ML20058Q135

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Proposed Tech Spec Section 6, Administrative Controls
ML20058Q135
Person / Time
Site: Pilgrim
Issue date: 08/09/1990
From:
BOSTON EDISON CO.
To:
Shared Package
ML20058Q134 List:
References
NUDOCS 9008210111
Download: ML20058Q135 (39)


Text

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)

f Pace No.

4.0 MISCELLANEOUS RADI0 ACTIVE MATERIALS SOURCES 206k 4.1 Sealed Source Contamination 206k 4.2 Surveillance Reauirements 206k  :

4.3 Reports 2061 4.4 Records Retention 2061 5.0 MAJOR DESIGN FEATURES 206m  !

t 5.1 Site features 206m 5.2 Reactor 206m '

5.3 Reactor Vessel 2eL 5.4 Containment f fo '

5.5 Fuel Storage $  :

-5.6 Seismic Design 70 )

6.0 ADMINISTRATIVE CONTROLS &c 6.1 Responsibility 208 6.2 Crganization 208 6.3 Unit Staff Qualifications 209 6.4 Training- 209 .

6.5 Review and Audit 211 l 6.6 Reportable Event Action 215 .

6.7 Safety Limit Violation 216 6.8 Procedures 216 6.9 Reporting Requirements 217 ,

6.10 Record Retention 219 6.11 Radiation Protection Program 221  :

6.12 (Deleted) y 6.13 High Radiation Area 221 6.14 Fire Protection Program 222 Ooerational Obiectives Surveillance i

7.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 8.0 - 229 7.1 Monitoring Program 8.1 229 7.2 Dose - Liquids 8.2 232 7.3 Dose - Noble Gases 8.3- 233 7.4 Dose - Iodine-131, Iodine-133, 8.4 234 Radioactive Material-in Particulate Form, and Tritium l- 7.5 Total Dose 8.5 234 i

[hk8210111 9H30809 p ADOCK 05000293 PDC Revision Amendment No. 35, 45, 88, 89, 95, 122 iii 4

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY The Station Director shall be accountable for overall facility operation. In his absence, the Station Director shall designate, in writing, the individual to assume this responsibility.

6.2 ORGANIZATION A. OFFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions'for activities affecting the safety of the nuclear power plant.

1. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and. including all operating organization positions. These relationships shall be documented and updated .as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in Pilgrim Station Final Safety Analysis Report.
2. The Station Director shall be responsible for overall unit safe '

operation and shall have control over those onsite activities '

necessary for safe operation and maintenance of the plant.

3. The Senior Vice President - Nuclear shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support .-

to the plant to ensure nuclear safety. +

4. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may F report to the appropriate onsite manager; however, they shall
  • hau sufficient organizational freedom to ensure their independence from operating pressures.

B. UNIT STAFF l

1. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

i Revision

  • Amendment No. 69, 80, 88, 122 125 208 c:

~6 ,0 ADMINISTRATIVE CONTROLS

, 2. When the unit is in an operational mode other than cold shutdown or refueling, a person holding . Senior Reactor Operator License shall be present in the control room at all times. In addition to this Senior Operator, a Licensed Operator or Senior Operator shall be present at the controls when fuel is in the vessel.

3. At least two Licensed Operators shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips.
4. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
5. ALL CORE ALTERATIONS performed while fuel is '.n the reactor vessel after the initial fuel loading sham be directly supervised by e nher a licensed Senior Reactor Operator or Senior Reactor Oparator Limited to Fuel Handling who has no other concurrent 7esponsibilities during this. operation.
6. A Fire Brigade of 5 members including a Fire Brigade Leader shall be maintained on site at all times. This excludes 3 members of the minimum shift crew necessary for safe shutdown and any personnel required for other essential functions during a fire emergency.
7. The Chief Operating Engineer, Nuclear Watch Engineers, and Nuclear Operations Supervisors shall hold a Senior Reactor l Operator License. The Nuclear Plaut Operators shall hold a Reactor Operator License.

6.3 UNIT STAFF OUALIFICATIONS

  • The qualifications with regard to educational and experience backgrounds of the unit staff at the time of appointment to the active position shall meet the requirements as described in the American National Standards ~

[

Institute N18.1-1971 ." Selection and Training of Personnel for Nuclear .

Power Plants." In addition, the individual performing the functior. of

, Radiation Protection Manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September, 1975. ,

6.4 TRAINING A retraining and, replacement training program for the unit staff shall be l maintained under the direction of the Nuclear Training Department Manager. The training programs for the licensed personnel shall meet or-exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of.10CFR Part 55. The training programs for the Fire Brigade shall meet or-exceed the requirements of NFPA Standard No. 27-1975 " Private Fire Brigade". Fire Protection Training sessions will be held quarterly, i

Revision Amendment No. 41, 46, 69, 88, 122, 125 209 l

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. ... ~ . - . - - . . - - - _ . - _ - . . . . - - _ - . _ . . - - _ _ _ _ . - -

. i

.l EILGDIM NUCLEAR PuHER STATION 1

MINIMUM OPERATING SHIFT CREW COMPOSITION TECHNICAL SPECIFICATION TABLE 6.2-1 l 1

STATION . CREN (a). MINIMUM NUMBER ON DUTY t

CONDITION OPERATING- Licensed Senior Reactor Operator- 2 (b); $

, 1 Licensed Reactor Operator 2 '- -

t Unlicensed Operator 2 . j

, Shift, Technical Advisor ;1 - ,i COLD SHUTIK4Cl Licensed Senior _ Reactor. Operator 1 ano Licensed Reactor Operator -1 i

REFUELING Unlicensed 0Arator 1 Shift Technical Advisor ~ None' Required Notes
.

(a) Higher grade licensed operators may take the place of: lower grade licensed or unlicensed-personnel. ,

(b) A Shift Technical Advisor (STA):with a-Senior-Reactor Operator license may simultaneously serve as'STA and SRO. }

4 h

4 l

1 Revision i Amendment ! ,. 80 :2iO- .l

- * , _ _ . _-- 6 . ,.. _ ._ , , , _ , , _ _ , _ . , . . _ _ , . , . , , , _ , . _ , . .

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. , ae 6.5 REVIEW AND AUDIT

  • A. QPJRATIONS REVIEW COMMITTEE (ORC)'
l. MCTT'M The ORC shall function to: advise the Station Director on all-matters related to: safety.

, 2. COMPOSITION l.

The ORC lshall be composed of a Chairman, and at least six  !

members', who shall be appoi'ded in writing by the Station-

- Director- from senior' experienced onsite= individuals, at th.e -  :

manager level.or_ equivalent, representing each of the following i disciplines: plant operations, plant maintenance, plant

. ' technical, reactor engineering, radiation: protection, and chemistry. .

t

3. ALTERNATES Alternates ' hall be appointed-in writing by the Station Directorf L!

to serve em a temporary basis. ,

4.

MEETING FRE00ENCY ,

The ORC shallimeet at-least once per calendar. month and as convened by the ORC Chairman.-

5. OUORUM AquorumoftheORCshallconsistoftheChairmanor/ designated-
  • altenate and a majority of members / designated alternates;--  ;

however,_no more than two alternates shall-be. allowed to meet quorum requirements.

6. RESPONSIBILITIfi l

The ORC shall be re;oonsible for: i l

a. Review of 1) all procedures' required by: Specification 6.8_ l and changes thereto, 2) any other proposed precedures or.

changes thereto'that-affect nuclear, safety.- 1

.b. Review all proposed teste, and experiments:that affect.

nuclear safety.

c; Review of all proposed changes to the Technical Speci ficatier,s . '

d. Review of all' proposed changes or modifications to plant systems:or equipment that affect, nuclear _ safety.

i l

Revisica - I Amendment No.. 46, 69, 88, 122-211- 'l .

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.6.5.A.6 RESPONSIBILITIES (Continued).

e. . Review of facility operations to detect potential; safety hazards, f.. Review of the Station Security. Plan and implementing procedures and changes to the plan and procedures..
g. Review of the Emergency Plan and implementing procedures.and-changes to the plan and procedures,
h. Performance of special reviews and investigations and .

reports thereon as re@vsisd by the Nuclear Safety Review and Audit Committee (NSRAC) Chairman,

i. Investigation of all violations of the Technical i

' Specifications and shall prepare and forward a report ,

covering evaluation and recommendations- tc. prevent. recurrence I to the Station Director, the NSRAC Chairman, and the Senior i Vice President - Nuclear.4 i

j. Review the Station Fire Protection. Plan and implementing precedures and-changes-to the plan and procedures.

The ORC Chairman may appoint subcommittees composed of personnel-who are'not members of ORC to perform staff work necessary to the efficient functioning of ORC.

7. AUTHOR.UX
a. Recommend in writing to the Station' Director the approval ~ 1 or disapproval of items considered under 6.5 A.6(a) through (C abovt, e
b. Render determinations in writing with regard _to whether or not each item considered under 6.5.A.6(a)'through (d) above constitutes an unreviewe6 safety questiom "

i

c. Provide written notification within 94 hours0.00109 days <br />0.0261 hours <br />1.554233e-4 weeks <br />3.5767e-5 months <br /> to the-Station Director, the Nuclear Safety Review a.,d' Audit Committee, l o

-and the Senior Vice President - Nuclear of d L greement '

between the ORC Hembers and the ORC Chairman. The Station

~ Director shall have responsibility for resolution of.such.

disagreements.

8. RECORDS Tho ORC shall maintain written minutes of.. each r.setint and. copies >

shall be forwarded to the Station Dt 'ctor and the'NSRAC Chairman. j Revision: 4 Amendment No. 29, 46, 69, 88, 122 212 J.

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6.5.8. -NUCLEAR SAFETY REVIEW AND AUDIT COMITTEE (NSRAC)

1. f.1LNCTION

.I The NSRAC shall function'to provide independent, review and audit of I designated activities in the areas of:

1.. nuclear power plant operations;.  !

2. _ nuclear engineering;- l
3. chemistry and radiochemistry; i
4. metallurgy; I
5. instrumentation and control ' l
6. radiological safety; l
7. mechanical and electrical engineering;
8. quality assurance practices l
9. fire protection j
2. COMPOSITION j 1

The NSRAC Chairman and other. members shall be. appointed by the Senior o' Vice President - Nuclear.

The membership shall cellectively possess'a broad' based level of. i experience and. competence enabling the Committee to review and audit .1 those activities designated in 6.5.B.I.above and to recognize when_it j is necessary to'obtain technical-advice and counsel. The collective competence of the. Committee will be maintained as changes to the membership are made. The membership shall consist of a minimum of five persons of whom no more= than a minority are members of the plant i staff.- '

3. ' ALTERNATES Alternate members shall be appointed in writing by-the Senior Vice-President - Nuclear or the' Chairman to serve on a temporary basis.
4. CONSULTANTS ,

Consultants shall be utilized as determined byethe NSRAC Chairman to provide expert advice to the NSRAC.

]

5. MEETING FREOU SC1 ,

t The NSRAC shall meet at'least once per six months.

a

6. 000 RUM

{

A quorum of the NSRAC shall consist of the Chairman or his designated. d alternate and at least four NSRAC members-including:a'ternates. The Vice Chairman is the designated alternate.to the Chairman. .No.more than a minority of the quorum shall have line responsibility for- '

operation of the facility. No more than'two alternates;shall participate in a quorum at any_one time.- '

Revision 213

-Amendment No.

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6'.5.B' f(Continued)

7. REVIEW ,

The P.SPE shall; review:' ,

r The written safety evaluations for:.

a.

(1) _ changes in the. facility as described in the Final Safety l Analysis Report; h

._ (2) changes in-the procedures described in' Chapter 13 of the Final-Safety Analysis Report; t (3) test and' experiments not described in the Final Safety:

L. Analysis. Report to verify-thtc scch cl1anges, tests or experiments did not involve  ;

a change in the Technical Specifications'or an unreviewed safety question . as - defi ned . I n - 10CFR50.59(a)(2) .-

j

b. Proposed changes to. procedures, equipment or systems involve i an unreviewed safety question as defined in Section 50.o9,10 CFR. t
c. Proposed tests or e.iperiments which involve:an unreviewed safety' question as cofined in .Section 50.59, '10 CFR.- r
d. Proposed changes in Technica1'Specificationslor operating license,
e. Violations of applicable-statutes, codes, regulations - orders, , ,

Technical Specifications, license requirecents :or of internal- '

procedures or instructions.having nuci ar safety significance,

f. Significant -operating abnormalities: or deviations- from normal- and expected performance of plant equipment ~that effect< nuclear safety : (
g. All events which are-required by 10 CFR 50.73 to be reported:to  :

l the NRC in writing.  ;

i

h. Any other matter involving safe 1 operation of the nuclear plant- 4 which NSRAC deems appropr_ tate'for consideration.or which is-referred to NSRAC forithe onsite operating. organization.or'by L other functional organizational units within Boston Edison.

[* 1. Reports and meeting minutes of'the Operations Review Committee..

8. AUDITS Audits of facility activities shall be performed under the' cognizance '

of the NSRAC. These audits shall encompass: -i

a. The conformance of facility operation to provisions contained )

within the Technical Specifications and applicable license j, conditions at least once per year.

I

b. The training and qualifications of the entire unit staff at least l
.once per year.

Revision 214

. Amendment No. l b

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e .

r

/6.5.B.8 8U011S (Continued)-

c. ;The results of all actions required by deficiencies occurring in

. facility equipment, structures, systems or method of operation that affect nuclear safety at.least once per six months.-

-d. The performance of all activities required by the Quality Assurance Program to meet the criteria of Appendix "B".- 10 CFR 50, at least'once per two years.

e. The' Emergency Plan and implementing procedures ~at least once per two years.
f. The Station Security Plan and implementing procedures at.least once per two years..
g. Any other area of-facility operation considered appropr_iate by'the NSRAC or the-Senior-Vice President - Nuclear.
h. The Fire Protection Program and . implementing procedures at least once per two years. 1
9. AUTHORITY ,

I The NSRAC shall report to and advise the Senior Vice President - j Nuclear on those areas of responsibility.specified in Section 05.B.7 and 6.5.B.8. #

in. RECORDS  !

Records of NSRAC activities s' hall be prepared . approved and-  !

distributed as indicated below:

a. Minutes of each NSRAC meeting shall,be prepared, approved and;

-forrarded to the Senior Vice President --Nuclear, NSRAC members, and others the Chairman may designate.  !

t

b. Reports of reviews encompassed by-Section 6.5.B.7.e, f g and h -l above, shall-be prepared, approved and forwarded to:the. Senior:

Vice President - Nuclear, with a copy.to.the Station Director L

within 21 days following the completion of the review.=

c. Audit reports encompassed by-Section 6.5.B.E above shall be forwarded to the Senior.Vice President:- Nuclear and to'the management positions responsible for-the areas-audited within.30 days after completion of the audit.

6.6 REPORTABLE EVENT ACTION

'The following actions shall be taken for each reportable event:

A. The Commission shall be notified and/or a report submitted pursuant tc  !

the requirements of either.10 CFR'50.72 or 10 CFR 50;73.-

-l 3

B. Each Reportable Event Report submitted to the Commission shall-be reviewed by the ORC and submitted to the NSRAC Chairman and the' l

Station Director. '

Revision

' Amendment No. 46, 69; 74, 88, 104, J22 215 a

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.. . f 6.7 SAFETY LIMIT VIOLATION The following actions: shall be taken in the event a Safety Limit is violated:

A. The provisions of 10 CFR 50.36(c) (1)-(1) (A) shall be complied with - l /

immediately.

B .' The Safety Limit Violation shall be reported to the Commission within-  !

I hour per 10CrR50.36(c)(6).and 50.72, and to the Station Director and the NSRAC Chairman-immediately.

C. A Safety Limit-Violation Report shall be prepared. The report shall- I be reviewed by the ORC. This report shall describe (1) applicable-circumstances preceding the violation (2) effects of.the violation I upon facility components, systems:or structures, and (3) corrective action taken to prevent recurrence.

D. The Safety Limit Violation' Report shall be submitted to the-Commission ,.

within 30 days in accordance with 10CFR50.36(c)(7) and 50.73 and_ to I the NSRAC Ch.ltman and the StationLDirector. i 6.8 PROCEDURES A. Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and -

recommendations of Sections 5.1 and 5.3 of ANSI N18.7 - 1972 and Appendix "A" of USNRC Regulatory Guide 1.33, except as provided in  !

6.8.B and 6.8.C below.

B. Each procedure of 6.8.A above, and changes thereto, shall be reviewed  !

by the GRC and approved by'the responsible department manager prior to i implementation. These procedures shall be reviewed periodically as  ;

set forth in administrative procedures.

RQIE: ORC review and approval of procedures for vendors / contractors,-

who have a QA Program approved by Boston' Edison Company.-is not-required for work performed at the vendor / contractor facility, i

C. Temporary changes to procedures of 6.8.A above may be made provided:

1. The intent of th9 original procedure is not altered.
2. The change is. @ proved-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

3. .The' change is documented, subsequently reviewed by the ORC within 14 days of implementation, and approved by the-responsible L  ;

department manager. I l

D. Written procedures-to im?' ment the Fire Protection Program shall be established, implementeo and m atained- .

i Revison Amendment No. 29, 30, 46, 74, 88, 122 216 y

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.6.9 REPORTING REOUIREMENTS

- In addition to the applicable reporting requirements of Title 10, Code-of Federal Regulations, the following identified reports shall be submitted to the Comission.

A. Routine Reports 1 Startuo Renort. A summary 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 l the nuclear, thermal, or hydraulic performance of the plant. The >

report shall' address each'of the tests identified-in the FSAR and shall in general 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 i 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.

Startup reports shall be submitted within (1) 90 days following.

completion of the startup test program, (2) 90 days following resumption or comencement of commercial 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 commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed. >

2. Monthlv Ooeratino Report. Routine reports.o'f operating statistics, shutdown experience and^ forced reductions-in power shall be submitted on a monthly basis to the Comission to arrive no later than.the 15th 1 of each month'following the calendar month covered by the report. .

The Monthly Operating Report shall' include a narrative sumary of operating experience that describes the operation of.the facility, including :afety-related maintenance, for the_ monthly report period.-

3. Occuoational Exoosure Tabulation. A tabulation 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,.e.g.. reactor operations and surveillance inservice inspection, routine l maintenance, special maintenance (including a description), waste i processing, and-refuelina shall be submitted on an annual basis. l This tabulation supplements the requirements.of 20.407 of 10.CFR 20 The. dose assignment to various duty functions _may be estimates 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% of the tota'.

whole body dose received from external sources shall be assigned to I

specific major work functions.

I l B. (Deleted by Amendment No. 38)

Revision 217 Amendment No.

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6.9.C. .Uniaue Renortina Reauirements i

. l.. Semi-Annual Radioactive Effluent Release Report

a. Routine 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 ar.d July 1 of-' ,

each year. The report should be in accordance-with Appendix B of Regulatory Guidesl.21-(Revision 1) dated June, 197A. A' supplemental report containing dose assessments for the previous-year shall be' submitted annually within b + after January 1.

b. Any changes to the Offsite Dose Calculation Manual (ODCM) shall-  !

be submitted to the Commission in the Semi-Annual Radioactive 1 Effluent Release Report. l

2. - Annual Radioloaical EnvironmentaLHonitorina Renort  !

A report on the radiological environmental surveillance program for the previous calendar year of opention shall be-submitted to the i Commission prior to May 1 of the year. The reports-shall include I summaries, interpretations, and statistical evaluation of the results of the radiological environmental survd11ance activities for the report period, operational controls and. previous environmental  !

surveillance reports, and an assessment of the observed impacts of the plant operation on the environmenb The reports shall also ,

include the results of any land use surveys which affect the choice  !

of sample locations. If_ harmful effects or evidence of irreversible damage are detected by the monitoring,'.the licensee-shall provide an- 1 analysis of the problem and a proposed course of. action-to alleviate ,

the problem. i The Annual Radiological Environmental Monitoring Report shall include a sunnary of the results of analysis of all radiological environmental samples and of all environmental radiatian measurements  !

taken during the period pursuant to the locations specified in the I table and figures in the Offsite Dose Calculation Manual-~(ODCM) as-  !

well as summarized and_ tabulated results of these analyses and measurements in the format of the table in the Radiological i Assessment Branch Technical Position, Revision 1, November 1979.

In the event that some results are not available prior to May.1-of the year, the report shall be: submitted, noting and: explaining the 9asons for the missing results. The missing data shallLbe submitted 3, soon as possible in a supplementary report.

The report shall also include the following: a summary description of the radiojogical environmental monitoring-program; at least two legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of the reactor:

discussion of all deviations from the sampling schedule of Table 8.1-1; and discussion of-all analyses in which the lower limits of detection (LLD) required by Table 8.1-4 were not achievable.

1 One map shall cover stations near the site boundary;'a second shall include the more distant stations.

Revision Amendment No. 23, E7, 89, 703, 776 218 l

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6.9.C Uniaue Reoortina Reauirements (Continued) . i

' 3. Smecial~Reoorts

.Special reports shall be submitted as indicated in Table 6.9.l. .

-6.10 RECORD 2 RETENTION A. The following records shall be retained for at least five years: .

1. Records of facility' operation covering time' interval at each  !"

power level.

I

2. Records of principal maintenance activities. inspections,  ;

-repair and replacement of principal items of equipment related 1 to nuclear safety. q

3. Reportable Event Reports, j
4. Records of surveillance activities, inspections 'and cali.' rations required by these' Technical Specifications.
5. Records of reactor tests and experiments.

1

6.  : Records of changes made to Operating Procedures.  !
7. Records of radioactive shipments. . j i
8. Records of sealed source leak tests and results.

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9. Records of annual physical inventory of all source material of record.

B. The following records shall be retained for the duration of the

. Operating 1.icense:

1. Record and drawing. changes reflecting facility design modifications made to systems ~ and equipment described in the,

-Final Safety Analysis Report.

2. Records of new and irradiated fuel inventory. fuel transfers and assembly burnup histories..  :.
3. Records of faci _lity radiation and contamination' surveys.;
4. Records of radiation exposure for all individuals entering ,

radiation control areas. .

1

5. Records of the service lives of all hydraulic and mechanical snubbers listed in PNPS procedures including the date at which - l the service life commences and associated installation and maintenance records. +

Revision Amendmeiit No. 30, 60, 88, 92 - 219-t 1

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TABLE 6.9.1 I Arag Reference Submittal Date- l

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a.- Secondary Containment 4.7.C.I.c Upon completion of.  !

Leak Rate Testing (1) each test (2) i b .'- (Deleted)

c. (Deleted)
d. (Deleted)
e. - Standby Liquid Control 3.4.C.3 Fourteen days after solution enrichment out receipt of a non-of specification , complying enrichment report-or. lack of- -.

receipt of-such a l.

report within the '

required thirty days, if enrichment-compliance cannot be .

achieved within seven- l days.  :

i NOTES: 1. Each integrated leak rate test of the secondary containment j shall be the subject of a summary technical report. This report 1 shall include data on the wind speed, wind direction, outside i and inside tem 9eratures during the test, concurrent reactor building pressure, and emergency ventilation flow rate. The report shall also include analyses and interpretations.of those data which demonstrate compliance with the specified leak rate-limits.  !

2. The report shall be submitted-approximately 90 days after-completion of each test. Test periods shall be based on the commercial. service date as the starting point. ,

a Revision

- Amendment No. 702, II3 220-

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6.10.B RECORD RETENTION (Continued)

6. Records of gaseous and liquid radioactive material released'to the environs. -
7. Records of transient or operational cycles for those facility components designed for;a limited number of transients or cycles. "
8. Records of training and qualification for current members _of the i plant staff.
9. Records of in-service inspections pericrmed pursuant to these Technical Specifications.  ;
10. Records of Quality Assurance activities required'by the QA' Manual.  ;
11. Records of reviews performed for changes made to procedures or equipment or reviews.of tests and experiments pursuant to ,

10 CFR 50.59.

Records of meetings of the-ORC and the NSRAC.

12.

13. Records for Environmental Qualif1 cation.

6.11. RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be-prepred consistent with the requirements of 10 CFR Part 20 and s kl3 be ,

approved, maintained and adhered to for all operations involving '

u personnel radiation exposure.

6.12 (Deleted)

! 6.13 HIGH RADIATION AREA (OPTIONAL) 6.13.1 In lieu of the " control device" or " alarm signal" required by: .

paragraph 20.203(c)(2)' of 10 CFR 20, each high' radiation-area in which the intensity of radiation is greater than -.100 mrem /hr but _less than.

1000 mrem /hr shall be barricaded-and conspicuously. posted as a high radiation area and entrance thereto- shall' be controlled _ by requiring issuance of a Radiation.Hork Permit *. Any individual or group of  ;

individuals permitted to enter such areas shall be1provided with or-accompanied by one or more of the following:

a. A radiation monitoring device which continuously' indicates the-radiatio.i dose rate in the area. l l

Health Physics personnel or personnel: escorted by Health Physics--personnel shall be exempt from the RHP issuance requirements during _ the performance of this assigned radiation protection duties, provided they comply with. approved ~

radiation protection procedures for entry into high radiation areas.

Revision

(. Amendment No. 30, 45, 65, 122 221 h

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.v. .

6.13.1 HIGH RADIATION AREA-(Continuedt

, b. -A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry;into such areas with this.

monitoring device may be made after the dose rate level in the area has'been established and personnel have b.en made knowledgeable of them.

c. -An individual _ qualified in-radiation protection procedures who is equipped with.a radiation dose n te monitoring device. This-individual.shall be' responsible for providing positive control; over-the' activities within the area and shall perfv a periodic radiation surveillance at the frequency specified M_the Radiation Protection Manager in'the Radiation Work Permit.-

6.13.2 The requirements.of 6.13.1, above, shall~ also apply to each high realation area in which-the intensity of. radiation is greater than.

1 X)0 mrem /hr.. -In addition, locked doors shall-be provided to prevent unauthoH zed entry into such areas and the keys shall be maintained unC9r the administrative control of-the Nuclear Hatch Engineer on-4 ty and/or the Radiation Protection Manager.

6.14 FIRE PROTECTION PROGRAM The following inspectiors and audits shall bt performed:

1. An independent fare protection inspection and audit;shall be-

. performed annually utilizing either qualified off-site licensee' personnel or an outside fire protection firm.-

2. An inspection and audit by an outside qualified fire consultant shall be performed at intervals no-greater than 3 years.

(The next page is 229)

Revision Amendment No.. 30, 45, 122 '222 a

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-l ATTACHMENT C i

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. Pace No.

4.0 ' MISCELLANEOUS RADIOACTIVE MATERIALS' SOURCES 206k-

- 4.1 Sealed-Source Contamination 206k

4.2 Surveillance Requirements 206k .

4.3 Reports 2061 4.4 Records Retention 2061 5.0- MAJOR DESIGN FEATURES 206m 5.1 Site Features 206m 5.2 Reactor 206m l 5.3 Reactor Vessel 206m  ;

5.4 Containment 206m  ;

5.5 Fuel Storage- 207  !

5.6 Seismic Design 207 i'

6.0 ADMINISTRATIVE CONTROLS 208 6.1 Responsibility 208 6.2 anization Mg zoy c 6.3 @ staff Qualifications j 6.4 T ng j 6.5 Review ~and~ Audit .2.11 6.6 Reportable Event Action a.15 r  ;

6.7 Safety Limit Violation 214 k  ;

6.8 Procedures L I G- .

6.9 Reporting Requirements _ e i g. - /

.. 6.10 Record Retention ciq  !

6.11 Radiation Protection Program 2zl 6.12 (Deleted) 6.13 High Radiation Area 27l 6.14 Fire Protection Program 227

, Ooorational Chieclives ' Surveillance I 7.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 8.0 229-  !

l 7.1 Monitoring Program 8.1 229 i

7.2 Dose - Liquids 8.2 232~ i 7.3 Dose - Noble Gases 8.3 233 l- 7.4 Dose - Iodine-131.-Iodine-133, 8.4 234 i Radioactive Material in Particulate Form, and Tritium 7.5 Total Dose 8. 5, .- 234 -  !

)

i Revision Amendment o.35,45,88,89,95,h iii

6.0 ADMINISTRATIVE CONTROLS 6.1- RESPONSIBILITY g

"- The Station Director shall. be accountable for overall facility- '

operation. In his absence. the Station Director shall designate..in -!

-writing, the individual to assume this responsibility.

6.2 ORGANIZATION l A. OFFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizat.Ons-shall be established for unit operation and corporate mana ement, respectively. 'The onsite and

//

offsite organizations shall. nelude the positions for activities affecting the safety of the nuclear power plant. / '/

/

l

1. Lines of authority, responsibility, and communicatio shall: be /

established and defined for_the highest management 1 _

als through intermediate' levels.to and including all operating 1 organization positions. - These relationships'shall be L documented and updated, as appropriate, in the-form of 1 p/

organization charts, functional. descriptions of departmental responsibilities and relationships, and job descriptions for-l '

key personnel positions, or in equivalent forms of t/

documentation. . These requirements shall be documented in [L Pilgrim. Station' Final Safety Analysis Report.

2. The Station Director shall.be responsible for overall! unit saf operation and shall- have control over those onsite activities-necessary for safe operation and maintenance of the plant.

/ #

3. The Senior Vice Prasident - Nuclear shall'have corporate - '

responsibility for overall plant nuclearLsafety and'shall take /

any measures needed to ensure acceptable performance of the /. -

staff in operating.. maintaining, and providing te:hnical j support to the plant to ensure nuclear safety. ,

4. The individuals'who train the operating staff and those who- i

. carry out health physics'and quality assurance functions may /' )

report to the appropriate onsite manager; however,.they shall' '

havs sufficient _ organizational freedom to ensure their- /

/

independence from operating pressures, j

1. Each on duty shift shall be composed of at least the minimum shift crew composition-shown in Table 6.2-1. .!

I l

Revisionh f Amendment No. 69,80,88',722.h 208

6.0 ADMINISTRATIVE CONTROLS

~2.. . When the unit is in an operational mode other than cola: q shutdown or refueling, a person holding a hnior Reactor.  !

. Operator License shall .be present in the contiol- room at all .

times. In addition to this Senior Operator, a Licensed ..

1 Operator or Senior Operator shall be present at the controis- -

when fuel is in the vessel. <

3. .At least two Licensed Operators shall be present in the control-  ?

room dure.i; reactor startup, scheduled reactor shutdown and l during recov .i from reactor trips ~-.

4. . An 1.1 divi @l cuaMfled in-radiation protect 1_on procedures.

~

shall be on site when~ fuel is in the reactor. t

5. ALL CORE ALTERATIONS performed while fuel is in the reactor. e vessel supervisedafter-the initial-fuel by either loading;shall
a. licensed Senior Reactor be.directly'or Operator s

-Senior Reactor Operator Limited to Fuel Handling.who f has noi  :

other concurrent ' responsi bili ties during : thi s > operation.

6. A Fire Brigade of 5 members including a Fire Brigade Leader ,

shall t.e maintained on site at all times. This' excludes 3-members of.the minimum shift crew necessary for safe shutdown-and any personnel required for other essential functions.during a fire emergency,

7. The ni Chief Operating: Engineer,- ' s S c iti n Nuc ar Match n ineer uclear Operations Supervisors; shall hold a Sen or Reactor Operator License. The-Nuclear

/ /' 7 Plant Reactor Operators shall hold a Reactor.0perator: License. /

6.3 FAC[LITYMTAStOUALIFICtION$ -M hd M ,

The qu' ions with regard 4to educational and experience backgrounds.

y of the shall fneet staff at the time of appointment to the active position; requirements as described in the American National-

Stanaards Institute N18.1-1971, " Selection and' Training of Personnel for.

Nuclear Power Plants." InLaddition, the individual performing the function of Radiation Protection Manager shall.neet or exceed tne qualifications of Regulatory Guide 1.8, September,:1975. ,

L l

~

6.4 TRAINING g A retraining and replacement trainin program for:the staff '

shall be maintained'under the direct on of!the Nuclear raining; q ji Department Manager. The training programs lfor the licensed personnel ,

P shall meet or exceed the requirements;and. recommendations of Section 5.5 'l F of. ANSI N18.1-1971 and Appendix A of 10CFR Part 55. The trsining.-

S programs for the Fire Brigade shall meet or exceed the requirements of

NFPA Standard No. 27-1975 " Private Fire Brigade". Fire Protection: ~ .
Training. sessions will be Eneld quarterly. .

[

',  :{

a i Revision : 2 09)'.

F Amendment o. 47, 46, 69, 88, 122,

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PILGRIM NUCLEAR POWER STATION' MINIMUM OPERATING SHIFT CREW COMPOSITION t

TECHNICAL SPECIFICATION TABLE 6.2-1 l l

.f L CREW (a) n4INIMUM NUMBER ON DUTY  ;

STATION'

, CONDITION OPERATING Licensed' Senior Reactor' Operator 2 (b. l

. Licensed Reactor Operator- 2' i Unlicensed Operator- 2 i

j. Shift Technical Advisor -1 .

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COLD SHUTDOWN Licensed Senior. Reactor; Operator. -1 i

and- Licensed Reactor Operator 1

, REFUELING Unlicensed Operator 'l l -: Shift Technical Advisor.. None Required' .

t

-[

I Notes:

(a). Higher grade' licensed operators may' take
the place"of lower 1 grade licensed or unlicensed personnel..

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(b) A' Shift Technical Advisor-(STA) with a. Senior ~ Reactor Operator j

1 i license may simultaneously serve;as STA and SRO. j

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6.5 REVIEW AND AUDIT A . .. OPERATIONS REVIEW COMITTEE (ORC) o.

1. FUNCTION The ORC shall. function to advise the Station ~ Director on all matters related to safety.- #

1

2. COMPOSITION , .l T ORC shall be composed ofke/e((nicilfectio(Wnegef/wh /

[

l a as M fChairman) and aT sonst six memoir .

e appoint ~ d in eriting by the Station Director from senior '

experienced onsite ind< viduals, at the manager level or.-

equivalent, representing each of the:following disciplines: /'[' t plant operations, plant: maintenance, plant technical ~ r:setorc,

[ t engineering, radiation protection, and chemistry.

3. ALTERNATES

}

Alternates shall be appointed in writing by the' Station Director f to serve on a temporary buis.  %">

4. MEETING FREOUENCY The ORC shall' meet at.least once per calendar month and as convened by the ORC Chairman.- '
5. 000 RUM A quorum of the ORC shall_ consist of the Chairman or designated alternate and a majority of members / designated alternates; ,

however, no more than=two alternates shall be allowed to meet

, quorum requirements.-

L 6. RESPONSIBILITIES The ORC shall be responsible fer: *

=i

a. Review of 1) all procedures required'by Specification 6.8 ' I and changes'thereto, 2) any other proposed procedures or.

L changes thereto that affect' nuclear safety.

L- b. Review all proposed tests and experiments that affect l u nuclear safet,y.

o H

c. Review of all proposed changes-to the Technical-Specifications.

d.. Review of all proposed changes or modifications to plant ~ ,

syste:ns or equipment that: affect nuclear safety. 'I A / l '- f Revision Amendment o.46,69,88,h n

E_ - _ _ _ _ . _ _ _ . _ _ _ . . . . . _ . iJi _ . . _ .

6.5.A.6,_ RESPONSIBILITIES (ContinuedF N e., Review of facility operations to detect potential safety-hazards.;

f. Review of the Station Security Plan and implementing -

procedures and_ changes to the plan and procedures, g.. Review of the Emergency Plan and implementing procedures and 1 changes to the plan and procedures.- ,

s

h. Performance of special reviews and-investigations and .

reports: thereon as requested by the Nuclear Safety Review- '

,i and Audit Committee (NSRAC) Chairman. i

1. Investigation of all violations of the Technical' a Specifications and shall prepare and forward a report d covering evaluation and recommendations to prevent recurrence- 1

-to thetStation Director, the NSRAC Chairman, and the Senior l Vice President . Nuclear.- '

j. Review the Station Fire Protection Flan'and implementing ,

procedures =and. changes to the plan and procedures.

The ORC Chairman may appoint' subcommittees composed of personnel  ;

who are not members of ORC to perform staff work necessary to '

the efficient functioning of ORC.-

7. AUTHORITY
a. Recommend in writing to the-Station. Director the approval // 3 or disapproval of items considered under 6.5.A.6(a) .

through'(d) above.

I b.

Render determinations in writing'wif'.. regard to whether or- '

not each item considered under 6.5.A.6(a):through-(d) above:

i constitutes an unreviewed' safety question' .

q

c. Provide -

written notification the Station Director, the Nuclear Safety Review and Audit Committee, /

and the Senior Vice President - Nuclear of disagreement; _ ;

between the ORC Members and the ORC Chairman! :Thei$tation  :

Director shall have responsibility for, resolution of such.- /  :

disagreements.

L

8. RECORDS

/

The ORC shall maintain written minutes of-each meeting and copies shall be forwarded to the Station Director and the.NSRAC Chairman.. /

4

?.12,  !

'~ Revision ".

i

Amendment o. 29, 46,_69, 88, 1 /d 1

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l^ ; , l B

J g,B. NUCLEAR SAFETY REVIEW AND AUDIT COMMITTEE (NSRAC)

1. FUNCTION The NSRAC shall. function to p ovide' independent review and audit of-designated activities in_the areas of: j
l. nuclear power plant operations;

.2.- nuclear engineering; d 3L chemistry _and radiochem!stry; '

4. metallurgy;
5. --instrumentation and control;,
6. radiological- safety;-
7. mechanical _and' electrical: engineering;

.8. quality assurance' practices

9. fire protertion
2. COMPOSITION The NSRAC Chairman and other members shall;be-appointed by the Senior'

_ f  ;

Vice President - Nuclear, j

lThe membership shall' collectively possess a-broad based level of j 1' experience and competence enabling the Committee to review and audit '

those activities designated in 6.5.B.1 above and to recognize ~when it' f is necessary to obtain technical advice-and counsel.- The collective 1/

,l competence of the Committee will be maintained-as changes to-the I membership are made. The membership shall consist of a minimum of five persons of whom no more than-a minority are members-of the plant /

staff. 7

3. ALTERNATES Alter # 4 members shall be appointed in writing by the Senior.Vice- , _

Preslov t - Nuclear or the Chairman'to serve on a temporary basis, y

4. CONSULTANTS Consultants shall-be utilized as determined by'the-NSRAC Chairman to  !

provide. expert advice to the NSRAC. ,

5. MEETING FREQUENCY The NSRAC shall meet at least once per six months. -3
6. 000 RUM A quorum of.the NSRAC shalliconsist of the Chairman or his designated- .

alternate and at-least four NSRAC members including alternates. 'The 7 '

Vice Chairman is the designated alternate'to the Chairman. No more /

than a minority of the quorum shall have line responsibility for-. //

operation of the facility. No more:than two alternates shall participate in a quorum at any one time.

2/3 i Revision /

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_ _ . _ _ . _ _ _ ~ . _ ___ _ _ _ _ _ ._

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.' ' %ls,B (Cawd)

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7, REVIEW The NSRAC shal.1 review:

a. The written safety evaluations for:  ;

(1)- changes in the facility as. described in the Final Safety i Analysis Report;-

-(2) changes in the procedures described in Chapter 13 of the Final. Safety Analysis. Report;  !

(3) test and experiments not described-in the final Safety [ /-

Analysis Report toverifythatsuchchanges,testsorexperimentsdidnotinvobe, I[

a change in-the Technical Specifications or an unreviewed safety L L Equestion as defined in: 10CFR50.59(a)(2),

b. Proposed changes to procedures,' equipment'or systems which involve an unreviewed stfety question as defined-In.Section 50.59, 10 CFR,
c. Proposed tests.or experiments which involve an unreviewed safety-question as defined in Section 50.59, 10 CFR.
d. Proposed changes in Technical Specifications or operating license.
e. Violations of applicable statutes, codes, regulations,' orders, Technical Specifications, license. requirements,.or-of-internal. ,

procedures or instructions having nuclear safety significance.

i. f. Significant erating abnormalities or deviations from normal'and -

expected pert mance of plant equipment:that effectl nuclear safety.

g. All events which are required by 10 CFR 50.73 to be reported to the NRC in writing.
h. Any other matter involving safe operation of theLnuclear plant which NSRAC. deems appropriate for consideration or:which ls referred to NSRAC for the onsite operating organization or by.

l; other functional organizattonal. units;within' Boston, Edison.

1. Reports and meeting minutes of the Operations Review Committee.
8. AUDITS-Audits of facility activities shall be performed under-the cogni.'ance of the NSRAC. These audits shall encompass: I
a. The conformance of facility operation to provisions contained within the Technical Specifications;and applicable-license-conditions at least once per year. g
b. The training and qualifications of t'he entire taff at' least once per year.

2/Y Revisionh j G+MA u--

6.5.8.8l AUDITS 1 Continued)~

c. The results of.all actions required by deficiencies occurring in.

. - facility equipment, structures,' systems or method of operation

.o ,that affect nuclear safety at least-once per six months.

d. The performance of all activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50,-  ;

i at least once per two years.  ;

e. The Emergency .in and implementing procedures at lea t once per two years.

i i

f. The Station Security Plan and implementing procedcres at ; east-once per two years,
g. Any other area of facility operation considered appropriate by the~

NSRAC or the Senior Vice. President - Nuclear.

h. The Fire Protection Program and implementing procedures at_least once per two years.

l.

j. 9. AUTHORIIY {

i

The NSRAC shall report to and advise the Senior Vice~ President -- .

L Nuclear on those areas of responsibility specified in.Section 6.5.B.7

l. and 6.5.B.8.
10. RECORDS i

Records of NSRAC activities'shall be prepared, approved and distributed as indicated below:

F

[ a. Minutes of each_NSRAC meeting shell be prepared, approved and. L forwarded to the Senior Vice President . Nuclear, NSRAC members, end others the Chairman may designate. 1 1

'- b. Reports of reviews encompassed by Section 6.5.B.7;e, f, g and h -1 above, shall be prepared, approved and forwarded to the Senior /

Vice President - Nuclear, with-a copy to the Station Director- /

j within 21 days following the completion of the review.

! c. Audit reports encompassed by Section 6.5.8.8 above shall be L forwarded to the Senior Vice President - Nuclear and to the

! management positions responsible for the areas audited within 30

. days after completion of the: audit.  !

L ,

f 6.6 REPORTABLE EVENT ACTION .l

[ The following actions shall be taken for each reportable event:

i l

1 I A. The Commission shall be notified and/or a report submitted pursuant to j the requirements of either 10 CFR 50.72 or 10 CFR 50.73.
B. Each Reportable Event Report submitted to the Commission shall be i reviewed by the ORC and submitted to the NSRAC Chairman and the Station l Director. gfy I
Revision @

! Amendment Io. 46, 69, 74, 88, 764, f

i' I '

.__._..-_.-....-..~..,..-..-,.,.-_...,:l

  • y 4 ,- . ,

- 6.7 1AFETY LIMIT VIOLATION q The following actions shall be taken in the event a Safety Limit is '1

, .... violated:

'A. The provisions of 10 CFR.50.36(c) (1). (1) shall be complied with immediately,

8. The Safety Limit Violation shall be reported to the Commission within  !

I hour per 10CFR50.36(c)(6) and 50.72, and to the Station Director 1 and the NSRAC Chairman immediately.

C. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the ORC. This report shall describe (1) applicable; +

circumstances preceding the violation (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to preveni: recurrence.

D. The' Safety Limit Violation Report shall be submitted to the Commission within 30 days in accordance witt,100FR50.36(c)(7) and 50.73 and to ,

the NSRAC Chairman and the Station Director.

6.8 PROCEDURES- f A. Written procedures and admin'istrative policies shall' be established, '

l

. implemented and maintained that meet or exceed the requirements and l- recommendations of. Sections 5.1 and 5.3 of ANSI N18.7 - 1972 and Appendix "A" of USNRC Regulatory Guide 1.33, except as' provided in'  :

6.8.8 and 6.8.C below.

~

B. Each procedure of 6.8.A above, and changes thereto, shall.be reviewed b by the ORC and approved by the responsible department manager prior to 3 implementation. These procedures shall be reviewed periodically.as set forth in administrative procedures.

HQII: ORC. review and-approval of procedures for vendors / contractors, l.

who have a QA Program approved by Boston Edison Company, is not required for work performed.at the' vendor / contractor. facility.

C. Temporary changes to procedures of.6.8.A above'may be made provided:

1, . The intent of the original procedure is not altered.

2. The change is approved by two members of. the plant managerent 1 staff, at least one of whom holds a Senior Reactor 0peratc 's ,

license on the unit affected.

3. he change is documented, subsequently reviewed by the ORC within'  !

/,y' days of implementation, and approved by-the responsible j opartment manager.

O. Written procedures to implement the tire Protection Program shall be ~ ,

l established, implemented and. maintained. ,

- - Revison 2l(o3 i

x Amendmen o. 29, 30, 46, 74, 88,  ;

f

.W L. '6.9 REPORTING REQUIREMENTS l

-In addition to the; applicable reporting requirements of Title 10. Code of.

xw e Federal Regulations, the following identified reports shall be submitted -

to the Commtssion.- 1 A. Routine Reports-

1. 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 11c7nse 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 l the nuclear, thermal, or hydraulic performance of the plant. .The i report shall address each'of the. tests identified in the FSAR and' shall in general include a description of the measured values of,the operating conditions.or characteristics obtained during the test '

program and a comparison of these values wtth design predictions'and specifications. Any corrective-actions that were required to obtain ,

l satisfactory operation shall also be described. Any additional L specific dotatis required in license conditions based on other

commitpcats shall be inclu d in this report, l

Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3). 9 months following. initial criticality, whichever is earitest. If:the '

Startup Report does not cover all three events ~(i.e., initial criticality, completion of startup test pro 1 commencement of commercial power operation) ,

gram, andreports' supplementary resumption or shall be submitted at least every three months untti all three events have been completed.

2. Monthly Operatino Report.' Routine reports of operating statistics, shutdown experience-and forced reductions in power shall be submitted ,

on a monthly Msis to the Commission to arrive no later than the 15th of each month following the calendar month covered.by the report.

The Monthly Operating Report shall include a narrative summary of ,

operating experience that describes the operation of the-facility, ,

including safety-related maintenance, for the monthly. report period.

3. Occunational Exposure Tabulation. A tabulation of the number of stat'on, utility and other personnel (including contractors) receiving exposures greater than 100 aren/yr and their associated man-rem exposure according to work and job functions,-e.g. reactor operations and' surveillance inservice. inspection, routine.

maintenance, special maintenance (including a description).-waste ,

processing,-and refueling shall be' submitted on~an' annual basis. -

This tabulation supplements the~ requirements of 20.407 of 10 CFR 20. l The_ dose assignment to various duty. functions may be estimates based-on pocket dostmeter, TLD, or flim badge measurements. Small exposures totalling less than 20% of the indiv.1 dual totalt dose need. i not be accounted for. In the aggregate, at least 801 of tho' total l

whole body dose received from external' sources shall be assigned to 1 specific major work functions. ]

0 O Stds W 6-s a%dr2o,68) EIT Revisionh

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. . s < a. $- -i 6!9.C. . Uniaue Reoortina Renuirements ,

_ . .) . Semi-Annual Radioactive ' Effluent Releas'eL Recort .

a. Routine radioactive effluent release reports covering the operation of_the unit:during the previous 6 months of operation i.
shall be submitted within 60 days after: January 1 and July 1 of- f each year. The report should be in accordance with Appendix B / .

of Regulatory Guide 1.21-(Revision 1) dated June.1974. : A

/

/ -

supplemental report containing dose assessments for the previous  ;

year shall be submitted annually within 90 days after January 1.

b. Any changes to.the Offsite Dose Calculation' Manual (ODCM)'shall be submitted to the Commission in the Semi-Annual Radioactive L Effluent Release Report. j
2. Annual Radioloaical Environmental Monitorina Report-  !

A report on the radiological environmental surveillance program for the previous calendar year of operation shall be submitted to the ,

Comission prior to May 1 of the year. The reports shall include sumaries, interpretations, and statistical evaluation of the results 4 of the radiological environmental surveillance activitiesifor the ,

, report period, operational; controls and previous environmental--

surveillance reports, and an assessment'of the observed impacts of-the plant operation on the environment. The reports,shall also include the results of any land use surveys which affect the choice of sample locations. If harmful; effects or evidence of. irreversible 4

damage are detected by the monitoring, the licensee-shall provide an i-analysis of the problem and:a proposed course of action to alleviate the problem.

L The Annual Radiological Environmental Monitoring Report shall include a sumary of the results of analysis of a11' radiological

environmental samples and of all environmental radiation measurements 2

taken1during; the period. pursuant to~ the locations specified in the

. table and' figures in the.0ffsite Dose Calculation' Manual- (00CM) as-4 well as sumarized and tabulated results' ofJ these analyses-and .

i measurements in the format of the table:in the Radiological Assessment Branch Technical Position, Revision .1, November 1979.

l In the event that some results'are not available prior to May'.1 of

~

! the-year, the report shall be submitted, noting and explaining the

! reasons for the. missing results. The'aissing data shall-be: submitted F as soon as possible in a; supplementary report. t

The report shall also!includeIthe following: a summary description of the radio ogical environmental monitoring program;.at-least two' ,

L legible maps covering all sampling. locations keyed.to a table.giving

i. . distances and ' directions:from the centerline of the reactor; j discussion of all deviations from the: sampling schedule of' Table 1 .

8.1-1; and discussion of all- analyses;in:which-the lower' limits of l

detection (LLD) required by Table 8.1 4 were not achievable.

i One map shall cover stations near the site boundary; a second shall' '

include the.more distant stations.

i " Revision 2/8 Amendment . 23, 57, 89, 763,

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.3. Specia11 Reports Special reports shall be submitted as indicated in' Table 6.9.1.  !

I 6.10 RECORD RETENTION A. The following records shall be retained for at least five years:

- I l- l

1. Records of factitty operation covering time interval ~at each i power' level.

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! 2. Records of principal' maintenance activities, inspections, repair' and replacement of principal items of equipment related to nuclear safety.,

3. Reportable Event Reports. f
4. Records of surveillance-activ'itles,' inspections and calibrations required by these Technical, Specifications.

- 5. Records of reactor-tests and experiments, i

6. Records of-changes made to Operating Procedures. l
7. Records of radioactive shipments.

Records of sealed source leak tests and~results.

8.

9. Records of annual physical inventory of all source material of l-TeCord. i B. The following records shall be retained for the duration of the' =i Operating License:
1. Record and drawing changes reflecting facilityL. design - ,

f modifications made to systems and equipment described in'the 3 Final Safety Analysis. Report.  !

2. ' Records of new and irradiated fuel-Inventory, fuel transfers and' l assembly burnup hlstories.
3. Records of facility radiation and contamination' surveys.
4. ' Records of radiation exposure for all-individuals entering L radiation-control areas.'.

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5. Records of the service: lives of all hydraulic and mechanical '

snubbers listed in PNPS procedures including the'date at which' the service'llfe commences and. associated installation and' i- maintenance records.

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Amendment No. 39, $@, 88, 2/9 i

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.- e o r s i TABLE 6.9.1 gylg Reference Submittal Date

a. Secondary Cor,tainment 4.7.C.l.c Upon completion of Leak Rate Testing (1)- each test (2)  ;
b. (Deleted)
c. (Deleted) (Delefed) j / ec 4 r o ur l'
e. Standby Liquid Control 3.4.C.3 Fourteen days after solution enrichment out receipt of a non-of specification complying enrichment report or lack of ,

receipt of such a '

report within the required thirty days,  !

if enrichment compliance cannot be achieved within seven days.

NOTES: 1. Each integrated leak rate test of the secondary containment

, shall be the subject of a summary technical report. This report shall include data on the wind speed, wind direction, outside and inside temperatures during the test, concurrent reactor building pressure, and emergency ventilation flow rate. The report shall also include analyses and interpretations of those data which demonstrate compliance with the specified leak rate limits.

2. The report shall be submitted approximately 90 days after /

completion of each test. Test periods shall be based on the commercial service date as the starting point.

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    • 6.10.B RECORD RETENTION (Continued) '

6.- Records ~of gaseous,and liquid radioactive ~ material. released to- f

, - the environs. '

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7. Records of-transient or operational cycles for..t'osen facility components designed for a limited number of transients or cycles.- / 1
8. Records of training and qualification for current members of the-- I plant staff.

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9. Records of U -service inspections performed pursuant to these L locnnical Specifications. .
10. Records of Quality Assurance activities required by the QA Manual. /
11. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant-to i 10 CFR 50.59.- 7[, 1

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12. Records of meetings of the ORC and the NSRAC.

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13. 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 i personnel radiation exposure. ,

6.12 (Deleted) 6.13 HIGH RADIATION AREA'(OPTIONAL) 6.13.1 In lieu of.the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area -in which .

the intensity vf radiation is: greater than 100 mrom/hr but less than '

1000 arem/hr 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 *. 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 dost rate in:the area..

  • Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RHP issuance requirements during the performance of this i assigned radiation protection duties,-provided they comply with approved radiation protection procedures for entry into high radiation areas. 4 22/

'Revisionh

' Amendment No. 30, 45, 95,

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6.13.1 HIGH RADIATION AREA'(Continued)

.b. A radiation monitoring device which continuously integrates the

-- radiat'.on dose rate in the area and alarms when a preset i' integrated dose is r$ceived. Entry into such areas with this.

monitoring device may be made after the dose rate. level in the )

area has been established and personnel have been made  ;

knowledgeable of them. j

c. An individual qualified in radiation protection procedures who is q equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control d over the activities within the area and shall perform periodic ,

radiation surveillance at the frequency specified by thei n  !

Radiation Protection Manager in the Radiation Work Permit. g i 6.13.2 The requirements of 6.13.1,'above, shall also apply to each high '!

radiation atea in which the_ intensity of-radiation is greater than 1000 mres/hr. . In addition, locked doors shall be provided to prevent--

unauthorized entry into such areas and the keys.shall be maintained under the administrative control of.the Nuclear. Match Engineer on /

duty and/or the Radiation Protection Manager. / ,

6.14 f1RE PROTECTION PROGRAM i The following inspections and audits shall.be performed:

1. An independent fire protection inspection and audit shall be i performed annually utilizing either qualified off-site licensee personnel or an outside fire protection firm.
2. An inspection and audit by an outside qualified fire consultant shall'  ;

be performed at intervals no greater than 3 years. .j I

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Amendmen 36, 45, 4

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