ML20114A563

Amends 113,116,131 & 135 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,changing Types of Procedures Requiring Review by Onsite Review & Investigative Function

ML20114A563
Person / Time
Site:	Dresden, Quad Cities
Issue date:	07/24/1992
From:	Barrett R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20114A566	List: ML20114A563 ML20114A569
References
NUDOCS 9208120081
Download: ML20114A563 (79)

Text

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UNITED STATES o

.i NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20566

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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.116 License No. DPR-19 1.

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

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated May 7,1992, as supplemented July 1,1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and F

regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confor:nity with the application, the provisions of the Act and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technica'i Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-19 is hereby amended to read as follows:

9200120001 920724 PDR ADOCK 05000237 P

PDR

• (2)

Technical Soecificaticns The Technical Specifications contained in Appendix A, as revised through Amendment No. 116, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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ed Ric r.

arrett, Director Projec Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Attachment:

< Changes to the Technical

,.Speci fications Date of Issuance:

July 24, 1992 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 116

-FACILITY OPERATING LICENSE _NO. DPR-19 DOCKET NO. 50-237 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT vi vi-1 1.0-6 1.0-6 6-1 6-1 6-2 6 - 2..

t.

6-3 6-3 6-5 6-5 6-6 6-6 6-7 617 6-8 6-8 6-9 6-9 6-10 6-10 G-11 6-11 6-12 6-12 6-13 6-13 6-14 6-14 6-15 6-15 6-16 6-16 --

DRESDEN II DPR-19 Amendment No. 116 (Table of Contents, Cont'd.)

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4.9 Auxiliary Electrical Systems 3/4.9 - 1 4.9.A Station Batteries 3/4.9 - 1 4.9.B (N/A) 4.9.C Diesel Fuel 3/4.9 - 5 4.9.D Diesel Generator Operability 3/4.9 - 5 4.10 Refueling 3/4.10- 1 4.10.A Refueling Interlocks 3/4.10- 1 4.10.8 Core Monitoring 3/4.10- 1 4.10.C Fuel Storage Pool Water Level 3/4.10- 2 4.10.0 Control Rod Drive and Control Rod Drive Maintenance 3/4.10- 3 4.10.E Extended Core Mainteaance 3/4.10- 4 4.10.F Spent Fuel Cask Handling 3/4.10- 5 4.10.G Fuel Storage Reactivity Limit 3/4.10- 8 l

4.11 High Energy Piping Integrity 3/4.11-1 4.12 Fire Protection Systems -

Sections 4.12.A through 4.12.H -

f Deleted per Generic letters 86-10 and 88-12 (Amendment 106) i.0 Design Features 5-1 5.1 Site 5-1 5.2 Reactor 5-1 5.3 Reactor Vessel 5-1 5.4 Containment 5-1

5. 5 Fuel Storage 5-1 5.6 Seismic Design 5-2 6.0 Administrative Controls 6-1 6.1 Organization, Review, Investigation and Audit 6-1 6.2 Procedures and Programs 6-13 6.3 Action to be Taken in the Event of a REPORTABLE EVENT in Plant Operation 6-15 6.4 Action to be taken in the Event a Safety Limit is Exceeded 6-15 ti. 5 Plant Operating Records 6-15 6.6 Reporting Requirements 6-17 Envi'onmental Qualification 6-22 6.7 r

6.8 Offsite Dose Calculation Manual (ODCM) 6-24 6.9 Process Control Program (PCP) 6-25 6.10 Maior Changes to Radioactive Waste Treatment

$ystems (Liquid, Gaseous, Solid) 6-25 4

vi

DRESDEN II DPR-19 Amendment No. 116 1.0 Definitions (Continued)

HH.

Process Contt.,1 Program (PCP) - Contains the sampling, analysis, and formulation determination by which solidification of radlo-active wastes from liqu!d systems is assured.

II. Offsite Dosa Caiculation Manual (ODCM) - Contains the methodology

[

and parameters used in the calculation c.f offsite doses due to radioactive gaseous and liouid effluents, and in the calculation of gaseous and liquid effluent monitor alarm / trip setpoints.

JJ.

Channel Functional Test (Radiation Monitor) - Shall be the-injection of a simulated si0nal into the channel as close to the sensor as practicable to verify operability including alarm

~

and/or trip functions.

t KK.

Source Check - The qualitative assessment of instrument response when the sensor is exposed to a radioactive source.

LL.

Member (s) of the Public _ Shall include all persons who are not occupationally associated with the plant.

This category does not g

include employees of the utility, its contractors, or vendors.

Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

HM, Rated Recirculation Pump Speed - is the recirculation pump speed i

that corresponds to rated core flow (98 x 106 lb/hr) when operat-ing at rated thermal power (dual loop operation).

NN.

Dual Loop Operation - reactor powe'r operation with both recirculation pumps running, f

00.

Single Loop Operation (SLO) - reactor power operation with one i

recirculation pump running.

PP.

Transient Linear Heat Generation Rate (TLHGR) - The transient linear heat generation rate limit protects against fuel center-line melting and 1% plastic cladding strain during transient conditions throughout the life of the fuel.

QQ.

Fuel Design Limiting Ratio for Centerline Melt (FDLRC) - The fuel design limiting ratio for centerline melt is the limit used to assure that the fuel will neither experience centerline melt nor exceed 1% plastic cladding strain for transient over-power events beginning at any power and terminating at 120%

of rated thermal power.

-R R.

Linear Heat Generation Rate (LHGR) - The linear heat generation rate is the operating fuel pin power level.

SS.

Reportable Event - A Reportable Event shall be any of those conditions specified in 10 CFR 50.73.

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DRESDEN 11 DPR-19 Amendment No. 116 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization, Review, Investigation and Audit A.

Onsite and offsite organizations shall be established for the 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 th9 highest management levels through th intermediate levels to and including all operating orgo ization p sitions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of department responsibilities and relationships and jcb descriptior,s for key personnel positions, or in the cqulvalent forms o; documentation.

The requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Secticn 3 Organiza-tional Authority, Activity; Section 6 Interdepartaental Relationships, 2.

The Station Manager shall be responsible for overall unit safe c

operatinn and shall have control over those onsite activities necessuy for safe operation and maintenance of plant.

3.

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

4.

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

B.

Administrative procedures shall be developed'and implemented to limit the working hours of unit staff who perform safety-related functions, e.g., licensed Senior Operators, licensed Operators, health physics personnel, equipment operators, and key maintenance personnel.

The amount of overtime worked by Unit staff members performing safetyicy related functions shall be limited in accordance with the NRC Pol Statement on working hours (Generic Letter No. 82-12).

C.

The shift manning for the station shall be as shown in Table 6.1.1.

The Operating Assistant Superintendent, Operating Engineers,icense.

Shift Engineers, and Shift Foremen shall have a Senior Operating L The Fuel Handling Foreman shall have a limited Senior Operating License.

The Vice President BWR Operations on the corporate level has responsibility for the Fire Protection Program. An Operating

. Engineer at the station will be responsible for implementation of the Fire Protection Program, d

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DRESDEN II DPR-19 l

Amendment No. 116 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

D.

Qualifications of the station managttent and operating staff shall meet minimum acceptable levels as described in ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel," dated March 8, 1971, i

with the exception of the Health Physics Services Supervisor who shall meet or exceed the qualifications of Radiation Protection Manager of Regulatory Guide 1.8, September 1975, and the Shif t Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.

The individual filling the position of Technical Superintendent shall meet the minimum acceptable level for " Technical Manager" as described in 4.2.4 of ANSI N18.1 - 1971.

E.

Retraining and replacement training of Station personnel shall be in accordance with ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel," dated March 8, 1971.

t A training program for the fire brigade shall be maintained i

n under the direction of the Operating Engineer and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1975, except for fire brigade training sessions which shall be held at least quarterly.

F.

Retraining shall be conducted at intervals not exceeding two years.

G.

The Review and Investigative Function and the Audit Function 7

of activities affecting quality during facility operations shall be constituted and have she responsibilities and authorities outlined below:

1.

The Superintendent of the Offsite Review and Investigative Function shall be appointed by the Manager of Quality Assurance /

-Nuclear Safety (QA/NS).

The Corporate Audit Function shall be the responsibility of the Manager of QA/NS and shtil be independent of operations.

The Manager of QA/NS reports directly to the Chief Executive Officer and has the responsibility to set

' Corporate Policy for both the areas of Quality Assurance and-Nuclear Safety.

Policy is promulgated through a central policy committee directed by the Manager of QA/NS.

The Manager of QA/NS has the responsibility for the performance of periodic audits of each nuclear station and corporate department to determine that QA/NS policy is being carried out.

a.

Offsite Review and Investigative Function The Superintendent of the Offsite Review and Investigative Function shall:

(i) provide directions for the review 6-2 i

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c DRESDEN 11 DPR-19 Amendment No. 116 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

and investigative function and appoint a senior participant to provide appropriate direction, (ii) select each participant for this function i) selectacomplementofmorethanonepartIcipantwho collectively possess background and qualifications in the subject matter under review to provide compre-hensive interdisciplinary review coverage under this function, (iv) independently review and approve the findings and recommendations developed by persoiinel performing the review and investigative function, (v) approve and report in a timely manner all findings of noncompliance with NRC requirements and provide recommendations to the Station Manager, Vice President BWR Operations, Manager of QA/NS, General Manager of Quality l

Programs and Assessment, and the Senior Vice President Nuclear Operations.

During periods when the Superintendent of the Offsite Review and Investigative Function is unavail-l able, he shall designate this responsibility to an estab-c lished alternate who satisfies the formal training and experience requirements for the Superintendent of the Offsite Review and Investigative Fun: tion.

I The responsibilities of the personnel performing this function are stated below.

The Offsite Review and l

Investigative Function shall review:

(1) The safety evaluations for 1) changes to procedures, equipment or systems es described in the safety analysis report and 2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute unreviewed safety questions.

Proposed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of QA/NS; l

l (2) Proposed changes.to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59;

[

s (3) Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; l,

(4) Proposed changes in Technical Specifications or this Operating Licent,e;

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DRESDEN II

. DPR-19 Amendment No. 116 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(5) Noncompliance with Codes, regulations, orders, Techni-cal Specifications, license requirements, or of inter-nal procedures or instructions having nuclear safety significance; l

(6) Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function; (7) All REPORTABLE EVENTS; (8) All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems or components; I

(9) All changes to the Generating Stations Emergency Plan prior to implementation of such changes; and (10) All items referred by the Technical Staff Supervisor, Station Manager, Vice President BWR Operations and General Manager of Quality Programs and Assessment.

b.

Station Audit Function i

The Station Audit Function shall be the responsibility of the General Manager of Quality Programs and-Assessment independent of BWR Operations.

Such responsibility is delegated to-the Nuclear Quality Programs Manager.

The Nuclear Quality Programs Manager or designated Corporate Staff or Supervisor approved by General Manager of Quality Programs and Assessment shall approve the audit

-agenda and checklists, the findings and the report of each audit.

Audits shall be performed in accordance with the Company Quality Assurance Program and Procedures.

Audits shall be performed to assure that safety-related functions are covered within the period designated below:

t (1) The Conformance of facility operation to provisions l

contained within the Technical Specifications and 1

applicable license conditions at least once per year; l

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DRESDEN II DPR-19 Amendment No. 116 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(2) The adherence to procedures, training and qualifica-tion of the station staff at least once per year; (3) The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or methods of operation that affect nuclear safety at least once per six months; (4) The performance of activities required by the Quality Assurance Program to meet the Criteria of Appendix "B",

10 CFR 50; (5) The Facility Emergency Plan and implementing proce-dures at least once per 12 months; (6) The Facility Security Plan and implementing procedures at least once per 12 months; (7) Onsite and Offsite Reviews; (8) The Facility Fire Protection Program and implementing procedures at least once per 24 months; (9) The radiological environmental monitoring program and the results thereof at least once per 12 months; (10) The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months; and (11) The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive waste at least once per 24 months.

All findings of noncompliance with NRC requirements and recommendations and results of each audit shall be reported to the Station Manager, the Manager of QA/NS, the Vice President BWR Operations, General Manager o. Quality Programs I

and Assessment, the Ser.ior Vice President-Nuclear Operations and the Chief Operating Officer.

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4 DRESDEN II DPR-19 Amendment No. 116 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

c.

Authority The Manager of QA/NS reports to the Chief Executive Officer.

The Manager of QA/NS has the authority to order unit shutdown er request any other action which he deems necessary to avoid unsafe plant conditions.

The General Manager of Quality Programs and Assessment re-I ports to the Senior Vice President-Nuclear Operations.

The General Manager of Quality Programs and Assessment has the l

authority to recommend unit shutdown or request any other action which he deems necessary to avoid unsafe plant condi-tions.

All such disagreements shall be reported immediately to the Manager of QA/NS and the Chief Operating Officer.

d.

Records 0

(1) Reviews, audits and recommendations shall be documented and distributed as covered in 6.1.G.I.a and 6.1.G.I.b.

(2) Copies of documentation, reports, and correspondence shall be kept on file at the station.

e.

Procedures Written administrative procedures shall be prepared and maintained for the Offsite Reviews and Investigative I

Functions described in Specifications 6.1.G.1.a.

These procedures shall cover the following:

(1) Content and method of submission of presentations to the Superintendent of the Offsite Review and Investi-l-

gative Function.

(2) Use of committees and consultants.

(3) Review and approval.

(4) Detailed listing of items to be reviewed.

(5) Method of (a) appointing personnel, (b) performing reviews, investigations, (c) reporting findings and recommendations of reviews and investigations, (d) approving reports, and (e) distributing reports.

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DRESDEN II DPR-19 Amendment No. 116 f

6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(6) Determining satisfactory completion of action required I

based on approved findings and recommendations reported by personnel performing the review and investigative function.

f.

Personnel (1) The persons, including consultants, performing the Offsite Review and Investigative Function, in-addition to the Superintendent of the Offsite Review and Investigative Function, shall have expertise in one or more of the following disciplines as appropriate for the subject or subjects being reviewed and investigated.

(a) nuclear power plant technology (b) reactor operations e

(c) utility operations (d) power plant design (e) reactor engineering (f) radiological safety (g) reactor safety analysis (h) instrumentation and control (i) metallurgy (j) any other appropriate diciplines required by unique characteristics of the facility.

(2)

Individuals performing the Offsite Review and l

Investigative Function shall possess a minimum formal training and experience as listed below for each discipline.

(a) Nuclear Power Plan + Technology Engineering graduate or equivalent with 5 years-I experience in the nuclear power field design and/or operation.

I (b) Reactor Operations Engineering graduate or equivalent with 5 years experience in the nuclear power plant operations.

(c) Utility Operations Engineering graduate or equivalent with at least 5 years of experience in utility operation and/or engineering.

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e DRESDEN II DPR-19 Amendment No. I M 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(d) Power Plant Desian Engineering graduate or equivalent with at least 5 years of experience in power plant design and/or operation.

(e) Reactor Engineering Engineering graduate or equivalent.

In addition, at least 5 years of experience in nuclear plant gineering, operation, and/or graduate work nuclear engineering or equivalent in reactor physics is required.

(f) Radiological Safety Engineering graduate or equivalent with at least 5 years of experience in radiation g

control and safety.

(g) Safety Analysis Engineering graduate or equivalent with at least 5 years of experience in nuclear engineering.

(h)

Instrumentation and Control Engineering graduate or equivalent with at least 5 years of experience in instrumenta-tion and control design and/or operation.

(i) Hetallurgy i

Engineering graduate or equivalent with at least 5 years o experience in the i

metallurgical field.

(3) The Superintendent of the Offsite Review and l

Investigative Function shall have experience and training which satisfy ANSI N18.1 - 1971 requirements for plant managers.

2.

The Onsite Review and Investigative Function shall be -

supervised by the Station Manager.

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DRESDEN II DPR-19 Amendment No. 116 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

a.

Onsite Review and Investigative Function The Station Manager shall:

(1) provide direction for the l

Review and Investigative Function and appoint the Technical Staff Supervisor, or.other comparably qualified individual as the senior participant to provide appropriate direction; (2) approve participants for this function; (3) assure that at least two participants who collectively postess back-ground and qualifications in the subject matter under review are selected to provide comprehensive interdisciplinary review coverage under this function; (4) independently review and approve the findings and recommendations developed by personnel performing the Onsite Review and Investigative Function; (5) report all findings of non-compliance w'.sh NRC requirements, and provide recommenda-tions; and (6) submit to the Offsite Review and Investiga-

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tive Function for concurrence in a timely manner, those i

items described in Specification 6.1 G.I.a which have been approved by tLa Onsite Review and Investigative Function.

I b.

Responsibility The Onsite Review e.,j Investigative Function shall be responsible for con _ ': ting the following:

(1) Review of all applicable Plant Administrative Procedures recommended in Appendix A of Regulatory Guide 1.33.

Revision 2, February 1978 and changes thereto; (2) Review of Emergency Operating Procedures required to implement the requirements of NUREG-0737 and Supplement I to NUREG-0737 as stated in Section 7.1 of Generic-Letter No. 82-33 and changes thereto; (3) Review of all proposed tests and experiments that affect nuclear safety; (4) Review of all proposed changes or. modifications to plant systems or equipment that affect nuclee: safety; (5) Review of proposed changes to the Fire Protection Program; (6) Review of the Station Security Plan and submittal of recommended changes to the Station Security Plan in accordance with station procedures; j

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DRESDEN 11 DPR-19 Amendment No. 116 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(7) Review of Emergency Plan and identification of recommended changes; (8) Review of changes to the PROCESS CONTROL PROGRAM and 0FFSITE DOSE CALCULATION MANUAL; (9) Review of all proposed changes to the Technical Specifications or Operating Licenses, and any proposed change which involves an unreviewed safety question that is to be submitted to the Commission for approval; (10) Review of investigation results for all violations of the Technical Specifications, including the preparation and I

forwarding of reports covering evaluations and a

recommendation to prevent recurrence; (11) Review of investigation results for all REPORTABLE EVENTS e

and other significant operating abnormalities, including

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the preparation and forwarding of reports covering evaluations and *ecommendation to prevent recurrence;

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(12) Review of investigation results for any accidental, unplanned, or uncontrolled radioactive release, including the preparation and forwarding of reports covering evaluations and recommendation to prevent recurrence; (13) Review of Unit operations to detect potential hazards to nuclear safety; and (14) Performance of special reviews and investigations anc reports thereon as requested by the Superintendent of the Offsite Review and Investigative Function, c.

Authority The Onsite Review and Investigative Function shall:

(1) Adsise the Station Manager on all matters related to nuclear safety; (2) Recommend to the Station Manager disposition of items considered under Specification 6.1.G.2.b(1) through (9) prior to their implementat'. n; (3)

Include among its review conclusions for each item considered under Specifications 6.1.G.2.o(1) through (4),

a determination of whether or not the item involves an unreviewed safety question; and i

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t DRESDEN II DPR-19 Amendment No. 116

[

6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(4) Provide prompt notification to the Vice-President BWR Operations and the Superintendent of the Offsite Review and Investigative Function of disagreement between the Onsite Review and Investigative Function and the Station Manager.

The Station Manager shall follow the recom-endations of the Onsite Review and Investigative Function or select a courre of action that is more conservative regarding safe operation of the facility.

d.

Records (1) Reports, reviews, fnvestigations, and recommendations l

prepared and performed for Specification 6.1.G.2.b shall be documented and forwarded to the Superintendent of the Offsite Review and Investigative Function unless otherwise specified.

,4 (2) Copies of all records and documentation shall be kept on file at the station.

e.

Procedures Written administrative procedures shall be prSDSred god maintained for conduct of the Onsite Review and Investiga-tive Function.

Those procedures shall include the following:

(1) Content and method of submission and presentation to the Station Manager, Vice president BWR Operations and the Superintendent of the Offsite Review and Investigative Functfen; (2) Use of committees; (3) -Review and approval; (4) Detailed listing of items to be reviewed; (5) Procedures for administration of the quality control activities; and (6) Assignment of responsibilities, f.

Personnel l

(1) The personnel, including consultants, performing the Onsite-Review and Investigative Function, in addition l

to the Station Manager shall have expertise in one or

)

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DRESDEN II DPR-19 Amendment No, 116 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

more of the following disciplines as appropriate for the subject or subjects being reviewed and investigated:

(a) nuclear power plant technology; (b) reactor operations; (c) reactor engineering; (d) radiological safety; (e) chemistry; (f) instrumentation and control; and (g) mechanical and electric systems.

(2) Personnel performing the On-site Review and l

Investigative Function shall meet minimum acceptable levels as described in ANSI N18.1-1971, Sections 4.2 and 4.4.

H.

Fire Protection.

1.

An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified off-site licensee personnel or ar. outside fire protection firm.

2.

An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

6.2 Procedures and Programs A.

Written procedures shall D established, implemented and maintained covering the activities referenced below:

1.

The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978; 2.

T'he Emergency Operating Procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Section 7.1 of Generic Letter No. 82-33; 3.

Station Security Plan implementation; 4.

Generating Station Emergency Response Plan implementation; 5.

PROCESS CONTROL PROGRAM implementation; 6.

OFFSITE DOSE CALCULATION MANUAL implementation; and 7.

Fire Protection Program implementation.

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to DRESDEN II DPR-19 Amendment No. 116 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

B.

Technical Review and Control Procedures required by Specification 6.2.A and other procedures which affect nuclear safety, as determined by the Station Manager, and changes thereto, shall be reviewed as follows prior to implementa-tion, except as noted in Specification 6.2.C:

1.

Each procedure or procedure change shall be independently reviewed by a qualified individual knowledgeable in the area affected other than the individual who prepared the procedure or procedure change.

This review shall include a determination of whether or not additional cross-disciplinary reviews are necessary.

If deemed necessary, the reviews shall be performed by the review personnel of the appropriate discipline (s).

2.

Individuals performing these reviews shall meet the applicable experience requirements of-ANSI N18.1-1971, Sections 4.2 and 4.4, and be approved by the Station Manager.

t 3.

Applicable Administrative Procedures recommended by Regulatory Guide 1.33, Plant Emergency Operating Procedures, and changes thereto shall be submitted to the Onsite Review and Investigative Function for review and approval prior to implementation in accordance with Specification 6.1.G.2.c(2).

4.

Review of the procedure or procedure change will include a deter-mination of whether or not an unreviewed safety question is involved.

This determination will be based on the review of a written safety evaluation prepared by a qualified individual, or documentation that a safety evaluation is not required.

Onsitt Review, Offsite Reiew and Commission approval of items involving unreviewed safety questions shall be obtained prior to station approval for implementation.

5.

The Department Head approval authority shall be as specified in station procedures.

6.

Written records of reviews performed in accordance with this specification shall be prepared and maintained in accordance with Specification 6.5.A.

7.

Editorial and typographical changes shall be made in accordance with station procedures.

C.

Temporary changes to procedures 6.2.A above may be made provided:

'1.

The intent of the original procedure is not altered; 6-14

i DRESDEN 11 DPR-19 Amendment No. 116 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

2.

The change is approved by two members of the plant manage-ment staff, at least one of whom holds a Senior Reactor Operator's. License on the Unit affected; and 3.

The change is documented,' reviewed, and approved in accordance with Specification 6.2.B within 14 days of implementation.

D.

Drills of the emergency procedures described in Specification 6.2.A.3 shall be conducted at the frequency specified in the Generating Station Emergency Plan.

These drills will be planned so that during the course of the year, communication links are tested and outside agencies are contacted, j

6.3 Action to be Taken in the Event of a REPORTABLE EVENT in Plant Operation Any REPORTABLE EVENT shall be promptly reported tr the Vice President

/

BWR Operations or his designated alternate.

The incident shall be

. promptly reviewed pursuant to Specification 6.1.G.2.b(11) and a separate l

report for each reportable event shall be prepared in accordance with the requirements of Specification 6.6.B.

6.4 Action to be Taken in the Event a Safety Limit is Exceeded l

If a safety limit is exceeded, the reactor shall be shut down immediately and reactor operation shall not be resumed until authorized by the NRC.

The conditions of shutdown shall be promptly reported to the Vice President BWR Operations or his designated alternate.

The incident shall be reviewed pursuant to Specification 6.1.G.1.a and 6.1.G.2.b(10) and a separate report for l

each event shall be prepared in accordance with Specification 6.6.B.

6.5 Plant Operating Records A.

R^cor.ds and/or logs relative in the following items shall be kept in a manner convenient for review and shall be retained for at least five years.

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DRESDEN II DPR-19' Amendment No. 116 6.0 ADMINISTRATIVE CONTROLS (Cont d.)

~

1.

Records of normal plant operation, including power levels and periods of operation at each power level.

l 2.

Records of principal maintenance activities, including inspection and repair, regarding principal items of equipment pertaining to nuclear safety.

3.

Records and reports of reportable and safety limit events, f

4.

Records and periodic checks, inspection and/or calibrations performed to verify the Surveillance Requirements (See Section 4 of these Specifications) are being met.

All equipment failing to meet serveillance requirerents and the corrective action taken shall be recorded.

5.

Records of changes made to the equipment or reviews of tests and experiments to comply with 10 CFR 50.59.

~

6.

Records of radioactive shipments.

[

7.

ards of physic tests and other tests pertaining to

. lear safety.

8.

Records of changes to procedures required by Specification 6.2.A and other procedures which affect nuclear safety, as determined by the tation Manager.

t i

9.

Shift Engineers Logs.

10.

By product material inventory records and source leak test results.

l B.

Records and/or logs relative to the following items shall be recorded in a manner convenient for review and shall be retair.3d for the life of the plant.

1.

Substitution or replacement of principal items of E

equipment pertaining to nuclear safety.

f 2.

Changes'made to the plant as it is described in the Safety i

Analysis Report.

i 3.

Records of new and spent fuel inventory and assembly histories.

,4.

(Deleted)

[

5.

Updated, corrected, and as-built drawings of the plant.

6-16 i

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UNRED STATES

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NUCLEAR REGULATORY COMMISSION o,

WASHINGTON, D.C. 20H6 :

COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENDHENT TO FACILITY OPERATING LICENSE Amendment No. 113' License No. DPR-25 1.

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

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated May 7 1992, as supplemented July:1,1992, complies.with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and i

regulations set forth in 10 CFR Chapter I;-

B.-

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

There is reasonable assurance (i) that the activities authorized-by this amendment can be conducted.without endangering the health and safety of the public, and (ii) that such-activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical-to the common defense and security or to the health and safety of the public; e

and E.

The issuance of this amendment is in accordance with 10 CFR'.Part 51 of the Commis ion's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and' paragraph 3.B.:of Facility Operating License No. DPR-25 is hereby amended to read as follows:

_-----.__------_..-.----..--.----___--__._.--.-._-----.--_.______-__w-_-.__----.-.:._-~-

• B.

Technical Soecifications The Technical Specift.ations contained in Appendix A as revised through Amendment No. 113, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION J

9'Barrett, Director Richard Project Directorate III-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical

/

Specifications D$teofIssuance: July 24, 1992 5

ATTACHMENT TO LICENSE AMENDMENT NO. 113 FACILITY OPERATING LICENSE NO. DPR-25 DOCKET NO. 50-249 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The_ revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT vi vi 1.0-6 1.0-6 6-1 6-1 6-2 6-2 6-3 6-3 6-5 6-5 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 6-30 6-30 6-11 6-11 6-12 6-12 6-13 6-13 6-14 6-14 6-1E 6-15 6-16 6-16

4 l

DRESDEN III DPR-25 Amendment No. 113 (Table of Contents, Cont'd.)

Page 4.9 Auxiliary Electrical Systems 3/4.9-1 4.9.A Stationhatteries 3/4.9-1 4.9.B (N/A)

4. 9. C Diesel Fuel 3/4.9-5 4.9.D Diesel Generator Oper.)ility 3/4.9-5 4.10.

Refueling 3/4.10-1 4.10.A Refueling Interlocks 3/4.10-1 4.10.8 Core Monitoring 3/4.10-1 4.10.C Fuel Storage Pool Water Level 3/4.10-2 4.10.0 Control Rod Drive and Control Rod Drive Maintenance 3/4.10-3 4.10.E Extended Core Maintenance 3/4.10-4 4.10.F Spent Fuel Cask Handling 3/4.10-5

4. b. G Fuel Storage Reactivity Limit 3/4.10-8 l

4.11 High Energy Piping Integrity 3/4.11-1 4.12 Fire Protection Systems -

Sections 4.12.A through 4.12.H -

Deleted per Generic Letters 86-10 and 88-12 (Amendment 101)

5. 0 Design Features 5-1 5.1 Site 5-1

5. 2 Reactor 5-1 5.3 Reactor Vessel 5-1 5.4 Containment 5-1 5.5 Fuel Storage 5-1 5.6 Seismic Design 5-2 6.0 Administrative Controls 6-1 6.1 Organization, Review, Investigation and Audit 6-1 6.2 Procedures and Programs 6-13 6.3 Action to be Taken in the-Event of a REPORTABLE EVENT in Plant Operation 6-15 6.4 Action to be +aken in the Event a Safety Limit is Exceeded 6-15 6.5 Plant Operating Records 6-15 6.6 Reporti'ng Requirements 6-17 6.7 Environmental Qualification 6-21 6.8 Offsite Dose Calculation Manual (ODCH) 6-23 l

6.9 Process Control Program (PCP) 6-24 6.10 Major Changes to Radioactive Waste Treatment Systems (Liquid, Gaseous, Solid) 6-24 vi

~

DRESDEN III DPR-25 Am:ndm2nt No. 113 1.0 DEFINITIONS (Cont'd.)

HH. Process Control Program (PCP) - Contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is assured.

II. Of(site Dose Calculation Manual (ODCM) - Contains the methodology and parameters used in the calculation of offsite doses due to radioactive l

gaseous and liquid eff1Jents, and in the calculation of gaseous and liquid effluent monitor alarm / trip setpoints.

s JJ. Channel Functional Test (Radia' ion Monitor) - Shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify operability including alarm and/or trip functions.

KK. Source Check - The qualitative assessment of instrument response when the sensor is exposed to a radioactive source.

LL. Member (s) of the Public - Shall include all persons who are not occupa-tionally associated with the plant.

This category does not include employees of the utility, its contractors, or vendors.

Also excluded from thi:; category are persons who enter the site to service :.quipment

^

or to make deliveries.

This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

MM. Rated Recirculation Pump Speed - is the recirculation pump speed that 6

corresponds to rated core flow (98 x 10 lb/hr) when operating at rated thermal power (dual loop operation).

NN. Dual Loop Operation - reactor pt ver operation with both recirculation pumps running.

00. Singie loop Operation (SLOl - reactor power operation with one recir-culation pump running.

PP. Transient Linear Heat Generatior. Rate (TLHGR) - The transient linear neat generation rate limit protects against fuel centerline melting and 1% plastic cladding, train durir.g transient conditions throughout the life of the fuel.

QQ. Fuel Design Limit;.y Ratio for Centerline Melt (FDLRC) - The fuel design miting ratfo for centerline melt is the limit used to assure that the fuel will neither experience centerline melt nor exceed 1%

plastic cladding strain for tran11ent overpower events beginning at any power av: terminating at 120% of rated thermal power.

RR. Linear Heat Cenerction Rate (LHGR) - lhe linear heat generation-rate is the operating fuel ' pin power level.

SS. Reportable Event - A Reportable Event shall be any of those conditions specified in 10 CFR 50.73.

1.0-6

~

ORESDEN III DPR-25 Amendment No.113 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization, Review, Investigation and Audit A.

Onsite and offsite organizations shall be established for the 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 hi hest management leyals through the intermediate levels to and inc uding all operating organiza-tion positions.

These relationships shall be documented and updated, as appropriate, in the form or organization charts, functional descriptions of department responsibilities and rela-tionships, and,jo) descriptions for key personnel positions, or in the equivalent forms of documentation.

The requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organizational Authority.

Activity; Section 6 Interdepartmental Relationships.

2.

The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities y

necessary for safe operetion and maintenance of plant.

3.

The Senior Vice President-Nuclear Operations shall have the 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 report to the appropriate onsito manager; however, they shall have suffi-cient organizational freedom to ensure their independence from operational pressures.

B.

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions, e.g., licensed Senior Operators, licensed Operators, health physics personnel, equipment operators, and key maintenance personnel.

The amount"of overtime worked by Unit staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12).

C.

The shift manning for the station shall be as shown in Table 6.1.1.

The Operating Assistant Superintendent, Operating Engineers, Shift Engineers, and Shift Foremen shall have a Senior Operating License.

The Fuel Handling Foreman shall have a limited Senior Operating License.

The Vice President BWR Operations on the corporate level has responsibility for the Fire Protection Program.

An Operating Engineer at the station will be responsible for implementation of the Fire Protection Program.

4 6-1

DRESDEN III DPR-25 Amendment No. 113 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

D.

Qualifications of the station management and operating staff shall meet minimum acceptable levels as described in ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel," dated March 8, 1971, with the exception of the Nealth Physics Services Supervisor who shall meet or exceed the qualifications of Radiation Protection Manager of Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a sc.ientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.

The individual filling the position of Technical Superintendent shall meet the minimum acceptable level for " Technical Manager" as described in 4.2.4 of ANSI N18.1 - 1971.

beinaccordancewithANSIN18.1,gofStationpersonnelshall Retraining and replacement trainin E.

Selection and Training of Nuclear Power Plant Personnel," dated March 8, 1971.

A training program for the fire brigade shall be maintained under the direction of the Operating Engineer and shall meet i

or exceed the requirements cf Section 27 of the NFPA Code -

1975, except for fire brigade training sessions which shall be held at least quarterly.

F.

Retraining shall be conducted at intervals not exceeding two years.

G.

The Review and Investigative Function and the Audit Function of activities affecting quality during facility operations shall be constituted and have the responsibilities and authorities outlined below:

1.

The Superintendent of the Offsite Review and I.1vestigative Function shall be appointed by the Manager of Quality Assurance /

Nuclear Safety (QA/NS).

The Corporate Audit function shall be the responsibility of the Manager of QA/NS and shall be independent of operations.

The Manager of QA/NS reports directly to the Chief Executive officer and has the responsibility to set Corporate Policy for both the areas of Quality Assurance and Nuclear Safety.

Policy is promulgated through a central policy committee directed by the Manager of QA/NS.

The Manager of QA/NS has the responsibility for the performance of periodic audits of each nuclear station and corporate department to determine that QA/NS policy is being carried out.

l 6-2 1

i

,-s--

DRESDEN III DPR-25 Amendment No. 313

~

6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

a._ Offsite Review and Investiaative Function The Superintendent of the Offsite Review and Investigative Function shall:

(i) provide directions fnr the review and investigative function and appoint a senior participant to provide appropriate direction, (ii) select each participant for this function, (iii) select a com)1ement of more than one participant who collectively possess sackground and qualifica-tions in the subject matter under review to provide comprehen-sive interdisciplinary review coverage under this function, (iv) independently review and approve the findings and recom-sendations developed by personnel performing the review and investigative function, (v) approve and report in a timely manner all findings of noncompliance with NRC requirements and provide recommendations to the Station Manager, Vice President BWR Operations, Manager QA/NS, General Manager of-Quality

_l Programs and Assessment and the Senior Vice President-Nuclear Operations.

During periods when the Superintendent of the Offsite Review and Investigative Function is unavailable, he l

shall designate this responsibility to an established alternate who satisfies the formal training and_ experience i

requirements for the Superintendent of the Offsite Review and l

Investigative function.

The responsibilities of the personnel performing this function are stated below.

The Offsite Review and Investigative l

Function shall review:

(1)Thesafetyevaluationsfor1)chankestoproceduresnthesafetyanalysis equipment or systems as described report and 2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such &ctions did not constitute unreviewed safety questions.

Proposed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of QA/NS; l

(2) Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; l

(3) Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59;

'l 6-3

DRESDEN III DPR-25 Amendment No. 113 I

6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(4) Proposed changes in Technical Specifications or i

this Operating License; (5) Noncompliance with Codes, regulations, orders, Technical Specifications, license requirements, or of I

? "i internal procedures or instructions having nuclear safety significance; i

gf (6) Significant operating abnormalities or deviations from normal and expected performance of plant equip-ment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function; l

(7) All REPORTABLE EVENTS; l

(8) All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems or components; I

(9) All changes to the Generating Stations Emergency Plan prior to implementation of such changes; and (10) All items referred by the Technical Staff Super-l visor, Station Manager, Vice President BWR Operations and General Manager of Quality Program and Assessment.

b.

Station Audit function The Station Audit Function shall be the responsibility of the General Manager of Quality Programs and Assessment independent of the Production Department.

Such responsibility is delegated to the Nuclear Quality Programs Manager.

The Nuclear Quality Programs Manager, or designated Corporate Staff or Supervision approved by General Manager of Qua!ity Programs and Assessment shall approve the audit agenda and checklists, the findings and the repcrt of each audit.

Audits shall be performed in accordance with the Company Quality

, Assurance Program and Procedures.

Audits shall be performed to assure that safety-related functions are covered within the period designated below.

6-5

ORESDEN III DPR-25 Amendment No. 113 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(1) The Conformance of facility operation to provisions con-tained within the Technical Specifications and applicable g

licen:e conditions at least once per year; (2) The adherence to procedures, training and qualification of the station staff at least once per year; (3) The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or methods of operation that.iffect nuclear safety at least once per six months; (4) The performance of activities required by the Quality Assurance Program to meet the Criteria of Appendix "B",

10 CFR 50; (5) The Facility Emergency Plan and implementing procedures at least one per 12 months; (6) The Facility Security Plan and implementing procedures at least once per 12 months; a

(7) Onsite and Offsite Reviews; (8) The Facility Fire Protection Program and implementing procedures at least once per 24 months; (9) The radiological environmental monitoring program and the results thereof at least once per 12 months; (10) The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months; and (11) The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive waste at least once per 24 months.

All findings of noncompliance with NRC requirements and recommen-

. dations and results of each audit shall be reported to the Station Manager, Manager of QA/NS, the Vice president BWR Operations, General Manager of Quality Programs and Assessment, the Senior Vice President-Nuclear Operations and the Chief Operating Officer. l 6-6

DRESDEN !!!

DPR-25 Amendment No. 113 l

i 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

i c.

Authority The Manager of QA/NS reports to the Chief Executive Officer.

The Manager of QA/NS has the authority to order unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions.

The General Manager of Quality Programs and Assessment reports to the Senior Vice President-Nuclear Operations.- The General Manager of Quality Programs and Assessment has the authority to recommend unit shutdown or request any other which he deems necessary to avoid unsafe plant conditions.

All such dis-agreements shall be reported immediately to the Manager of QA/NS and the Chief Operating Officer.

d.

Records (1) Reviews, audits and recommendations shall be documented and distributed as covered in 6.1.G.I.a and 6.1.G.1.b.

(2) Copies of documentation, reports, and correspondence-shall be kept on file at the station.

e.

Procedures Written administrative procedures shall be Trepared and maintained for_the Offsite Reviews and Invettigative Func-g tions described in Specifications 6.1.G.I.a.

These procedt!res shall cover the following:

(1) Content and method of submission of presentations to the Superintendent of the Offsite Review and Investigative l

Function.

(2) Use of committees and consultants.

(3) Review and approval.

(4) Detailed listing of items to 'e reviewed.

o 4

4

'f 6-7

)

DRESDEN III DPR-25 Amendment No. 113 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(5) Method of (a) appointing personnel, (b) performing reviews, investigations, (c) reporting findings and recommendations of reviews and investigations, (d) approving reports, and (e) distributing reports.

i (6) Determining satisfactory completion of action required based on approved findings and recommendaions reported by personnel performing the Review and Investigative Function.

I f.

Personnel t

(1) The persons, including consultants, performing the Offsite Review and Investigative Function, in addition to the Superintendent of the Offsite Review and Investigative i

Function, shall have expertise in one or more of the following disciplines as appropriate for the subject or subjects being' reviewed and investigated.-

(a) nuclear power plant technology-(b) reactor operations (c) utility operations-(d) power plant-design

/

(e) reactor engineering (f) radiological safety--

(g) reactor safety analysis (h) instrumentation and control (i) metallurgy (j) any other appropriate disciplines required by unique characteristics of the facility.

7 (2) Individuals performing the Offsite Review and Investigative l

Function shall possess a minimum formal training and-experience as_ listed below for each discipline..

(a) Nuclear Power Plant Technology Engineering graduate or equivalent with'5 years experience in the nuclear power field design and/or operation, e

(b) Reactor Operations Engineering graduate or-equivalent with 5 years experience in nuclear power plant operations.

i i

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6-8 i

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DRESDEN !!!

DPR-25 l

Amendment No. 113 i

6. 0 ADMINISTRATIVE CONTROLS (Cont'd.)

(c) Utility Operations Engineering graduate or equivalent with at least 5 years.of experience in utility operation and/or engineer %g.

l (d) Power Plant Desian l

Engineering graduate or equivalent with at least 5 i

years of experience in power plant design and/or

. operation.

(e)ReactorEngineerjng f

[

Engineering graduate or equivalent..In addition, at, i

least 5 years of experience in nuclear plant. engineer--

ing, operation, and/or graduate work in nuclear i

engineering or equivalent in reactor physics is required.

(f) Radiological Safety a

Engineering graduate or equivalent with at least 5 years of experience in radiation control and safety.

(g) Safety Analysis Engineering graduate or equivalent with at least l

5 years of experience in nuclear engineering.

-i (h) Instrumentation and Control l

Engineering graduate or equivalent w'ith_at least 5, years of experience in instrumentation and contrcl design and/or operation.

(i) Meta 11uroy Engineering graduate or equivalent with at-least i

5 years of experience.in the metallurgical field.

i (3) The Superintendent of the Offsite Revice and Investiga-l' f

tive Function shall have experience and training which i

satisfy ANSI N18.1 - 1971 requirements for plant managers, j

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_,_,.._,_,.._._.J

DRESDEN III DPR-25 Amendment No. 113 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

2.

The Onsite Review and Investigative Function shall be supervised by the Station Manager, a.

Onsite Review and Investicative Function The Station Manager shall:

(1) provide direction for the Review and Investigative Function and appoint the Technical Staf f Supervisor, or other comparably qualified individual as the senior participant to provide appropriate direction; (2) approve participants for this function; (3) assure that at least two participants who collectively possess background and qualifications in the subject matter under review are selected to provide comprehensive interdisciplinary review coverage under this function; (4) independently review and approve the L

findings and reconmendations developed by persennel perform'ng the Onsite Review and Investigative Function; (5) report all l

3 findings of noncompliance with NRC requirements, and provide recommendations; and (6) submit to the Offsite Review and l

Investigative function for concurrence in a tisoely manner, those items described in Specification 6.1.G.I.a which have been approved by the Onsite Review and Investigative Function.

/

b.

Responsibility The Onsite Review and Investigative Function ;, hall be responsible for conducting the following:

(1) Review of all applicable Plant Administrative Procedures recommended in Appendix A of Regulatory GuMe 1.33, Revision 2, February 1978 and changes thereto; (2) Review of Emergency Operating Procedures required to implement the requirements of NUREG-0737 and Supplement I to NUREG-0737 as stated in Section 7.1 of Generic Letter No. 82-33 and changes thereto; (3) Review of all proposed tests and experiments that affect nuclear safety; (4) Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety; (5) Review of proposed changes to the Fire Protection Prograir; (6) Review of the Station Security Plan and submittal of recommended changes to the Station Security Plan in accordance with station procedurer; (7) Review of Emergency Plan and identification of recommended changes; (8) Review of changes to the PROCESS CONTROL PROGRAM and 0FFSITE DOSE CALCULATION MANUAL; 6-10

DRESDEN III DPR-25 Amendment No.113 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(9) Review of all proposed changes to the Technical Specifications or Operating Licenses, and any proposed change which involves an unreviewed safety question that is to be submitted to the Commission for approval; (10) Review of investigation results for all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluations and recommendation to prevent recurrence; (11) Review of investigation results for all REPORTABLE EVENTS and other significant operating abnormalities, including the preparation and forwarding of reports covering evaluations and recommendation to prevent recurrence; (12) Review of investigation results for any accidental, unplanned, or uncontrolled radioactive release, including the preparation and forwarding of reports covering evaluations and recommendation to prevent recurrence; (13) Review of Unit operations to detect potential hazards to nuclear safety; and-o (14) Performance of special reviews and investigations and reports thereon as requested by the Superintendent of the Offsite Review and Investigative Function.

c.

Authority The Onsite Review and Investigative Function shall:

(1) Advise the Station Manager on all matters related to nuclear safety; (2) Recommend to the Station Manager disposition of items considered under Specification 6.1.G.2.b(1) through (9) prior to their implementation; (3) Include among its review conclusions for each item considered under Specifications 6.1.G.2.b(1) through (4),

a determination of whether or not the item involves an unreviewed safety question; and (4) Provide prompt notification to the Vice-President BWR Operations and the Superintendent of the Offsite Review and Investigative Function of disagreement betweer the Onsite Review and Investigative function and the Station Manager.

The Station Manager shall follow the recommendations of the Onsite Review and Investigative function or select a course of action that is more conservative regarding safe operation of the facility.

6-11

DRESDEN III DPR-25 Amendment No. 113 6.0 ADMINISTRATIVE CONTROLS (Cor,t' d. )

d.

Records (1) Reports, reviews, investigations, and recomendations prepared and performed for Specification 6.1 G.2.b shall be documented and forwarded to the Superintendent of the Offsite Review and Investigative Function unless other-wise specified.

(2) Copies of all records and documentation shall be kept on file at the station.

e.

Procedures Written administrative procedures shall be prepared and maintained for conduct of the Onsite Review and Investigative l

Function.

These procedures shall include the following:

(1) Content and method of submission and presentation to the Station Manager, Vice President BWR Operations and the Superintendent of the Offsite Review and Investigative Function; i

(2) Use of comittees; (3) Review and approval; (4) Detailed listing of items to be reviewed; (5) Procedures for administration of the quality control activities; and l

(6) Assignment of responsibilities.

f.

Personnel (1) The personnel, including consultants, performing the Onsite I

Review and Investigative Function, in addition to the Station Manager, shall have expertise in one or more of the following disciplines as appropriate for the subject or subjects being reviewed and investigated:

(a) nuclear power plant technology; (b) reactor operations; (c) reactor engineering; (d) radiological safety; (e) chemistry; (f) instrumentation and control; and (g) mechanical and electric systems.

6-12 l

DRESDEN III DPR-25 Amendment No. 113 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(2) Personnel performing the Onsite Review and Investigative l

Function shall meet minimum acceptable levels as described in ANSI N18.1-1971, Sections 4.2 and 4.4.

H.

Fire Protection 1.

An independent fire protection and loss prevention program inspec-tion and audit shall be performed at least once per 12 months utilizing either qualified off-site licensee personnel or an outside fire protection firm.

2.

An inspection and audit of the fire protection and loss prevention nrogram shall be performed by a qualified outside fire consultant at least once per 36 months.

6.2 Procedures and Programs A.

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

1.

The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978; a

2.

The Emergency Operating Procedures required to implement the requirements of NUREG-0737 and Supplement I to NUREG-0737 as stated in Section 7.1 of Generic Letter No. 82-33; 3.

Station Security Plan Implementation; 4.

Generating Station Emergency Response Plan implementation; 5.

PROCESS CONTROL PROGRAM implementation; 6.

OFFSITE DOSE CALCULATION MANUAL implementation; and 7.

Fire Protection Program implementation.

6-13

DRESDEN III DPR 25 I

Amendment No.

113 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

B.

Technical Review and Control Procedures required by Specification 6.2. A and other procedures which affect nuclear safety, as determined by the Station Manager, and changes thereto, shall be reviewed as follows prior to implementation, except as noted in Specification 6.2.C:

1.

Each procedure or procedure change shall be independently reviewed by a qualified individual knowledgeable in the area affected other than the individual who prepared the procedure or procedure change.

This review shall include a determination of whather or not additional cross-disciplinary reviews are necessary.

If deemed necessary, the reviews shall be performed by the review personnel of the appropriate discipline (s).

2.

Individuals performing these reviews shall meet the applicable experience requirements of ANSI N18.1-1971, Sections 4.2 and 4.4, and be approved by the $tation Manager.

3.

Applicable Administrative Procedures recommended by Regulatory Guide 1.33, Plant Emergency Operating Procedures, and changes thereto shall be submitted to the-Onsite Review and Investigative Function for review and approval prior to implementation in accordancewithSpecification6.1.G.2.c(2).

e 4.

Review of the procedure or procedure change will include a determination of whether or not an unreviewed safety question is involved.

This determination will be based on tne review of a written safety evaluation prepared by a qualified individual or documentation that a safety evaluation is not required.

OnsIte Review, Offsite Review and Commission approval of items involving unreviewed safety questions shall be obtained prior to station approval for implementation.

5.

The Department Head approval authority shall be as specifieJ in station procedures.

6.

Written records of reviews performed in accordance with this specification shall be prepared and maintained in accordance with Specification 6.5.A.

7.

Editorial and typographical changes shall be made in accorda",ce with station procedures.

6-14

/,

DRESDEN III DPR-25 Amendment No. Ils 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

C.

Temporary changes to procedures 6.2. A above may be made provioed:

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; and 3.

The char.ge is documented reviewed, and approved in accordance with Specification 6.2.BwithIn14daysofimplementation.

D.

Drills of the emergency procedures described in Specification 6.2.A.3 shall be conducted at the frequency specified in the Generating Station Emergency Plan.

These drills will be planned so that during the course of the year, connunication links are tested and outside agencies are contacted.

6.3 Action to be Taken in the Event of a REPORTABLE EVENT in Plant Operation Any REPORTABLE EVENT shall be promptly reported to the Vice President BWR Operations or his designated alternate.

The incident shall be promptly reviewed pursuant to Specification 6.1.G.2.b(11) and a separate l

/

report for each reportable event shall be prepared in accordance with

,. the requirements of Specification 6.6.B.

6.4 Action to be Taken in the Event a Safety Limit is Exceeded I

If a safety limit is exceeded, the reactor shall be shut down immediately and reactor operation shall not be resumed until authorized by the NRC.

The conditions of shutdown shall be promptly reported to the Vice President BWR Operations or his designated alternate.

The incident shall be reviewed pursuant to Specification 6.1.G.I.a and 6.1.G.2.b(10) and a separate report

[

for each event shall be prepared in accordance with Specification 6.6.B.

6.5 Plant Operating Records A.

Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained for at least five years.

1.

Records of normal plant operation, including power levels and periods of operation at each power level.

6-15

DRESDEN III OPR-25 Amendment No. 113 6.0 ADMINI_STRATIVE CONTROLS (Cont'd.)

2.

Records of principal maintenance activities, including inspection and repair, regarding principal items of equipment pertaining to nuclear safety.

3.

Records and reports of reportable and safety limit events.

4.

Records and periodic checks, inspection and/or calibrations performed to verify the Surveillance Requirements (See Section 4 of these Specifications) are being met.

All equipment failing to meet surveillance requirements and the corrective action taken shall be recorded.

5.

Records of changes made to the equipment or reviews of tests and experiments to comply with 10 CFR 50.59.

6.

Records of radioactive shipments.

7.

Records of physic tests and other tests pertaining to nuclear safety.

8.

Rec'rds of changes to procedures required by Specification 6.2.A and other procedures which affect nuclear safety, as determined

/

by the Station Manager.

9.

Shift Engineers Logs.

10. By product material inventory records and source leak test results.

B.

Records and/or logs relative to the following items shall be recorded in a manner convenient for review and shall be retained for the life of the plant.

1.

Substitution or replacement of principal items of equipment pertaining to nuclear safety.

2.

Changes made to the plant as it is described in the Safety Analysis Report.

3.

Records of new and spent fuel inventory and assembly histories.

4.

(Deleted) 5.

Updated, corrected, and a'.-built drawings of the plant.

6.

Records of plant radiation and contamination surveys.

7.

Records of off-site environmental monitoring surveys.

6-16

lpasoug%

8' o

UNITED STATES g

,j NUCLEAR REGULATORY COMMISSION t,

wmnNotoN. D.C. s0006

....+

COMONWEALTil EDISON COMPANY AtiD IOWA-ILLINOIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-251 00AD CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 135 License No. DPR-29 1.

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

8 A.

The application for amendment by Commonwealth Edison Company (the licensee) dated May 7,1992, as supplemented July 1,1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

.The issuance of this amendment is in acco with 10 CFR Part s.

51 of the Commission's regulations and a.

.ppiicable requirements-have been satisfied.

2.

Accordingly, the license is amended by changes to-the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-29 is hereby-amended to read as follows:

. l t

B.

Technical Specifications The Technical Specifications contained in Apsendices A and B, as revised through Amendment No. 135, are here)y incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR Tile NUCLEAR REGULAT RY COMMISSISN yp.tk Richar arrett, Director Project Directorate 111-2 Olvision of Reactor Projects - !!!/IV/V Office of Nuclear Reactor.iegulation

Attachment:

e Changes to the Technical

.$recifications Date of Issuance:

July 24, 1992 r

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i s

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ATTACHMENT TO LICENSE AMENDNENT No.135 FAtlL11Y OPERATING LICENSE NO. DfR-29 DOCKET NO. 50-254 Revise the Appendix A Technical Sp;cifications by removing the pages identified below and inserting the attached.pages. The revised pages are

?'

identified by the cLptioned amendment number and contain marginal lines indicating the area of change.

t PD0VI JNSERT

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a 6.1-1 6.1-1 6.1-3 6.1-3 6.1-4 6.1-4 j

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6.1 6.1 5 j

i 6.1-6 6.1-6 l

6.1-7 6.1-7 i

6.1-8 6.1-8 i

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6.1-9 6.1-9 6.1-10 6.1-10 f

I 6.1-11 6.1 '

1 6.2-1 6.2-1

-i 6.2-2 6.2-2

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6.2-3 I.

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QUADCITIES DPR-29 TABLEOFCONTENTS(Cont'd)

Fage 3.12/4.12 FIRE PROTECTION SYSTEMS 3.12/4.12-1 A.

Five Detection Instrumentation 3.12/4.12-1 B.

Fire Suppression W ter System 3.12/4.12-2 C.

Sprinkler Systems 3.12/4.12-4 D.

00: Systems 3.12/4.19. E.

Fire Hose Stations 3.12/4.12-7 l F.

Penetration Fire Barriers 3.12/4.12-7 G.

Fire Pump Diesel Engine 3.12/4.12-8 3.12/4.12 Limiting Conditions for Operation and Sur<eillance 3.12/4.12-10 Requirements Bases 5.0 DESIGN FEA1URES 5.0 I t.0 ADMINISTRATION CONTROLS 6.1-1

.e i

6.1 Organization, Review, Investigation, and Auoit 6.1-1 6.2 Precedures and Program:

6.2-1 o

. 6. 3 Reportable Event Action 6.3-1 6.4 Action to be Taken in the Event a Safety Limit is :xceeded 6.4-1 6.5 Plant Operating Records 6.5-1 6.6 Reporting Requirements 6.6-1 6.7 Environmental Qualification 6.7-1

'4 6.8 Offsite Dose Calculation Manual (0DCM) 6.8-1 6.9 Process Control Program (PCP 6.9-1 6.10 Major Changes to Radioactive) Waste Treatment Systems (Liquid, Gaseous, Solid) 6.10-1 6.11 Radiation Protection Program 6.11-1 6.12 High Radiation Area 6.12-1

+

'iv Amendment No.135

QUAD-CITIES DPR-29 6.0 ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION, REVIEW, INVESTIGATION, AND AUDIT A.

Onsite and offsite organizations shall be established for unit operation and corporate management, resp 2ctively.

The onsite and offsite organiza-tions shall include the positions for acMvities affecting the safety of the nuclear power plant.

1.

Linet, of authority, responsibility, and communication shall be estralished 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 apnropriate, in the form of organization charts, functional descrip-tions of department responsibilities and relationships, and job descriptions for key personnel positions, or in the equivalent in forms of documentation.

These requirements shall be documented the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organization Authority, Activities:

Section 6 Interdepartmental Relationships.

2.

The Station Manager shall be responsible for overall unit safe operation and shall haJe control over thos6 onsite activities necessary for safe operation and maintenance of the plant.

3.

The Senior Vice President-Nuclear Operations shall have the corpo-rate responsibility for overall plant nuclear safety and shall take cny measures needed to ensure acceptable performance cf 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 report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their Independence from operating pressures.

B.

Administrative procedures shall be developed and implemented to limit the working hours of cnit staff who perform safety-related functions; e.g., licensed Senior Operators, licensed Operators, health physics personnel, equipment operators, and key maintenance personnel.

The amount of overtime worked by Unit staff members performing safety-related functions shall be limited in accordance with the NRC Policy ftatement on working hours (Generic Letter No. 82-12).

C.

The shift manning for the station shall be as shown in Figure 6.1-3.

The Operating Assistant Superintendent, Operating Engineer, Shift Engi-neers, and Shift Foremen shall have a Senior Operator's License.

The Fual Handling Foreman has a limited Senior Operator's License.

The Vice President BWR Operations on the corporate level has responsibility for the Fire Protection Program.

The Maintenance Assistant Superintend-ent will be responsible for implementation of the Fire Protection Program.

A fire brigade of at least 5 members shall be maintained on-site at all times.

This excludes the shift crew necessary for safe shutdown of the plant, and any pasonnel required for other essential functions during a fire emergency.

6.1-1 Amendment No.135

QUAD-CITIES DPR-29 G.

The Review and Investigative Function and the Audit Function of activ-ities affecting quality during facility operations shall be constituted and have the responsibilities and ethorities outlined below:

1.

The Superintend:nt of the Offsite leview and Investigative Function shall be a p ointed by the Manager of Quality Assurance / Nuclear Safety (QA/NS) responsible for nuclear activities.

The Corporate l

Audit Function shall be the responsibility of the Manager of QA/NS and shall be independent of operations.

The Manager of QA/NS rceports directly tr) the Chief Executive Officer and has the responsibility to set Corporate Policy for botii the areas of Quality Assurance and Nuclear Safety.

Policy is promul-gated through a central policy committee directed by the Manager of QA/NS.

The Manager of QA/NS has the responsibility for the perform-ance of pericdic audits of each nuclear station and corporate depsrtment to determine that QA/NS policy is being carried out.

l a.

Offsite Review and Investigative Function The Superintendent of the Offsite Review and Investigative Function shall:

(1) provide directions for the review and investigative function and appoint a senior part8cipant to provide appropriate direction, (2) select each participant for this function, (3) select a complement of more than one participant who collectively possess background and qualifica-tions in the subiect matter under review to provide comprehen-sive interdisciplinary review covetage under this function, (4) independently review and approve the findings and recom-mendations developer 1 by personnel performing the review and investigative function, (5) approve and report in a timely manner all findings of noncompliance with NRC requirements to the Station Manager, Vice President BWR Operations, Manager of QA/NS, General Manager (GM) Quality Programs and Assessment, l

and the Senior Vice President-Nuclear Operations.

During periods when tM Superintendent of Offsite Review and 'Investi-gative Furetion ;? unavailable, he shall designate this responsibiliv fa an established alternate, who satisfies the formal training and experience for the Superintendent of the l

Offsite Review and Investigative Function.

The responsibil-ities of the personnel performing this function are stated below.

The Offsite Review and Investigative Function shall review:

(1) The safety evaluations for: (1) changes to procedures, I

equipment, or systems as described in the safety analysis report and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.

Proposed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of QA/NS; l

6.1-3 Amendment No. 135

=

QUAD CITIES DPR-29 (2) Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR $0.59; l

(3) Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; (4) Proposed changes in Technical Specifications or this Operating License; (5) Noncomplia,ce with Codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures, or instructions having nu ' ear safety significance; (6) Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function; (7) All REPORTABLE EVENTS; I

(8) All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components; (9) All changes to the Generating Stations Emergency Plan prior to implementation of such change; and (10) All items referred by the Technical Staff Supervisor, Station Manager, Vice President BWR Operaticns, and GM Quality Programs and Assessment.

b.

Station Audit Function The Station Audit Function shall be the responsibility of the GM Quality Programs and Assessment independent of BWR Opera-l tions.

Such responsibility is delegated to the Nuclear Quality Programs Manager.

The Nuclear Quality Programs Manager or designated Corporate Staff or Supervision approved by the GM Quality Programs and Assessment shall approve the audit agenda and checklists, the findings and the report of each audit.

Audits shall be performed in accordance with the Company Quality Assurance Nogram and Procedures.

Audits shall be performed to assure nat safety-related functions are covered within the period designated below:

(1) The conformance of facility operation to provisions l

l contained within the Technical Specifications and l

applicable license conditions at least once 32 months; g

6.1-4 Amendment No. 135

QUAD-CITIES DPR-29 (2) The adherence to procedures, training and qualification of the station staff at least once per 12 months; (3) The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or methods of operation that affect nuclear safety at least once per 6 months; (4) The performance of activities required by the Quality Assurance Program to meet the Criteria of Appendix B 10 CFR Part 50, at least once p 24 months:

(5) The Facility Emergency Plan and implementing procedures at least once per 12 months; (6) The Facility Security Plan and implementing procedures at least once per 12 months; (7) Onsite and offsite reviews; (8) The Facility Fire Protection programmatic controls including the implementing procedures at least once per 24 months by qualified QA personnel; (9) The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months; (10) The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months; and (11) The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive waste at least once per 24 months.

All findings of noncompliance with NRC requirements and recommendations and results of each audit shall be reported to the Station Manager, Manager of QA/NS, GM Quality Programs and Assessment, Vice President BWP. Operations, the Senior Vice President-Nuclear Operations, and the Chief Operating

Officer, c.

Authority The Manager of QA/NS reports to the Chief Executive Officer.

The Manager of QA/NS has the authcrity to order unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions.

6.1-5 Amendment No. 135

QUAD-CITIES DPR-29 The GM Quality Programs and Assessment reports to the Senior Vice President-Nuclear Operations.

The GM Quality Programs and Assessment has the authority to recommend unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions.

All such disagreements shall be reported immediately to the Manager of QA/NS and the Chief

}

Operating Officer.

d.

Records (1) Reviews, audits, and recommendations shall be documented and distributed as covered in 6.1.G.I.a and 6.1.G.I.b.

(2) Copies of documentation, reports, and correspondence shall be kept on file at the station.

e.

Procedures Written administrative procedures shall be prepared and main-tained for the offsite reviews and investigative functions described in Specifications 6.1.G.1.a.

Those procedures shall cover the following:

(1) Content and method of submission of presentations to the Superintendent of the Offsite Review and Investigative Function.

(2) Use of committees and consultants.

(3) Review and approval.

(4) Detailed listing of items to be reviewed.

(5) Method of (1) appointing personnel, (2) performing reviews, investigations, (3) reporting findings and recommendations-of reviews and investigations, (4) approving reports, and (5) distributing reports.

(6) Determining satisfactory completion of action required based on approved findings and recommendations reparted by personnel performing the review and investigative function.

f.

Personnel 1)

The persons, including consultants, performing the Offsite Review and Investigative Function, in addition to the Superintendent of the Offsite Review and Investi-gative Function, shall have expertise in one or more 6.1-6 Amendment No. 135

QUAD-CITIES OPR-29 of the following disciplines as appropriate for the subject or subjects being reviewed and investigated:

a)

Nuclear power plant technology, b)

Reactor operations, c)

Utility operations, d)

Power plant design, e)

Reactor enginem 'ng, f)

Radiological a f g)

Reactor safety anaiysis, a

h)

Instrumentation and control, 1)

Heta11urgy, j)

Any other appropriate disciplines required by unique characteristics of the facility.

2)

Individuals performing the Offsite Review and Inves-l tigative Function shall possess a minimum formal training and experience as listed below for each discipline.

a)

Nuclear Power Plant Technology Engineering graduate or equivalent with 5 years experience in the nuclear power field design and/or operations.

b)

Reactor Operations Engineering graduate or equivalent with 5 years experience in nuclear power plant operations.

c)

Utility Operations Engineering graduate or equivalent with at least 5 years of experience in utility operation and/or engineering, d)

Power Plant Design Engineering graduate or equivalent with at least 5 years of experience in power plart design and/or operation, e)

Reactor Engineering Engineering graduate or equivalent.

In addition, at least 5 years of experience in nuclear plant engineering, operation, and/or graduate work in nuclear engineering or equivalent in reactor physics is required, f)

Rac;iological Safety Engineering graduate or equivalent with at least 5 years of experience in radiation control and safety, ti.1-7 Amendment No. 135

QUAD-CITIES OPR-29 g)

Reactor Safety Analysis Engineering graduate or equivalent, with at least 5 years of experience in nuclear engineering.

h)

Instrumentation and Control Engineering graduate or equivalent with at least 5 years of experience in instrumentation and control design and/or operation.

i)

Metallurgy Engineering graduate or equivalent with at least 5 years of experience in the metallurgical field.

3)

The Superintendent of the Offsite Review and Investigative Function shall have experience and training which satisfy ANSI N18.1-1971 requirements for plant managers.

2.

The Onsite Review and Investigative Function shall be' supervised by the Station Manager, a.

Onsite Review and Investigative Function The Station Manager shall:

(1) provide direction for the Review and Investigative Function and appoint the Technical i

Staff Supervisor, or other comparably qualified individual as 1

a senior participant to provide appropriate directions; (2) approve participants for this function; (3) assure that a complement of at least two participants who collectively l

possess background and qualifications in the subject matter under review are selected to provide comprehensive interdisciplinary review coverage under this function; (4) independently review and approve the findings and I

recommendations developed by personnel performing the Onsite l

Review and Investigative Function: (5) report all findings of noncompliance with NRC requirements, and provide recommenda-tions; and (6) submit to the Offsite Review and Investigative Function concurrence in a timely manner, those items described in Specification 6.1.G.1.a which have been approved by the Onsite Review and Investigative Function.

i b.

Responsibility i

The Onsite Review and Iavestigative= Function shall be responsible.for conducting the following:

1 1)

Review of all applicable Plant Administrative Procedures-recommended in Reg. Guide 1.33, Revision 2, February 1978 and changes thereto; 6.1-8 Amendment No. 135

i r

QUAD-CITIES l

DPR-29 2)

Review of Emergency Operating Procedures required to implement the requirements of NUREG-0737 and Supple-ment 1 to NUREG-0737 as stated in Section 7.1 of Generic Letter No. 82-33 and chang:s thereto; j

3)

Review of all

~oposed tests and experiments that affect nuclear safety; 4)

Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety;

-t i

5)

Review of proposed changes to the Fire Protection Program; 6)

Review of the Station Security Plan and submittal of recommended changes to the Station Security Plan in accordance with station procedures; 7)

Review of Emergency Plan and identification of recommended changes; 8)

Review of changes to the PROCESS CONTROL PROGRAM and'the 0FFSITE DOSE CALCULATION MANUAL;

+

i 9)

Review of all proposed changes to the Technical Specifications or Operating License, and any proposed change which involves an unreviewed t,afety question that is to be submitted to the Commission for approval; i

10) Review of investigation results for all violations of the Technical Specifications,_incieling the preparation and forwarding of reperts covering tvaluations and recommendations to prevent recurrence;

11) Review of investigation results for all REPORTABLE EVENTS and other significant operating abnormalities including the preparation and forwarding of reports covering-evaluations and recommendations to prevent recurrence; i

12) Review of any accidental, unplanned, or uncontrolled t

I radioactive release including the preparation and j

forwarding of reports covering evaluations and rcrommendations to prevent recurrence;

13) Review of Unit operations to detect potential hazards to nuclear safety;

14) Performance of special reviews and -investigations 'and f

reports thereon as-reque ;;ed by the Superintendent of the t

Offsite Review and-Investigative Function.

t i

I 6.1 Amendment No.135 i

L

.._..i._,--__ _..

.,,_.6--_,

-s u,-,,-.

QUAD-CITIES SPR-29 c.

Authority i

The Onsite Review and Investigative Function shall:

1)

Advise the Station Manager on all matters related to Nuclear Safety.

2)

Recommend to the Station Manager '6he disposition of items considered under Specification 6.1.G.2,a.1) through 9) prior to their implementation.

3)

Inq ude amon, its review conclusions for each item considered under Specification 6.1.G.2.a.1) through 4), a determination of whether or not thc item involves an unreviewed safety question.

4)

Provide prompt notification to the Vice President BWR Operations and the Superintendent of the Offsite Review and Investigative Functirn of disagretment between the Onsite Review and Investigative Function and the Station Manager.

The Station Manager shall follow the t

recommendatis.s of the Onsite Review and Investigative Function or select a course of action that is more conservative regarding safe operation of the facility.

d.

R? cords 1)

Reports, reviews, investigations, and recommendations prepared and performed for specification 6.1.G.2.a shall be documented and forwarded to the Superintendent of the Offsite Review and Investigative Function unless other-wise specified.

2)

Copies of all records and documentation shall be kept on l

file at the station, e.

Procedures P

l Written administrative procedures shall be prepared and maintained for conduct of the Onsite Review and Investigati"e l

function.

These procedures shall include the following:

1)

Content and method of submission and presentation to the Station Manager, Vice President BWR Operations, and the Superintendent of the Offsite Review anc Investigative Function.

i 2)

Use of committees when necessary.

l l

3)

Review and approval.

4)

Detailed listing of items to be reviewed.

6.1-10 Amendment No. 135

}

QUAD-CITIES DPR-29 5)

Procedures for administration of the quality control activities.

I 6)

Assignment of responsibilities, f.

Personnel 1)

The personnel, including consultants, performing the Onsite Review and Investigative Function,-in addition to the Station Manager, shall have expertise in one or more of the following disciplines as appropriate for the subject or subjects being reviewed and investigated:

a)

Nuclear power plant technology, b)

Reactor operations, c)

Reactor engineering, d)

Chemistry, e)

Radiological controls, f)

Instrumentation and control, and g)

Mechanical and electric systems, t

2)

Personnel performing the Onsite Review and Investigative Function shall meet minimum acceptable levels as described in ANSI N18.1 1971, Sections 4.2 and 4.4.

H.

Fire Protection Program An independent fire protection and loss prevention program inspection and audit shall be performed at least once pe,- 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.

An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

6.1-11 Amendment No.135

QUAD-CITIES DPR-29 6.2 PROCEDURES AND PROGRAMS A.

Written procedures.shall be established, implemented-and maintained covering the activities referenced below:

1.

The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, 2.

The emergency operating procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Section 7.1 of Generic Letter No. 82-33, 3.

Station Security Plan implementation, 4.

Generating Station Emergency Plan implementation, 5.

PROCESS CONTROL PROGRAM implementation, 6.

OFFSITE DOSE CALCULATION MANUAL implementation, and 7.

Fire Protection Program implementation.

6.2-1 Amendment No. 135

QUAD-CITIES DPR-29 6.2 PROCEDURES AND PROGRAMS (Continued)

B.

DELETED C.

Technical Review and Control e

Procedures required by Specification 6.2.A and other procedures which affect nuclear safety, as determined by the Station Manager, and changes thereto, other than editorial or typographical cha mes, shall be reviewed as follows prior to implementation, except as noteo in Spcifica-tion 6.2.D:

1.

Each procedure or procedure change shall be independently reviewed by a qualified individual knowledgeable in the area affected other than the individual who prepared the procedure or procedure change.

This review shall include a determination of whether or not additional cross-disciplinary reviews are necessary.

If deemed necessary, the reviews shall be performed by the qualified review personnel of the appropriate discipline (s).

2.

Individuals performing these reviews shall meet the applicable experience requirements of ANSI 18.1, 1971, Sections 4.2 and 4.4, 3

and be approved by the Station Manager.

3.

Applicable Administrative Procedures recommended by Regulatory Guide 1.33, Plant Emergency Operating Procedures, and changes thereto shall be submitted to the Onsite Review and Investigative Function for re:iew and approval prior to implementation in accordance with Specification 6.1.G.2.b.

4.

Review of the procedure or procedure change will include a determination of whether or not'an unreviewed safety question is involved.

This determination will be based on the review of a written safety evaluation prepared by a qualified individual (s), or documentation that a safety evaluation is not required.

Onsite Review, Offsite Review and Commission approval of items involving-unreviewed safety questions shall be obtained prior to station approval for implementation.

5.

The Department Head approval authority shall be as specified in station procedures.

6.

Written records of reviews performed in accordance with this specification shall be prepared and maintained in accordance with Specification 6.1.G.2.

7.

Editorial and typographical changes shall be made in accordance with station procedures.

6.2-2 Amendment No.135 -

i QUAD-CITIES DPR-29 6.2 PROCEDURES AND PROGRAMS (Continued)

D.

Temporary changes to procedures 6.2. A may be made provided:

1.

Th9 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.

?

The change is documented, reviewed, and approved in accordance with Specification 6.2.c within 14 days of implementation.

E.

Drills of the emergency procedures described in Specification 6.2. A shall be conducted in accordance with the GSEP manual.

t t

E 6.2-3 Amendment No. 135

amu (7

g UNITED STATES

-s a

NUCLEAR REGULATORY COMMISSION -

WASHINoTON, D.C. 20006

\\.....,/

COMMONWEALTH EDISON COMPANY-s 8!iQ IOWA-ILLINOIS GAS AND ELECTRIC COMPANY DOCKET NO 50-265 OVAD CITIES NUCLEAR POWER STATION. UNIT R AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 131 License No. DPR-30 1.

The Nuclear Regulatory Commission-(the Commis:; ion) has found that:

c A.

The application for amendment by Commonwealth Edison Company (the licensee) dated May 7,1992, as supplemented July 1,1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and-regulations set forth-in 10 CFR Chapter I;-

B.

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

There' is rei.sonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that _such-activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the-health and safety of_ the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission'_s regulations and all applicable requirements

-have.been satisfied.

2.

Accordingly; the license is amended.by changes 'to the Technical Specifications as indicated in the attachment.to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-30 is hereby amended-to read as follows:

e

. B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.131, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 0v4 Rich r

. Barrett, Director Projec Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Attachment:

! Changes to the Technical

, Specifications Date of Issuance: July 24, 1992

O ATTACHMENT TO LICENSE AMENDMENT NO. 131 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265 Revise the Appendix A Technical Specifications by re-cying the pages identified below and inserting the attached pages. The ievised pages are ider,tified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT iv iv 6,1-1 6.1-1 6.1-3 6.1-3 6.1-4 6.1-4 6.1-5 6.1-5 e

6.1-6 6.1-6 6.1-7 6.1-7 6.1-8 6.1-8 6.1-9 6.1-9 6.1-10 6.1-10 6.1-11 6.1-11 6.2-1 6.2-1 6.2-2 6.2-2 6.2-3 l

L QUAD CITIES DPR-30 TABLE OF CONTENTS (Cont'd) t Page i

3.12/4.12 Limiting conditions for operations and Surveillance 3.12/4.12-6 Requirements Bases 5.0 DESIGN FEATURES 5.0 1 6.0 ADMINISTRATIVE CONTROLS 6.1 1 i

6.1 Organization, Review, Investigation, and Audit

-6.1-1 l

6.2 Procedures and Programs 6.2-1 t

6.3 Reportable Event Action 6.3-1 s

6.4 Action to be Taken in the Event a Safety Limit is Exceeded 6.4-1 r

6.5 Plant Operating Records 6.5-1 6.6 Reporting Requirements 6,6-1 6.7 Environmental Qualification 6.7-1 6.8 Offsite Dose Calculation Manual (ODCM) 6.8 1-a6. 9 Process Control Program (PCP) 6.9-1

6. (0 Major Changes. to Radioactive Vaste Treatment Systems 6.10-1 (Liquid, Caseous, Solid) 6.11 Radiation Protection Program 6.11-1 6.12 High Radiation Area 6.12-1 l

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F iv Amendment No. 131 e

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QUAD-CITIES DPR,

6.0 ADMINISTRATIVE CONTROLS i

l 6.1 ORGANIZATION, REVIEW, INVESTIGATION, AND AUDIT A.

Onsite and offsite orga,Izations:shall be established for-unit operation and corporate management..respectively.

The onsite and 4

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offsite organizations shall include the positions for activities affecting the-safety of the nuclear power plant.

4 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 i

positions.

These relationships shall be documented and updated, as appropriate, in the form of organization charts,-functional-descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in.the equivalent forms of documentation.

These requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations Section 3 Organization Authority, Activities:-Section 6 Interdepartmental Relationships.

2.

The Station Kanager 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 Operations shall have the corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable per.formance of the staff in operating, maintaining, and providing technical support to tne plant to ensure nuclear safety.

4.

The individuals who train the werating staff and those who carry out health physics and quality assurance functions may report to the appropriate unsite manager; however,-they shall_have sufficient organizational freedom to ensure'their independence from operating pressures.

B.

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., licensed Senior Operators, licensed Operators', health physics personnel, equipment operators, and key maintenance personnel.

The amount of overtime worked by Unit staff members perfcrming safety-related functions.shall be limited in accordance with the NRC Policy Statement.on working hours (Gener.lc Letter.No. 82-12).

C.

The shift manning for the station shall be as shown in figure 6.1-3.

The. Operating Assistant Superintendent, Operating Engineer, Shift Engineers, and Shift Foremen shall have a senior operator's license.

The Fuel Handling Foreman has a limited Senior Operator's License.

The Vice' President BWR Operations on the corporate level has responsibility for.the Fire Protection Program.

The'Haintenance Assistant Superintendent will be responsible for. implementation of the Fire Protection Program. A fire brigade of at least 5 members shall be maintained on-site at all times.

This excludes the shift crew-necessary for safe shutdown of the plant, and any personnel required for other essential functions during a fire emergency.

6.1-1 Amendment No. 131

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QUAD-CITIES DPR-30

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G.

The Review and Investigative Function and the Audit Function of.

activities affecting quality during facility operations shall be constituted and have the responsibilities and authorities outlined below:

1.

The Superintendent of the Offsite Review and Investigative Function shall be_ appointed by the Manager of Quality Assurance / Nuclear Safety (QA/NS) rtsponsible for nuclear activities. The Corporate Audit Function shali De the responsibility of the Manager of Quality Assurance / Nuclear Safety (QA/MS) and shall be independent of operations.

The Manager of QA/NS reports directly to the Chief Exe:Utive Officer and has the responsibility to set Corporate Policy for.

both the areas of Quality Assurance and Nuclear Safvty.

Policy is prosylgated through a central policy comittee directed by the.

Manager of QA/NS. The Manager of QA/XS has the responsibility.for the performance of periodic audits of each nuclear statlan and corporate department to determine that QA/NS policy is being l

carried out, a.

Offsite Review and Investigative Function' The Superintendent of the Offsite Review and Investigative Function shall:

(1) provide directiens for the review and investigative function and apootnt a-senior participant to provide appropriate directior., (2) select each participant for this function, (3) select a complement of more than one participant who collectively possess background and qualifications in the subject matter under review to provide comprehensive interdisciplinary review coverage under this function, (4) Independently review and approve-the findings and recomendations developed by personnel performing the review and investigative function, (5): approve and report in a timely manner all findings of noncompliance with NRC requirements to the Station Manager, Vice President BWR-Operations,'Hanager QA/NS, General Manager (GM) Quality l

Programs and Assessment,.and the Senior Vice. President of Nuclear Operations.

During periods when the Superintendent of'Offsite-Review and Investigative Function is unavailable, he shall designate this responsibility to an established alternate, who satisfies the formal training and experience for the Superintendent of the Offsite Review and l

Investigative Function. The responsibilities of the personnel performing this function are stated below. The.

i Offsite Review and Investigative Function shall review:

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6.1-3 Amendment No. 131

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QUAD-CITIES DPR-30

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1) The safety evaluations for:

(1) changes to procedures.

l equipment, or systems as described in the safety analysis report and (2) tests or experishents completed under the provision of 10 CFR 50.59.to verify that such actions did not constitute an unreviewed safety question. Proposed changes to the Quality Assurance Program descriptton shall be reviewed and approved by the Manager of QA/NS; l

2) Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; l

3) Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59;

4) Proposed changes in Technical Specifications or this Operating License;

5) Noncompliance with Codes, regulattor.3, orders, Technical Specifications, license requirements, or of internal procedures, or. instructions having nuclear safety significance;

6) Sign!ficant operating abnormalities or deviation from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and' Investigative Function;

7) A'l REPORTABLE EVENTS;

8) All recognized. indications of an unanticipated deficiency in some aspect of design or operation il safety-related structures, systems, or componen'es;

9) All changes to the Generating Stctions Emergency Plan prior te implementation of such change; and

10) All items referred by the Technical Staff Supervisor, Station Manager, Vice President BHR Operations, and GM Quality Programs and Assessment.

b.

Station Audit Function The Station Audit Function shall be the responsibility of the GM Quality Programs and Assessment independent of BWR l

Operations. Such responsibility-is delegated to the Nuclear Quality Programs Manager.

6.1-4 Amendment No.131

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QUAD-CITIES DPR-30 I

The Nuclear Quality Programs-Manager or designated Corporate l

Staff or Supervision approved by the GM Quality Prograr.s-and Assessment shall approve the audit agenda and checklists..the:

l i-findings and the report lof each audit. Audits shall be performed in accordance with the Company Quality Assurance Program and Procedures.- Audits-shall be performed to assure that safety-related functions are covered within the' period designated below:

ll

1) The conformance of-facility operation to' provisions

-l-contained within-the Technical Specifications.and

-applicable license conditions at least once per 12 months;- l

2) The adherence to-procedures, training and qualification of the station staff at least once per 12_ months;

-3) The results of actions taken to correct deficiencies occurring in_ facility equipment, structures, systems, or-methods of operation that affect nuclear safety at least once per 6 months;

4) The performance of activities required by the Quality-Assurance-Program to meet-the Criterta of Appendix B, 10 CFR Part 50, at least once per 24 months;-

5) The Facility Emergency-Plan and implementing procedures at least once per 12 months;

6) The Facility Security Plan and implementing procedures at least once per 12 months; 7)- Onsite and offsite reviews;-

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8) The Facility Fire Protection programatic controls including the implementing procedures at least once per r

24 months by-qualified QA personnel;

9) The Radiological Environmental: Monitoring Program and the-

-results thereof at least once per 12 months;

10) The OFFSITE DOSE CALCULATION MANUAL and implementing _

procedures at least once per 24 months; and F

11) The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive waste at11 east once per 24 months.

All findings of noncompliance with NRC requirements and-recommendations knd results_of each audit-shall be reported to the Station Manager, Manager of QA/NS, GM Quality Prc, grams and Assessment,Vice President BHR Operations, the-Senior-Vice. President-Nuclear Operations, and the Chief Operating l

Officer.

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5.1-5 Amendment No. 131.

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QUAD-CITIES

.DPR-30 c.-

Authority The' Manager of-QUNS reports to the Chief Executive Officer.-

The Manager of QUNS has the authority 'to order unit shutdown or request any other action which he deems necessary to avoid unsafe plant-conditions.-

i The GM Quality Progr ec end Assessment-reports to the Senior-i Vice President-Wuclear Operations. The GM Quality: Programs-

- and Assessment-has the authority.to recomend unit shutdown or request any other action which he deems'necessary to avoid unsafe plant conditions. All such disagreements shall be reported imediately to the Manager of QUNS and the Chief

-l Operating Officer.

d.

Records

1) Reviews, tudits,-and recommendations shall be documented __

and distributed as covered in 6.1 G.I.a and 6.1.G.I.b.

2) Copies of-documentation, reports, and' correspondence-shall be kept on file at the station.

a e.

Procedures j

Written administrative procedures shall be prepared and maintained for the_offsite reviews and investigative functions described in Specifications 6.1.G.1.a.

Those procedures shall-cover the following:

1) Content-and method of submission of presentations to the Superintendent of the Offsite P.eview and Investigative j

function.

I

2).Use of comittees and. consultants.

3) -Review and approval..

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4) Detailed' listing of. items to be reviewed.

5) Method'of (1) appointing personnel, (2) performing reviews, investigations,-(3) reporting findings and recomendations of. reviews and investigations, (4) approving reports,-and_(5) distributing reports.

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6) Determining satisfactory completion of-action required based on approved findings and recommendations reported i

by personnel performing-the review and investigative i

function, t

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6.1-6 Amendment No.131 i

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QUAD-CITIES DPR-30 f.

Personnel

-1) The persons, including consultants, performing the Offsite Review and Investigative Function, in addition to l

the Superintendent of the Offsite Review and Investigative Function, shall have' expertise in one or more of the following disciplines as appropriate for the subject or subjects being reviewed and investigated:

a) Nuclear power plant technology, b) Reactor operations, c) Utility operations, d) Power plant design, e) Reactor engineering, f) Radiological safety, g) Reactor safety analysis, h)

Instrumentation and control,

1) -Metallurgy, j) Any other appropriate disciplines required by unique characteristics of the facility.

2) Individuals performing the Offsite Review and l

Investigative Function shall possess a minimum formal t.aining and expertence as listed below for each discipline, a) Nuclear Power Plant Technolegy Engineering graduate or equivalent with 5 years experience in the nuclear power field design and/or operations.

b) Reactor Operations Engineering graduate or. equivalent with 5 years expertence in nuclear power plant operations.

c) Utility Operations Engineering graduate or equivalent with at least 5 years of experience in utility operation and/or engineering, d) Power Plant Design Engineering graduate or equivalent with at least 5 years of experience in power plant design and/or operation.

e) Reactor Engineering Engineering graduate or equivalent.

In addition, at least 5 years of expertence in nuclear plant engineering, operation, and/or graduate work in nuclear engineering or equivalent in reactor physics is required.

6.1-7 Amendment No. 131

QUAD-CITIES DPR-30 f) Radiological Safety.

I Engineering graduate-or equivalent with at least 5 years'of experience.in radiation control.and safety.

g) Reactor Safety. Analysis Engineering graduate or equivalent.- with at least 5 years of experience in nuclear engineering, h) Instrumentation and Control Engineering graduate or equivalent with at least 5 years of experience in-instrumentation and control design and/or N aratton.

1) Metallurgy Engineering graduate or equivalent with at least 5 years of expe* lance in the metallurgical field.-

3 3)- The Superintendent of the Offsite Review and Investigative Funcilon shall-have expertence and'trainteg which satisfy ANSI N18.1-1g71 requirements for-plant.

managers.

2.

The Onsite Review and Investigative Function shall be supervised I

by the Station Manager, a.

Onsite Review and Investigative Function l

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The Station Manager shall:

(1) provide direction for the-Review and Investigative. Function and appoint the Technical i

Staff Supervisor, or other comparably qualifted individual as t

a senior-participant.to provide' appropriate directions; (2)-

i i

approve participants lfor this function; (3)tassure that a 7

l complement:of at least two participants who collectively possess background and qualifications-in the; subject matter i

under review-are selected to provide comprehensive r

l interdisciplinary review coverage-under this function;'(4)-

I_

independently review and approve the findings-and

- reconnendations.-developed by personnel performing the Onsite.

Review and Investigative Function;;(5) report all findings of:

noncompliance with NRC requirements, and provide reconnendations;-and (6) submit to the Offstte Review and-Investigative-Function concurrence in a timely manner, those l

items described in-Specification 6.1.G.1.a which have been t

approved by the Onsite Review and Investigative Function.-

i 6.1-8 Amendment No.131 l

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QUAD-CITIES DPR-30

-b.

Responsibility The Onsite Review and Investigation Function shall be responsible for conducting the following:

1)

Review of all-appilcable Plant Administrative Procedures recommended by Reg. Guide 1.33. Revision 2 February 1978, and changes thereto; 2)

Review of Emergency Operating Procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Section 7.1 of Generic Letter No.

82-33 and changes thereto; 3)

Review of all proposed tests and experiments that affect nuclear safety; 4)

Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety; S)

Review of proposed changes to the Fire Protection Program; 6)

Review of the Station Security Plan and subir.1ttal'of l

recommended changes to the Station Security Plan in accordance with station procedures; 7)

Review of Emergency Plan and identification of recomended changes; 8?

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL; 9)

Review of all proposed changes to Technicel 3pecifications or Operating License, and any proposed chknge which involves an unreviewed safety question that is to be submitted to the Comission for approval; t

i

10) Review of investigation results for all violations of the Technical Specifications, including the preparation and forwarding of reports coverir.g evaluations and recommendations to prevent recurrence;

11) Review of Investigation results for all REPORTABLE EVENTS and other significe.nt operating abnormalltles including the preparation and forwarding of reports covering evaluations and recommendations to prevknt recurrence;

12) Review of any ecctdental, unplanned, or uncontrolled radioactive release including the preparation and forwarding of reports covering evaluations and recomendations to t

prevent recurrente; P

13)

Review of Unit operations to detect potential hazards to nuclear safety; l

6.1-9 Amendment No.

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QUAD-CITIES DPR-30

14) Perforn:ance of special reviews and investigations and reports thereon as requested by the Superintendent of the Offsite Review and Investigative function.

Authority The Onsite Review and Investigative function shall:

1)

Advise the Station Manager on all matters related to Nuclear

Safety, 2)

Recommend to the Station Manager the disposition of items considered under Specification 6.1.G.2.a.1) through 9) prior to their implementation.

3)

Include among its review conclusions'for each item considered under Specification 6.1.G.2.a.1) through 4), a determination of whether or not the item involves an unreviewed safety question.

4)

Provide prompt notification to the Vice President BWR Operations and the Superintendent of the Offsite Review and Investigative Function of disagreement between the Onsite Review and Investigative Function and the Station Manager.

c The Station Manager shall follow the recomendations of the Onsite Review and Investigative Function or select a course of action that is more conservative regarding safe operation of the facility, d.

Records 1)

Reports, reviews, investigations, and recomendations prepared and performed for Specification 6.1.G.2. shall be documented and forwarded to the Superintendent of the Offsite Review and Investigative Function unless otherwise specified.

2)

Copies of all recctds and documentation shall be kept on file at the station.

e.

Procedures Written adm191strative procedures shall be prepared and maintained for conduct of the Onsite Review and Investigative function.

These procedures shall include the following:

1)

Content and method cf submission and presentation to the Station Manager, Vice President BWR Operations, and the Superintendent of the Offsite Review and Investigative Function.

2)

Use of committees when necessary.

3)

Review and approval.

6.1-10 Amendment No.

131

o QUAb-CITIES DPR-30 4)

Detailed listing of items to be reviewed.

5)

Procedures for admir.istration of the quality control activities.

6)

Assignment of responsibilities.

i f.

Personnel 1)

The personne1, including consultants.: performing the Onsite l

Review and Investigative Function, in addition to the Station Manager, shall have expert:ise in one or more of the following disciplines as appropriate for the subject or subjects being reviewed and investigated:

a) Nuclear power plant technology, b) Reactor operations, c) Reactor engineering, d) Chemistry, e) Radiological controls, f)- Instrumentation and control ;and-g) Nechanical and electric systtes.

2)

Personnel performing the Onsite Review and Investigative Function shall meet minimum acceptable levels as-described in ANSI M18.1 1971, Sections 4.2 and 4.4.

H.

Fire P"otection Program An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.

An inspection and audit of ths_ fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

6.1-11 Amendment No.131

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CUAD-CITIES DPR.30 6.2 PROCEDURES AND PROGRAMS A.

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

1.

The applicable procedures reconnended in Appendix A of Regulatory Guide 1.33, Revision 2. February 1978, 2.

The emergenc3 operating procedures required to implement the requiromenta of NUREG-0737 cnd Supplement 1 to NUREG-0737 as stated in Section 7.1 of Generic Letter Mc. 82-33, 3.

Station Security Plan implementation, 4.

Generating Station Emergancy Plan implementatten, 5.

PROCESS CONTROL PROGRAM 1mplementation, 6.

OFFSITE DOSE CALCUATION MAWJAL implementation, and 7.

Fire Protection Program implementation.

6.2-1 Amendment No. 131

QUAD-CITIES DPR-3D 62 PROCEDURLS AND PROGRAMS (Continued)

B.

DELETED C.

Technical Review and Control Procedures required by Specification 6.2.A and other procedures which affect nuclear safety, as determined by th< Station Hanager, and changes thereto, other than editorial or typographical changes, shall be reviewed as follows prior to implementation except as noted in Specification 6.2.D.:

1.

Each procedure or procedure change shall be independently reviewed by a qua11 fled individual knowledgeable in the area affected other than the individual who prepared the procedure or procedure change.

This review shall include a determination of whether or not additional cross-disciplinary reviews are necessary.

If deemed necessary, the reviews shall be performed by the qua11 fled review personnel of the appropriate discipline (s).

2.

Individuals performing these reviews shall meet the applicable experience requirements of ANSI 18.1, 1971, Sections 4.2 and 4.4, and be approved by the Station Manager.

3.

Applicable Administrative Procedures recommended by Regulatory Guide 1.33, Plant Emergency Operating Procedures, and changes thereto shall be submitted to the Onsite Review and Investigative Function for review and approval prior to implementation in accordance with Specification 6.1.G.2.b.

4.

Review of the procedure or procedure change 'will include a determination of whether or not an unreviewed safety question is involved.

This determination will be based on the review of a written safety evaluation prepared by a quallfled individual (s),

or docc;nentation that a safety evaluation is not required. Onsite Review, Offsite Review and Commission approval of items involving unreviewed safety questions shall be obtained prior to Station approval for implementation.

S.

The Department Head approva' authority shall be as specified in station procedures.

6.

Written records of reviews performed in accordance with this specification shall be prepared and maintained in accordance with Specification 6.1.G.2.

7.

Editorial and typographical changes shall be made in accordance with station procedures.

6.2-2 Amendment No.131

l QUAD-CITIES DPR-30 6.2 PROCEDURESANDPROGRAMS(Continued)

D.

Temporary changes to procedures 6.2.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 r:sagement staff, at least one of whom holds a Senior Reactor Operator's license on the unit affected.

3.

The change is documented, reviewed and approved in accordance with Specification 6.2.C within 14 days of implementation.

E.

Drills of the emergency procedure; described in Specification 6.2.A shall be conducted in accordance with the G5EP manual.

4 6.7.-3 Amendment No. 131

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