ML20099F088

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Proposed Tech Specs Revising Sections 6.1 Through 6.8 & Figures 6.2.1 & 6.2.2 Re Organizational Responsibilities
ML20099F088
Person / Time
Site: Pilgrim
Issue date: 11/09/1984
From:
BOSTON EDISON CO.
To:
Shared Package
ML20099F082 List:
References
NUDOCS 8411260253
Download: ML20099F088 (17)
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Text

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' Attachment A Proposed Technical Spectfication Changes

-NOTE: Because of a prior license amendment request involving _the deletion of Licensee Event Report requirements (Ref. Gen. Ltr.

83-43, 12/19/83),;it will be noted, when reviewing the following submittal, that :ertain paragraphs of Section 6 incorporate the -

previously-requested changes. This was done at the' request of the NRC'.s Pilgrim Station Project Manager, Mr. Paul Leech.and to simpilfy the review of this submittal.

Proposed Change:

Reference ~is made-to Pi! grim Nuclear Power Station, Techaical Specifications Sections 6.1 thru 6.8 and, Figures 6.2.1 and 6.~2.2. The following changes are

. requested to be ":ade:

1) -Section 6.1, pg. 208.

Change: "The Station Manager shall be' accountable.for overall facility operation. In his absence the Statton Manager shall designate in writing the individual to a'ssume this responsibility."

To: "The Nuclear Operations Manager shall be accountable for overall facility operation. In his absence the Nuclear Operations Manager shall designate in writing the individual to as;ume this responsibility".

2) Section 6.5.A.1, pg. 212 Change: The ORC shall function to advise the Station Manager on all matters related to safety". -

To: "The ORC shall function to provide timely and continuing review of all aspects of plant operation and to advise the Nuclear Operations Mahager on all matters related to nuclear safety".

3) Section 6.5.A.2, pg. 212 Change the entire Section 2 entitled " Composition".

Change: 2. COMPOSITION The ORC shall be composed of the Chairman: Station Manager Member: Chief Operating Engineer Member: Chief Technical Engineer Member: Chief Maintenance Engineer Member: Chief Radiological Engineer Member: Onsite Safety & Performance Group Leader

! The ORC Chaire.an may appoint subcommittees composed of personnel who are not members of ORC to perform staff work necessary to the efficient functioning cc ORC.

8411260253 841109 PDR ADOCK 05000293 P ppy

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2.-COMPOSITION I

The ORC shalI be composed of the:

Chairman: Technical Section Head, or designated alternate Members: Chief Operating Engineer, or designated alternate Chief Maintenance Engineer, or designated alternate Chief Technical Engineer, or designated alternate Chief Radiological-Engineer, or designated alternate

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Chief Chemical Enoineer, cr designated alternate Onsite Safety and Performance Group Leader, or designated alternate

4) Section 6.5.A.3, pg. 212 Change: " Alternate' members shall be appointed in writing by the ORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate in an ORC quorum at any one time". .

To: " Alternates shall be appointed in writing by the Nuclear Operations Manager to serve on a temporary basis".

5) Section 6.5.A.5,-pg. 212 Change: "A auorum of the ORC shall consist of the Chairman and a majority of members including alternates".

To: "A quorum of the ORC shall consist of (ne Chairman or designated alternate and a majority of members / designated alternates; however, no more than two alternates shall be allowed to meet quorum requirements".

6) Section 6.5.A.6, pg. 212 Change: "e. Investigation of all violations of the Technical Spec-ifications................to the Vice President -

Nuclear Operations and to the NSRAC Chairman".

[ To: "j. Investigation of all violations of the Technical l Specifications and shall prepare and forward a report

!- covering evaluation and recommendations to prevent i recurrence to the Nuclear Operations Manager and to the l hSRAC Chairman."

i Note: A re-arrangement of the list of responsibilities will be necessary due to the above changes.

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(Section 6.5.A.6 continued on page 213)

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Change: " l '. Provide'imme64te written notification to the Vice President - Nuclear Operations ............... and the ORC Chairman. The Vice President - Nuclear Operations shall have responsibility-for resolution for such disagreements."

To: "1. Provide immediate written notification to the Nuclear Operations Manager and the Nuclear Safety Review and

? Audit Committee, of disagreement between the ORC Members andithe ORC Chairman. The Nuclear Operations Manager

' shall have responsibility for resolution for such disagreement.

Add as a new paragraph:

The ORC Chairman may appoi.nt subcommittees composed of personnel who are not-members of ORC to perform staff .ork necessary to i the efficient functioning of ORC.

7) Section 6.5.A.7, pg. 213 Change: "7. Authority it:a ORC .shall report to and advise _ the Station Manager on those areas of responsibility specified in Section 6.5.A.6."

To: "7. Authority

a. The ORC shall act as advisor to the Nuclear Operations Manager (NOM) on all matters related to nuclear safety and recommend proposals considered under Sections 6.5.A.6(a) through (h) above for NOM approval.
b. The ORC may reject proposals submitted pursuant to Sections 6.5.A.6(a) through (h) above which do not satisfy the Committee's concerns."
8) Mction 6.5. A.8, pg. 213

! Change: "8. RECORDS The ORC shall maintain written minutes of each meeting and copies shall be provided to the Vice President -

Nuclear Operations."

, To: "8. RECORDS The ORC shall maintain written Minutes of each meeting and copies shall be forwarded to the Nuclear Operations Manager and the Nuclear Safety Review and Audit Committee Chairman."

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9) 'Section 6.5.B.10, pg. 216 Change: "b. Reports of reviews ..............., with a copy to the -

Station Manager within 21 days following the completion of the review."

g7 n To: "b. Reports of reviews ..............., Dith a copy to the Nuclear Operations _ Manager within 21 days following the "

completion _of the review.-

'-- 10) Section 6.6, pg. 216

, Change: "B. Each Reportable Event Report ... and the Station Manager."

To: "B. Each~ Reportable Event Report ... and'the Nuclear Operations Manager."

11) Section 6.7, pg. 216-

-Change: "B. 'The Safety Limit Violation shall be reported to the

' Commission within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per_10CFR50.36(c)(6) and 50.72,

'and'to the Station Manager and the NSRAC Chairman immediately.

To: "B. The Safety Limit Violation ..............., and to the-Nuclear Operations Manager and the NSRAC Chairman immediately."

Change: "D. The Safety Limit Violation Report shall be submitted to the Commission within 30 days in accordance with 10CFR50.35(c)(7) and 50.73 and to the N3RAC Chairman and the Station Manager.

To: "D. The Safety Limit Violation Report shall be sdbmitted to the Commission..............., the NSRAC Chairman and the Nuclear Operations Manager.

12) Sectior 6.8, pg. 216 Change: "B. Each procedure of 6.8.A above, and changes thereto, shall be reviewed by the ORC and approved by the Station Manager prior to implementatio7 "

To: "B. Each procedure of 6.8.A above, and changes thereto, shall be reviewed by the ORC and approved by the Nuclear Operations Manager prior to implementation."

13) Section 6.8.C, pg. 217 Change: "3. The change is documented, reviewed subsequently by the ORC,
and approved by the ORC Chairman within 7 days of implementation."

To: "3. The change is documented, subsequently reviewed by the ORC within 7 days of implementation, and approved by the Nuclear Operations Manager."

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. . f O Reason i for Change L

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Organization: changes,' referred to in BECo Letter-No. 83-307-(Reference 1),

,T have been approved,4thereby necessitating revisions to the PNPS-Administrative Technical. Specifications. These. changes transfer the Tecnnical Section, which reported:to the corporate on-site' representative (Director of Operations:

Review) to a position reporting:to the Nuclear.0perations Manager. A new-w -position..of Technical- Section Head has been formed to oversee this group which

' willJnow consist of the:On-site Safety and Performance Group and the Technical '

Group. This'new position.will.also assume the-responsibillty_as Chairman of. >

the Operations Review Connittee.

Also within this, reorganization,'a separate water chemistry group has been formed to provide the dedicated manpower;cnd associated resources to improve .

our Chemistry-Control Program. 'The water-chemistry control group will-be

- cheaded by a new position,; Chief-Chemical Engineer, and will report directly'to.

the Nuclear Operations Manager. This new position'also will be a member of.

-the. ORC.

r ;With this reorganizatica,= BECo has endevored to increase'the effectiveness of organizational. lines of responsibility and available human resources.

Safety Considerations The proposed changes revise most parts of Section 6 and Figures-6.2.1 and 6.2.2 of the-Administrative. Technical. Specifications for Pilgrim Nuciper Power

, Station. The changes are all administrative in nature and have no safety significance, do not physically affect plant safety related syste;ns,. and do not reduce any safety margin. Therefore, the changes do not present an unreviewed safety question as defined in 10CFR50.5Ac).

The changes have been reviewed and approved by the Operations Review Committee and reviewed by the Nuclear Safety Review and Audit Committee.

I Safety Hazards Considerations The Comission has provided guidance concerning the application of the i

standards by providing certain examples (48FR14870). One of these examples

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(1), involving no significant hazards consideration is "a purely

- administrative change to Technical Specifications." The requested amendment matches this example. .

' Schedule of Change This proposed amendment will be put into effect upon receipt by the NRC.

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. +.. . . 2 cire v: - .Pages affected by this proposed change l-areias follows:.

. 208 J 208a

' 209-

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  • : 212' 213 '

LF 214-215*

- 216

: 217:

218*~

  • These'.pages have o'nly been renumbered, there-are no changes to theitext.~

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. Attachment 8'

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6.0 ADMINISTRATIVE CONTROLS

6.1 : RESPONSIBILITY "The N'uclear Operations Manager shall be accountable for overall facility.

operation. ~In his absence the Nuclear Operations Manager shall' designate in writing the individual to assume:this responsibility.

- 6.2~: ORGANIZATION A. ~0FFSITE-y' The Company-organization for' station managemeret and technical sup-por_t shall be as shown on Figure 6.2.1.

B. FACILITY- >

The racility organization shall be as shown on Figure 6.2.2 and:

1 Each on duty shift'shall be composed of at least the minimum

~- snift crew-composition shown in Table 6.2.1.

2. When the unit is.in an operational mcde'other than' cold shutdown or refueling, a person holding a 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 in the reactor vessel after the initial fuel loading shall be directly super-vised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities 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.

C. CHANGES TO THE ORGANIZATION Changes may be made to the organization without prior license amendment provided that a revision to Section 6.2 is included in a subsequent license amendment request.

Amendment No. 208 c_, ,w . . . - , - - . i-*y , -,em--- ,- - - - - , . ,--- - . - - - - ,-,..---.---..y--- .-, -r - ,,m--- ,.

E =6.3 FACILITY STAFF QUALIFICATIONS

.The; qualifications with. regard to~ educational.and experience b'ackgrounds

'of.L.the. facility staff at the time of appointment to the active position ashall- meet'the requirements as described in the American National Stan-dards Institute N18.1-1971, " Selection and Training of Personnel for 2 Nuclear Power Plants." . In addition, the individual performing the func-

tion of-Radiation Protection Manager _shall meet or exceed the quall-fications of Regulatory Guide 1.8,- September,1975.

6.4 : TRAINING A.retra'ining and. replacement training program for the facility-staff shall be maintained under the direction of the Training Manager. ~

The.  !

training programs for the licensed personnel shall meet lor 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-shal1~ meet or exceed the requirements of NFPA' Standard No. 27-1975

" Private Fire Brigade". Fire Protection Training sessions will be held quarterly, f-t a

T Amendment No. 208a

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a Chief Executive Officer _

Sr. Vice President Nuclear Nuclear Safety Review _ ' _ '

and Audit Comittee 7

.1-1.

Vice P--sident Vice-President  ; l .-

Nuclear Engineering and Nuclear Operations Quality Assurance 1

1- i Quality Assurance Nuclear Engineering Nuclear Management Nu lear Trainin9 Nuclear Operations Nuclear Operations I-Manager Manager Services Department Department Support Department Department (Off-site) (Of f-site) (Off-site) (Of f-site) (On-site) (On-site) l 1-Operations Flant Staff Review ,_,_

(On-site) Comittee (On-site)-

Boston Edison Company -

Organization for Operation of; Pilgrim I .

Figure 6.2.1

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, :d a sq NUCLEAR OPERATIONS MANAGER s

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J TECHNICAL SECTION HEAD (ORC CHAIRMAN}

(SRO)

CHIEF CHIEF CHIEF CHIEF CHIEF ON-SITE SAFET1 OPERATIONS IlAINTENANCE RADIOLOGICAL CHEMICAL TECHNICAL & PERFORMANCE ENGINEER ENGINEER ENGINEER ENGINEER ENGINEER GROUP LEADER (SRO) (ORC) (ORC) (ORC) (ORC) (ORC) (ORC) l NUCLEAR TECHNICAL TECHNICAL TECHNICAL TECHNICAL TECHNICAL WATCH STAFF STAFF STAFF- STAFF STAFF ENGINEERS

  • Mechanical
  • Radiation
  • Chemical *0n-Site-
  • Electrical Protection Engineering Technical
  • Instrument
  • Reactor Advisors and Control Engineering
  • Perfonnance Engineering NUCLEAR OPERATING '

SUPERVIS0RS (SRO)

Code: ORC - Member of OPC.

R0 - NRC Reactor Operator License SR0 '- NRC Senior Reactor Operator License .

NUCLEAR Pilgrim Station Organization TORS (RO) hgure 6.2.'2-

- 210 .

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6.5 ' REVIEW AND AUDIT-

~A. OPERATIONS REVIEW COMMITTEE (ORC)

1. FUNCTION The ORC shall function to provide timely and continuing review of all aspects of plant operation and to advise the Nuclear Operat-lons Manager on_all matters related to nuclear safety.
2. COMPOSITION ,

The ORC shall_be composed'of the:

Chairman: Technical Section Head, or-designated alternate Members: Chief Operating Engineer, or designated alternate Chief Maintenance Engineer, or designated alternate Chief Technical Engineer, or designatec alternate Chief Radiological Engineer, or desingated alternate Chief Chemical Engineer, or

-designated altornate Onsite Safety and Performance Group Leader, or designated alternate

3. ALTERNATES Alternates shall be appointed in writing by the Nuclear Operations Manager-to serve on a temporary basis.
4. MEETING FREQUENCY The ORC shall meet at least once per calendar month and as convaned by the ORC Chairman.
5. QUORUM 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 snall be allowed to meet quorum requirements.
6. RESPONSIBILITIES The ORC shall be responsible for;
a. Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto that affect nuclear safety.

Amendment No. 212 :

c ' 6. .

RESPONSIBILITIES (Conti.')

Review all proposed tests and experiments that affect.

b.

. nuclear-safety.~ -

4c. Review of all proposed changes =to the Technical

-Spectfications.

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d. Review of all proposed changes.or modifications-to plant systems ~or equipment that affect nuclear: safety.
e. . Review of facility' operations to detect potential safety

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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. Review the Station Fire-Protection Plan and implementing procedures and-changes to.the plan and procedures.
1. Performance of special reviews and _ investigations and reports thereon as requestea-by the NSRAC Chairman.
j. Investigation of all violations of the Technical Specifica-tions and shall prepare-and forward a report covering evaluation and recommendations to prevent recurrence to the Nuclear Operations Manager and-to the NSRAC Chairman.
k. Render determinations in writing with regard to whether or not each-item considered under 6.5.A.5(a).through (e) above constitutes an unreviewed safety question.
1. Provide immediate_ written notification to the Nuclear Opera-tions Manager and the Nuclear Safety Review and Audit Committee, of disagreement between the ORC Members and the ORC Chairman. The Nuclear Operations Manager shall have responsibility for resolution for such-disagreements.

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. The ORC shall act as advisor to the Nuclear Operations Manager (NOM) on all matters related to nuclear safety and recommend proposals considered under Sections 6.5.A.6(a) through (h) above for NOM approval.

b ~. The ORC may reject proposals submitted pursuant to Sections 6.5.A.6(a) through (h) abow which do not satisfy the Committee's concerns.

-Amendment No. 213 i-I

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8. - RECORDS:

-The ORC shall maintain wr1tteniMinutes of each meeting and copies-

-l- shall be. forwarded to the Nuclear Operations Manager and the Nuclear Safety Review and Audit Committee Chairman.

B. NUCLEAR SAFETY REVIEW AND AUDIT COMMITTEE (NSRAC)

1. FUNCTION ,

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'The.NSRACshall-functiontoprovideindependentre[leCndauditof

' designated activities in the areas of: *

l. nuclear power plant _ operations; -,
2. ' nuclear engineering; s r"
3. chemistry and radiochemistry; -
4. metallurgy; -
5. Instrumentation and cortrol; ..,,
6. radiological safety; . .
7. mechanical and electrical engineering; ,.
8. quality assurance practices ' '

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9. fire protection. -
2. COMPOSITION , ,

TheNSRACChairman'andothermembersshallbeappointedbytheSenior's Vice President - Nuclear, or such other person as he shall ,

designate. NSRAC irembers shall. collectively possess' experience and competence required to review and audit the designated areas noted in 6.5.B.1.

The collective competence of the c.ommittee will be maintaine'd as changes to the membership are made. The membership shall consist of a minimum of five persons.

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3. ALTERNATES ,

Alternate members shall be appointed in wr11-ing by the Senior Vice President - Nuclear or the chairman to serve on a temporary basis; >

however, no more than two alternates shall participate in a quorum at any one time. -

4. CONSULTANTS Consultants shall be utilized.as determined by the NSRAC Chairman to provide expert advice to the NSRAC. -

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5. MEETING FREQUENCY N The NSRAC shall meet at least once per six months.

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6. OUORUM A quorum of the NSRAC shall consist of th'e Chairman and a majority of the.NSRAC members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility.

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Amendment No. 214

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'7. REVIEW c :The NSRAC sha'll review:

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a. :Thecsafety evaluations lfor:

(1) Changes to procedures, equipment or systems and.

(2) Tests or experiments completed under the provision of Section-50.59, 10 CFR to verify that such actions did not constitute an unreviewed safety question.

b. -Proposed changes to procedures, equipment or systems which in-volve an unreviewed safety 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.

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 the NRC in writing.
h. Any other matter involving safe operation of the nuclear plant which NSRAC deems appropriate for consideration or which is referred to NSRAC for the onsite operating organization or by 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 cogni-t zance of the NSRAC. These audits shall encompass:
a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per year.
b. The training and qualifications of the entire facility staff at least once per year.

Amendment-No. 215

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

- -facility equipment structures, syste s or method of operation -

that affect nuclear safety at least once per six months.

ud.< The performance 4of all activities required by the Quality As-surance 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 P'lan and implementing procedures at-least once,per two years.
g. Any other area of facility operation constdered appropriate by the NSRAC or the Senior Vice President - Nuclear.
h. .The Fire' Protection. Program and implementing procedures at least once.per two years.
9. AUTHORITY The NSRAC shall report to and advise the Senior Vice President -

Nuclear on those areas of responsibility spcified in Section 6.5.B.7 and 6.5.8.8.

10. RECORDS Records of NSRAC activities shall be prepared, approved and distri-buted as indicated below:
a. Minutes of each NSRAC meeting shall be prepared, approved and forwarded to the Senior Vice President - Nuclear, NSRAC mem-bers, ano others the Chairman may designate, within 14 days following each meeting.
b. Reports of reviews encompassed by Section 6.5.B.7 e, f, g and h above, shall be prepared, approved and forwarded to the Senior Vice President - Nuclev , with a copy to the Nuclear Operations Manager within 21 days following the completion of the review.
c. Audit reports encompassed by Section 6.5.8.8 above shall,be forwarded to the Senior Vice President - Nuclear and to the management posittor.s responsible for the areas audited within 30

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days after completion of the audit.

l 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 j to the requirements of either 10 CFR 50.72 or 10 CFR 50.73.

l B. Each Reportable Event Report submitted to the Commission shall be review.d by the ORC and submitted to the NSRAC Chairman and the Nuclear Operations Manager. l l

I  ; Amendment No. 216 i

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' !6;7: SAFETY LIMIT: VIOLATION;

' The following actions shall'bi taken in the event a= Safety. Limit il

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violated:

4 g , L A. The provisions of 10 CFR -50.36(c) (1) '(1) shall _be complied'.with

-immediately.

. B. :The Safety-Limit Violation shall be reported _to the Commission within-1 ' hour per 10CFR50.36(c)(6) and 50.-72, . and - to:the Nuclear Operations A Manager and_the NSRAC. Chairman immediately.

lC. 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

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action taken to prevent recurrence.

D. _The Safety Limit Violation Report shall be submitted to.the Commission within S0. days in accordance with_10CFR50.36(c)(7) and 50.73 and to the NSRAC Chairman and the Nuclear Operations Manager. l 6 3 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 l'.33, except'as provided in

-6.8.B and 6.8.C below.

- i! . Each procedure of 6.8.A above ;and changes thereto, shall be reviewed l

.by the ORCand approved by the Nuclear Operations Manager prior to implementation. These procedures shall be reviewed periodically as set forth in administrative procedures.

NOTE: ORC review and ipproval 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.

- 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' management staff, at least one of whom holds a Senior Reactor Operator's license on the unit affected.
3. The change is documented, subsequently reviewed by the ORC within 7 days of implementation, and approved by the Nuclear Operations Manager.

D. . Written procedures to implement the Fire Protection Program shall be established,. implemented and maintained.

Amendment No. 217 1

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.6.9 REPORTING REQUIREMENTS In addition to the' applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified: reports ~shall be submitted

'o the Director of'the appropriate Regional Offics of Inspection and.

.Enforceme6t unless.otherwise noted.

Routine Reports

1. Startup Report. A summary report.of plant startup and pcwe*

escalation testing shall.be submitted following (1) receipt of an

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.opccating license,:(2) amendment'to the license ~1nvolving a. planned increase in power level, (3) installation of fuel that has a different design or has bem manufacturered,by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performant.e of the plant. The report shall address each of the tests-identified in the FSAR and shall in general. Include a cescription of-the. measured values of the

operating conditions or characteristics obtained during the test program and a comparison of these. values with design predictions and specifications. Any corrective actions that were required to obtain sati; factory operation shall also be described. Any additional specific details. required in license conditions based on other-commitrents shall be included in this report.

Startup reports shall be submitted within-(l) 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 earliest. If the Startup Report does rot 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. Monthly Operating Report. Routine reports of operating statis- tics, shutdown experience and forced reductions in power shall be submitted on a monthly basis to Director, Office of Inspec- tion and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, 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, i including safety-related maintenance, for the monthly report period.

3. Occupational Exposui e Tabulation. A tabulation of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their asso- clated man-rem exposure according to work and job functions, e.g. reactor operations and surveillance inservice inspection, routine maintenance, special maintenance (including a descrip- tion), 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 func- tions may be estimates

! based on pocket dosimeter, TLD, or film badge rtasurements. Small

! exposures totalling less than 20% of the individual total dose need l not be accounted for. In the aggregrate, at least 80% of the total whole body dose received from external sources shall be assioned to

! specific major work functions.

Amendment No. 218 i

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