Amendment No. 77, 77, pf, pp. 77,  !

oeu 119,Ill, life

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PAGES 6-6 THROUGH 6-13 HAVE BEEN INTENTIONALLY DELETED.

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i MI,LLSTONE - UNIT 3 6-6 Amendment No. 77, pp, pp, pp, Jpp,

ADNINISTRATIVE CONTROLS JJ Deleted, il Deleted.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978;
b. The applicable procedures required to implement the requirements of NUREG-0737 and supplements thereto;
c. Refueling operations;
d. Surveillance activities of safety related equipment;
e. Not used.

NILLSTONE - UNIT 3 6-14 Amendment No. 77 77, JJJ, JJJ, oeu ^ 119,11),

4

ADMINISTRATIVE CONTROLS

f. Not used.

g._ Fire Protection Program implementation;

h. Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21, Rev.1, June 1974; and
i. Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM) implementation except for Section I.E, Radiological Environmental Monitoring.

6.8.2 a. The Unit 3 Unit Director or Vice President - Millstone Unit 3 or Senior Vice President and CN0 - Millstone may designate specific '

procedures and programs, or classes of procedures and programs to be reviewed in accordance the Quality Assurance Program Topical Report.

b. Procedures and programs listed in Specification 6.8.1, and changes thereto, shall be approved by the Unit 3 Unit Director or Senior Vice President and CN0 - Millstone or by cognizant Manager or Directors who are designated as the Approval Authority by the Unit 3 Unit Director or Senior Vice President and CN0 - Millstone, as specified in administrative procedures. The Approval Authority for each procedure and program or class of procedure and program shall be specified in administrative procedures.
c. Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed and approved in accordance with the Quality Assurance Program Topical Report, prior to implementation. Each procedure of Specification 6.8.1 shall be reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided: l

a. The intent of the original procedure is not altered; j
b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license on the unit affected; and
c. -The change is documented, reviewed in accordance with the Quality Assurance Program Topical Report, within 14 days of implementation. ,

MILLSTONE - UNIT 3 6-15 Amendment No. pp, pp, JJ), Jgp, 17) 0634

c AnMTMTtTRATTWF rnMTDnlC 6.9.1.6.c The' core operating limits shall be determined so that all applica-ble limits (e.g. fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.6.d The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Adminis-trator and Resident Inspector.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, one copy to the Regional Administrator Region I, and one copy to the NRC Resident Inspector, within the time period specified for each report.

5 2 Deleted, l

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l NILLSTONE - UNIT 3 6-21 Amendment No. 17, pp, pp 0635 1

r ADNINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAN 6.11.1 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.

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gjLSTONE-UNIT 3 6-22 Amendment No pp, pp, ypp,

I ADMINISIRATIVE CONTROLS 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL fREM0DCM)

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 l exposure pathways and for those radionuclides released as a result of station I operation. It shall also specify operating guidelines for radioactive waste treatment systems and report content.

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

Changes to the REM 0DCM:

a. Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Topical Report. This documentation I 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 '9 CFR 20.106, 40 CFR Part 190, i

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 in accordance with the )

Quality Assurance Program Topical Report.

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 by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and l 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 cl1 operations involving offsite releases of radioactive effluents. These procedi1res shall specify the use of appropriate waste treatment systems utilizing t 6 guidance provided in the REMODCM.

The Solid Rad'.oactive 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. JJ, 77, JJ, JJ, JJJ, 0636

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