ML20079H208

Application for Amends to Licenses DPR-29 & DPR-30, Reflecting Util Efforts to Upgrade Existing Tech Spec Section 6.0, Administrative Controls

ML20079H208
Person / Time
Site:	Quad Cities
Issue date:	10/02/1991
From:	Schrage J COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20079H211	List: ML20079H208 ML20079H214
References
NUDOCS 9110100202
Download: ML20079H208 (51)

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, (C b Downers Grove, Illinois 50515 October 2, t991 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulator Commission Washington, D.G. 205y5 a Attn: Document Control Desk

Subject:

Quad Cities Nuclear Power Station Units 1 and 2 Application for Amendment to Facility Operathg Licenses DPR 29 and DPR-30, Appendix A, fechnical Specifications Technical Specification Upgrade Program NRCRockeLNos,50:25 Land 50-265 Dr. Murley:

In 1990, Quad Cities Station hitlated a formal program to enhance the Gution's per'armance in various aspects of plant operation. The Performance Gahucement Program (PEP) was developed by assessing existing improvement pic.ns, elentifying potential weaknesses and prioritizing improvement actions, d ceinary improvements to the Technical Specifications were identified as one of the Stntion top priority issue. Details of the goal and methodclogy for the Technical Spechication Upgrade Program are provided in the Executive Surnmary section of the prooosed amendment. The Program has been previously discussed with members of the NRR staff.

Pursusnt to 10 CFR 50.90, Commonwealth Edison proposes to amend Appendix A, Technical Specificatienc to Facility Operating Licenses DPR-29 and DPR-30. The prowsed amendment reflects Commonwealth Edison's efforts to upgrade existing "echnical Specification Section 6.0 "Administrat' re Controls". An overall description of the proposed amendment is also included in the Executive Summary.

The oroposed amendment request for each Technical Specification section is provided as fol}ows:

1. An Executive Summary of the Technical Specification Upgrade Program and the proposed amendment;

2. A summary of the changes;

3. A detailed descriptica of the changes;

4. Th9 proposed Technical Specification pages with the requested changes; I 5. The existing Technical Specification pages for JPR 29, are marked-up to l reflect the appropriate changes to the existing bases sections.

l Commonwealth Edison's evaluation pursuant to 10 CFR 50.92(c) and 6.

10 CFR 51.21; and,

7. The technical differences between the existing Unit 1 and Unit 2 Technical Specifications, 0g 911010o202 911002 ADOCK 0500 0\

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Dr. Thomas E. Murley October 2,1991 The 3roposed amendment has been reviewed and approved by Commonwealt i Edison's on site and off site review in accordance with Company procedures.

The Technical Specification Upgrade Program proposes changes to each section of the existing Technical Specifications. As such, Commonwealth Edison rec:uests that the proposed amendments be approved and issued as one document rathe than as individual sections. Commonwealth Edison respectfully requests the NRC s approval of the upgraded Technical Specifications by July 1,1992.

To the best of my knowledge and belief, the statements contained are true and correct.- In some respects, these statements are not based on my personal knov,' edge but obtained information furnished by other Commonwealth Edison emphyees and consultants. Such information has been reviewed in accordance with Comp:! y practice and I believe it to be reliabla.

Commonwealth Edison is notifying the State of Illir.ois of this application for amendment by transmitting a copy of this letter and its attachments to the designated State Official.

Please direct any questions concerning this proposod amendment to J. Schrage at 708/515-7283.

Very trul l /;9c,y yoursfx[4 ,

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/ John L. Schrage Nucids Licensing Administrator Enclosure (A): Proposed Amendment to Technical Specification Section 6.0, " Administrative Controia" cc: A.Bert Davis, Regional Administrator l- ' LN. Olshan, Pro ect Manager T.E. Taylor, Senior Resident inspector -

Illinois Department of Nuclear Safety State of . County of #f_

Signed ore me on thisMday of 4.199 . , , oFFICI A S ANDRA C Notary Public A NmRY FuetX miE ARA

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EXECUTIVE

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QUAD CITIES TECHNICAL BPECIPICATION UPGRADE PROGRAM The Quad Cities Technical Specification Upgrade Program O was conceptualized in respense to lessons learned from the Dresden Diagnostic Evaluatien Team inspection and the frequent need for Technical Specification interpretations. A comparison of the existing Quad Cities Technical Specification and, Standard Technical Specifications and later operating plants' Technical Specification provisions was conducted to identify potential improvements in O clarifying requirements and to identify requirements which are no longer consistent with current industry practices.

The comparison review identified approximately one-hundred and fifty suggested improvements. The Technical Specification Upgrade Program was not intended to be a complete adoption of the Standard Technical Specifications.

Overall, the Quad Cities custom Technical Specifications

.O provide for safe operation of the plant and, therefore, only a upgrade was deemed appropriate.

The comparison study reve21ed a mix of recommended upgrades which included the relaxation of certain existing Technical Specification requirements, the addition of g surveillances, the removal of allowances which would no longer be allowed under new plant licensing, and better definition of appropriate action requirements in the event a Limiting Condition for Operation cannot be met. The Technical Specification Upgrade Progrnm also implements NRC recommended line item improvements to the Technical Specifications which were issued under Generic Letters.

O In response to an NRC recommendation, the Unit 1 and Unit 2 Technical Specifications are combined into one document. To accomplish the combination of the Units' Technica: Specifications, a comparison of the Unit 1 and 2 Technica'. Specifications was performed to identify any technical differences. The technical differences are 0 identified in the proposed amendment package for each section.

• The Technical Specification Upgrade Program was identified as a Station top priority during the development of Quad Cities Station's Performance Enhancement Program O (PEP). The Technical Specification Upgrade Program's goal is to provide a better tool to Station personnel to implement their responsibilities and to ensure Quad Cities Station is operated in accordance with current industry practices. The upgraded specifications provide for more safe and reliable operation of the plant. The program improves the operator's ability to use the Technical Specifications by more clearly O defining Limiting Conditions for Operations and required actions.

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, EXECUTIVE SUKMARY Jcontinued)

Proposed Changes to Technical Specification Section 6.0 " Administrative Controlar

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In this proposed amendment, new programmatic controls for radioactive effluents and radiological environmental monitoring are relocated to Technical Specification Section 6.0. Procedural details are relocated, as applicable to the Offcite Dose Calculation Manual (ODCM) and the Process Control Program (PCP) in accordance with the guidance issued

j) by the NRC in Generic Letter 89-01.

S Also, this proposed amendment removes the Fire Protection Systems and the fire brigade staffing requirements from tre Technical Specifications, and adds administrative controls to support the Fire Protection Program in accordance lO with the guidance for removal of the fire protection requirements from the Technical Specifications provided by Enclosure 1 to Generic Letter 88-12.

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SUMMARY

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O C) SUKMARX OE CHANGES PROPOSED SPECIFICATION 6.0 ADMINISTRATIVE CONTROLS O This amendment package is one in a series of proposals that will provide improvements to the present Quad Cities Technical Specifications. The summary of changes includes a list of changes that are page by page specific.

Item 1:

~O Paces L.1_1 and 5 1-9. DPR-29 Delete the reference to the fire brigade in 6.1.C. Add the review of the Fire Protection Program and implementing procedures and submittal of recommended changes to the Offsite Review and Investigative Function in 6.1.G.2. These changes tre needed in O order to implement the provisions of Generic Letter 88-12 conc 1rning the deletion of Fire Protection from the technical spectfications.

Item 2:

Eages 6.2-1, 6.2-2. 6.5-2, 6.6-3, 6.6-4, 6.6-5, 6.8-1, 6.9-1. and I) 6.10-1. DPR-29 The proposed changes to the affected pages are made in order to implement the provisions of Generic Letter 89/01 concerning relocation of Radiological Technical Specifications to the ODCM and the Process Control Program Specifications to the PCP. Other o minor changes are made to eflect changes made to other technical specification sections,

a. The title of Section 6.2 is changed from Plant Operating Procedures to Plant Operating Procedures and Programs.

b. New Sections 6.2.F and 6.2.G are added for the Radioactive O Effluent Controls Program and the Radioactive Environmental Monitoring Program,-respectively,

c. Section 6.5.B on Plant Operating Records is changed by adding  ;

the life of the plant retention requirement for reviews performed for changes made to the ODCM and PCP.

O d. Present Sections 6.6.B.1, RaFloactive Effluent Release Report (Semi-Annual), and 6.6.B.2, !.nvironmental Program Data (Annual Report), and Section 6.6.B.3 are replaced with Generic Letter 89/01 guidelines.

e. Proposed changes to Table 6.6-1, Special Reports, include o referencing-the ODCM for relocated technical specification 0

O O sections, the addition of the Special Reporting requirement for the Explosive Gas Mixture specifications, and the renumbering of present specifications to match changes proposed to other technical specification sections,

f. Present Section 6.8, Offsite Dose Calculation Manual (ODCM),

is replaced with Generic Letter 89/01 guidelines.

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g. Present Section 6.9, Process Control Program (PCP), is replaced with Generic Letter 89/01 guidelines. l l

h. Present Section 6.10-1, Major Changes to Radioactive Waste l Treatment Systems (Liquid, Gaseous, Solid), is deleted from  !

q the technical specifications and placed in the ODCM and PCP. l v

Item 3:

Ea[Le 6.6-2, DPR-29 The Monthly Operating Report requirements in 6.6.A.3 are changed O by deleting the requirements to include changes to the ODCM and major changes to the radioactive waste treatment systems.

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PROPOSED TS 6.0 g ' ADMINISTR ATIVE CollTROLS" 3

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[ pESCRIPTION O_I PAQf_OBJJ} ARENDMENI REQUESl PROPOSED SPECIFICATION 6.0 ADMINISTRATIVE CONTROLS

) The chances proposed in this amendment request are r.iade tc 1) improve the understanding and usability of the preacnt technical specifications, 2) incorporate technical improvements, and 3) include some provisions from later operating BWR plants.

An item by item description of the proposed changes requested is provided below. The Summary of Changes section can be referred to

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in order to reference back to a given change and its affected j page.

Item 1 Generic Letter 86-10 recommended the removal of fire protection I requirements from the technical specifications. Although a comprehensive Fire Protection Program is essential to plant safety, the basis for this recommendation is that many details of this program that are currently addressed in the technical specifications can be modified without affecting nuclear safety.

Such modifications can bs made provided that there are suitable administrative controls over these changes. These details, that b are presently included in the technical specifications and which are removed by this amendment request, do not constitute performance requirements necessary to ensure safe operation of the facility and, therefore, do not warrant being included in the technical specifications. At the same time, suitable administrative controls ensure that there will be careful review g and analysis by competent individuals of any changes in the Fire Protection Program including those technical and administrative requirements removed trom the technical specifications to ensure that nuclear safety .s not adversely affected. These controls include: (1) the technical specification administrative controls that are applicable to the Fire Protection Program; (2) the license condition or implementation of, and subsequent changes to p the Fire Protection Program; and (3) the 10 CFR 50.59 criteria tor evaluating changes to the Fire Protection Program as described in the UFSAR.

This proposed amendment removes the Fire Protection Systems and fire brigade staffing requirements from the technical specifications, and adds administrative controls to support the b Fire Protection Program. Enclosure 1 to GL 88-12 provides the guidance for removal of fire protection requirements from the technical specifications. The Generic Letter addresses five elements that should be included in a license amendment request.

These five elements and Quad Cities implementation methods are discussed below.

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_$ 1) GEllEElC JETTER 88-12: The NRC Fire Protection Program must be incorporated into the FSAR and submitted with the certification required by 10 CFR 50.71(e)(2), as requested by GL 8 6-10. The PSAR update includes the incorporation of the Fire Protection Program, including the fire hazards analysis and najor commitments that form the basis for the NRC-approved Fire Protection Program. This may be accomplished by S referencing the documents which define the licenseo's Fire Protection Program as identified in the NRC 's Safety Evaluation Reports.

OUAD CITIES E_OSITION: The required inforr.ation has been incorporated into UFSAR Section 10.6 for Quad Cities Units 1 g and 2.

2) GENEBlg LETTER 88-12: The Limiting Conditions for Operation (LCO) and Surveillance Requirements associated with fire detection systems, fire suppression systems, fire barriers, and the administrative controls that address fire brigade staffing would be relocated from the TS. An inder of these

$ specifications is provided in Enclosure 2. The existing administrative controls related to fire protection audits are to be retained in TS. Also, any specifications related to the capability for safe shutdown following a fire, e.g. see Item 8(j) in Enclosure 1 to Generic Letter 81-12, are to be retained in TS.

I OUAD glIIRS POSITION: The proposed changes to Section 3.12/4.12 and those contained in attached Section 6.0 implement the requirements of GL 88-12. Quad Cities Units 1 and 2 TSs do not contain requirements concerning the capability for safe shutdown following a fire.

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. 3) QENERIC LETTER 1R-111 All operational conditions, remedial actions, and test requirements presently included in the TS for these systems, as well as the fire brigade staffing requirements, shall be incorporated into the Fire Protection Program. In this manner, the former TS requirements will become an integral part of the Fire Protection Program and changes subsequent to this amendment will be subject to the jk standard license condition. These remedial actions include shutdowns currently required by TS 3.0.3 when an LCO and its associated Action Requirements cannot be met. An example of such a requirement is the shutdown required for the loss of the fire suppression water system and failure to establish a backup water supply within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

k. QUAD CITIES RESPONSE: The Quad Cities Fire Protection Program (as described in UFSAR Section 10.6) has incorporated the TS requirements for the systems proposed to be relocated including TS shutdown reguirements. A copy of the UFSAR changes and Fire Protection Program Implementing procedures is attached to this amendment request, for information only.

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0 4; GENERig LETTER 88-12:, The standard fire protection licenso g condition in Generic Letter 86-10 must be included in the license. Any other current fire protection license conditions shall be removed. This license condition precludes changes to the approved Fire Protection Program without prior Commission approval if those changes would adversely affect the ability to achieve and maintain safe shutdown conditions in the event of a fire. The shutdown requirement that applies because of a ll failure to establish a backup water supply within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a loss of the fire suppression water system is an example of a Fire Protection Program requirement that would be subject to the license condition and could be changed in accordar.ce with the standard license condition. However, the staff believes that any change to the shutdown requirement would also require the implementation of extraordinary

) compensatory measures. Absent such extraordinary measures, changes to this requirement are likely to have an adverse effect on the ability to achieve and maintain safe shutdown in the event of a fire and, therefore, could not be made without prior Commission approval.

3 QUAD CITIES EQEITION: The proposed change to the Facility

> Operating Licenses for Quad Cities Units 1 and 2, described in the proposed changes for Section 3.12/4.12, includes the replacement of present Fire Protection license conditivn 3.F with the standard license condition from Generic Letter 88-10.

5) GENE. Rig LETTER 88-12: The Administrative Controls section of

} the TS shall be augmented to support the Fire Protection Program. This shall be accomplished by additions to two specifications. First, the Unit Review Group (Onsite Review Group) shall be given responsibility for the review of the Fire Protection Program and implementing procedures and the submittal of recommended changes to the Company Nuclear Review and Audit Group (Offsite or Corporate Review Group). Second, Fire Protection Program implementation shall be added to the list of elements for which written procedures shall be established, implemented, and maintained.

The Emergency Plan and the Security Plan were used as models to determine the appropriate administrative control for the N Fire Protection Program. These additions will provide J administrative controls for the Fire Protection Program that are equivalent to those for other programs that are implemented by license condition. The enclosed marked pages of the Westinghouse Standard Technical Specifications (STS) serve as a model for the changes to the administrative controls. If the plant's TS differ from the STS, additions to

} the administrative controls for the Fire Protection Program should be proposed that are consistent witn the administrative controls for the Emergency and Security Plans.

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I QMAD QlTIES POSITION:

The Administrative Controls Section 6.0 of the Quad Cities Technical Specifications contains provisions that are s

! different from the STS. The Fire Brigade manning requirements l of present 6.1.C are deleted while corporate and plant designated responsibility for the Fire Protection Program are I retained. Training provisions for the Fire Brigade contained j in present 6.1.E are retained. The present Offsite Review and j Investigative Functions in 6.1.G.1 requiring review and audit functions for the Fire Protection Program and implementing procedures are retained. In accordance with GL 88-12 recommendations, the required review of the Fire Frotection l Program and implementing procedures is added to Section 6.1 G.2.a, Onsite Review and Investigative Function. Present Fire Protection Program inspections and audits required by 6.1.H are retained. Present Section 6.2, Plant Operating Procedures, contains the GL 88-12 recommendation for Fire Protection Program implementation and, thus, no changes are required for this section for implementation of Generic Letter I 88-12.

Item 2 The NRC issued Generic Letter 89/01 on January 31 1989, in order to allow the technical specification provis1ons for the Radiological Effluent Technical Specifications (RETS) to be b relocated to the Administrative Controls section of the technical specifications (programmatic requirements) and to the ODCM or PCP (procedural details). New programmatic controls for radioactive effluents and radiological environmental monitoring are relocated to Section 6.0 of the technical specifications to conform to the regulatory g requirements of 10 CFR 20.106, 40 CFR Part 190, 1C CFR 50.36a, and Appendix I to 10 CFR Fart 50. The proposed changes to Section 6.0 implement the recommendations contained in Generic Letter 89/01. Other minor administrative changes are proposed to Table 6.6-1 in order to correct technical specification references and to add the Explosive Gas Mixture Special Reporting requirement.

I Item 1 Present Monthly Operating Report requirementu in 6.6.A.3 include reporting changes to the ODCM and major changes to the radioactive waste treatment systems. The changes to the ODCM are required to be reported in the Semiannual Radioactive I Effluent Release Report in accordance with GL 89/01 requirements. The reporting requirements for major changes in the radioactive waste treatment systems are being placed in tne ODCM and PCP.

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O QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 0 6.0 ADMINISTRA"'IVE CONTROLS 6.1 ORGANIZATION, REVIEW, INVESTIGATION, AND AUDIT A. Onsite and offsite organizations shall be established for unit operation and corporate mana9omonte rosPectivelY- Tho onSite ^nd O offsite organizations shall include the positions for activities af fecting the safety of the nuclear power plant.

1. Lines of authority, responsibility, and O mmunication shall be established and defined for the highest management levels througn intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization harts, functional descriptions of department O 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,

'n Authority, Activities" and Section 6,

" Interdepartmental Relationships".

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

3. The Senior Vice President-Nuclear Operations shall have the corporate responsibility for a overall plant nuclear safety and shall take any V 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 perform 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.

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QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 O B. Deleted.

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The in shift Figure manning for the station shall be as shown 6.1-3. The Operating Assistant Superintendent, Operating Engineer, Shift Engineers, and Shift Foremen shall have a Senior Operator's License. The Fuel i ) 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 Superintendent will be responsible for implementation of g the Fire Protection Program.

D. Qualifications of the station management and operating staff, excluding the Health Physics Services Supervisor and the Radiation Protection and g Chemistry Technicians, shall meet minimum acceptable levels as described in ANSI N18.1, " Selection and Training March 8, of Nuclear Power Plant Personnel", dated 1971. The Health Physics Services '

Supervisor or the Lead Health Physicist shall meet the requirements Regulatory Guide of radiation protection manager of 1.8. The individual filling the g position of Technical Superintendent shall meet the minimum acceptable level for " Technical Manager" as described in Section 4.2.4 of ANSI N18.1-1971. The Shift Control Room Engineer shall have a bachelor's degree or equivalent in a scientific or engineering g discipline and with and response specific training in plant design, analysis of the plant for transients and accidents.

The Radiation Protection Technicians shall have successfully completed the Protection Technician training established Radiation Chemistry program. The I Technicians shall have successfully completed the training program.

established Chemistry Technician Both shall have at least a total of one year of radiation protection general power plant, chemical, or experience, or equivalent training. In addition, the Radiation Protection I Technicians shall meet the criteria for " Individuals Qualified in Radiation Protection Procedures", as described in the D.L. Ziemann (NRC) letter to R.L.

Bolger (CECO) dated March 15, 1977. The Radiation Protection or Chemistry Technician training programs consists of the following:

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1. Satisfactory completion of an academic program.

Topics of these courses include mathematics, nuclear physics, radioactive decay, chemistry, sampling techniques, reactor coolant parameters, radiation exposure, shielding, O biological offects of radiation exposure, radiation survey techniques, personnel monitoring, and emergency procedures, as appropriate for their area.

2. Satisfactory performance on a comprehensive 0 examination following completion of academic training.

3. On-Shift training under the supervision of a qualified Radiation Protection or Chemistry Technician.

O 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 3, 1971.

O A training program for the fire brigade shall be maintained under the direction of the Station Fire Marshal and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 except that training sessions shali be at least quarterly.

F. Retraining for licensel operators, senior operators, O and senior operators - (limited) shall be conducted at intervals not exceeding 2 years.

G. The Review and Investigative Function and the Audit Function of activities affecting quality during facility operations shall be constituted and have 3 the responsibilities and authorities outlined below:

1. The Superintendent of'the offsite Review and Investigative Function shall be appointed by the Manager .of Ouality Assurance / Nuclear Safety 3 (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 U. the areas of Quality Assurance and Nuclear 6.1-3

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O I QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 lO promulgated through a Safety. Policy is

.! central policy committee directed by the

! Manager of QA/NS. The Manager of QA/NS has tho-i responsibility for the performance of periodic audits of each nuclear station and corporate l

Q departments to determine that QA/NS policy is 4

being carried out,

a. Offsite Review and Investigative Function

{ The Superintendent of the Offsite P.eview lO and Investigative runction shall: (1)-

- provide directions for the review and i investigative function and appoint a l

senior participant to provide appropriate l direction, (2) select each participant for i thie function, (3) select a complement of

' m re than one participant who collectively "O 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 g findings and recommendations developed by personnel performing the review and 4 investigative function, (5) approve and

report in a timely manner all. findings of __

l noncompliance with NRC requirements to the I

Station Manager, Vice President-BWR Operations, Manager of QA/NS, Assistant f

I Vice President ;(AVP) -Quality Programs and Assessment, and. the Senior- Vice

, President-Nuclear Operations. During l'

periods when the Superintendent of Of fsite Review and Investigative Function _'is .

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unavailable, responsibility _

he= shall designate this to an established '

l alternate, who estisfies the' formal training and expe: .ence requirements - for

. -the Superintendent of.the Offsite Review and Investigative. Function. The responsibilities of the personnel perf orming this _ function are ' stated below.

The Offsite Review and- Investigative Function shall review:

'(1) The safety evaluations for (1)

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l changes to procedures, equipment, or systems as described in the safety 6.1-4 1

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DPR-29 & DPR-30

!O j analysis report and (2) tests or i experiments completed under the I provision of 10 CFR 50.59 to verify that such actions did not constitute 4 an unreviewed safety question.

5 0 Proposed changes to the Quality i Assurance Program description shall j be reviewed and approved- by the i Manager of QA/NS.

I i (2) Proposed changes to procedures,

'O equipment or systems which involve an

! unreviewed safety question as defined in 10 CFR 50.59.

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

(4) Proposed changes in Technical Specification NRC operating licenses.

(5) Noncompliance with NRC requirements or, of internal proceduros or 3 instructions causing nuclear safety significance.

(6) Significant operating abnormalities or deviations from normal and g expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function.

(7) REPORTABLE EVENTS.

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

(9)- Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such

-change.

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(10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station Manager, Vice President-BWR Operations, and AVP

$ Quality Programs and Assessment,

b. Station Audit Function The Station Audit Function chall be the responsibility of the AVP Quality Programs O and Assessment independent of BWR Operations. Such responsibility is delegated to the Nuclear Quality Programs Manager.

The Nuclear Quality Programs Managrtr shall O 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 O are covered within a period of 2 years or less as desigr.ated below.

(1) The conformance of facility operation to provisions contained within the Technical Specifications and O applicable license conditions at least once per year.

(2) The adherence to proceduren, training and qualification of the station staff at leact once per year.

O The results of actions taken to i (3) l correct deficiencies occurring in facility equipment, structures, systems, or methods of operation that affect nuclear safety at least once g per 6 months.

l (4) Tne performance of activities required by the Quality Assurance Program to meet the Crite'ria of g Appendix "B" to 10 CFR 50.

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(5) The Facility Emergency P.lan and implementing procedures at least once per year.

(6) The Facility Security Plan and O implementing procedures at least once per year.

(7) The onsite and offsite reviews.

(8) The Facility Fire Protection Program

'O and implementing procedures at least once per 24 months.

(9) The radiological environmental monitoring program and the results thereof at least once per 12 ranths.

O (10) The ODCM and implementing procedures at least once per 24 months.

(11) The PCP and implementing procedures for solidification of radioactive O waste at least once por 24 months.

(12) Report all findings of noncompliance with NRC requirements and recommenda-tions and results of each audit to the Station Manager, Manager of O QA/NS, AVP Quality Programs and Assessment, Vice President-BWR Operations, the Senior Vice President

-Nuclear Operations, and the Chief Operating Officer.

O c. Authority The Manager of QA/NS reports to the Chief Executive Officer. The Manager of QA/Nb has the authority to order a unit shutdown or request any other action which he deems g necessary to avoid unsafe plant conditions.

The AVP Quality Programs and Assessment reports to the Senior Vice President-Nuclear Operations. The AVP Quality g Programs and Assessment has the authority to recommend a unit shutdown or request 6.1-7 0

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QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30

~O 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.

O

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

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

.O e. Procedures Written administrative procedures shall be prepared and maintained for the offsite Review and Investigative function described in Specifications 6.1.G.1.a.

O Those procedures shall cover the I

following:

(1) Content and method of submission of l presentations to the Superintendent i of- the Offsite Review and lC Investigative Function; (2) Use of committees and consultants.

(3) Review and approval.

l

!O (4) Detailed listing of items to be reviewed.

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

(6) Determining satisfactory completion O cf action required based on approved findings and recommendations reported 6.1-8 l

O

9 QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30

O by personnel performing the review and investigative function.

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

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

9 (2) Individuals performing the Review and Investigative Function shall possess a minimum formal training and experience as listed below for each discipline.

9 (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

,g plant operations.

6.1-9 O

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

O QUAD CITIES LNITS 1 & 2 DPR-29 & DPR-30 O

(c) Utility Operations Engineering graduate or equivalent with at least 5 years of experience in utility

'O operation and/or engineering.

(d) Power Plant Design Engineering graduate or equivalent with at least 5 years

.O of experience in power plant design and/or operation.

(e) Reactor Engineering Engineering graduate or

=O 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

0 required.

(f) Radiological Safety Engineering grac'ste or equivalent with at 1%st 5 years O of experience in radiation control and safety.

(g) Reactor Safety Analysis Engineering . graduate or

O equivalent, with at least 5 years of experience in nuclear engineering.

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

O 6.1-10 0

D QUAD CITIES UNITS 1 & 2 DPR-39 & DPR-30

, (i) Metallurgy Engineering graduate or equivalent with at least 5 year of experience in the metallurgical field.

l

[ (3) The Superintendent of the Offsite l Review and Investigative Function

! shall have experience and training which satisfy ANSI N18.1-1971 i

requirements for plant managers.

k 2. The Onsite Review and Investigativ6 Function j shall be supervised by the Station M nager.

I i

a. Onsite Review and Investigative Function The Station Manager shall: (1) provide I

direction for the Review and Investigative Function and appoint the Technical Staff Supervisor, or other comparably qualified individual as a senior participant to provide appropriate directions; (2) 8 approve participants for this function; (3) assure that a complement of more than one participant who collectively possess background and qualifications in the subject matter under review are selected

'_ to provide comprehensive interdisciplinary D

review coverage under this function; (4) independently review and approve the findings and recommendations developed by personnel performing the Review and

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

& responsibilities of the personnel performing this function are stated below:

(1) Review of (1) procedures required by Specification 6.2 and changes thereto and (2) any other proposed procedures S

6.1-11 l

b L__ __ _ . . . - . - . . . -

l D

QUAD CITIES UNITS 1 1 ?

DPR-29 & DPR-30 or changes thereto as determined by O the Station Manager to affect nuclear safety.

(2) Review of all proposed tests and experiments that affect nuclear safety.

(3) Review of all proposed changes to the Technical Specifications.

(4) Review of all proposed changes or modifications to plant systems or O equipment that affect nuclear safety.

(5) Investigation of all noncompliance with NRC requirements and shall prepare and forward a report covering evaluation and recommendations to O prevent recurrence.

(6) Review of facility operations to detect potential safety hazards.

(7) Performance of special reviews and O investigations and reports thereon as requested by the Superintendent of the Offsite Review and Investigative Function.

(8) Review of the Station Security Plan C and shall submit recommended changes to the Director of Corporate Security and the AVP Quality Programs and Assessment in lieu of the distribution in accordance with 6.1.G.2.C.(1).

D (9) Review of the Emergency Plan and station implementing procedures and identification of recommended changes.

) (10) Review of REPORTABLE EVENTS and actions taken to crevent recurrence.

(11) Review of any unplanned on-site release of radioactive material to the environs, including the D

6.1-12

)

)

QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 y preparation and forwarding of reports covering evaluation recommendations and disposition of the corrective action to prevent recurrence to the Vice President-BWR Operations and to l

the Superintendent of the Offsite Review and Investigative Funct.on.

(12) Review of changes to the PCP and ODCM, and major changes to the radwaste treatment systems.

j g (13) Review of the Fire Protection Program and implementing procedures and the i

i submittal of recommended changes to the Offsite Review and Investigative l Function.

I h, b. Authority j The Technical Staff Supervisor is responsible to the Station Manager and shall make recommendations in a timely manner in all areas of review, investigations, and quality control phases

' of plant maint( 3ance , operation, and administrative procedures relating to facility operations and shall have the authority to request the action necessary 4

I to ensure compliance with rules, I regulations, and procedures when in his opinion such action is necessary. The Station Manager shall follow such recommendations or select a course of action that is more conservative regarding safe operation of the facility. All auch disagreements shall be reported k immediately to the Vice President-BWR j Operations and the Superintendent of the Offsite Review and Investigative Function,

c. Records I

(1) Reports, reviews, investigations, and recommendations prepared and performed for specification 6.1.G.2.a shall be documented with copies to

" the Vice President-BWR Operations, the Superintendent of the Offsite

] 6.1-13

, t

3 QUAD CITIT.S UNITS 1 & 2 DPR-29 & DPR-30 g Review and Investigative Function, the Station Manager, and the AVP Quality Programs and Assessment.

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

d. Procedures Written administrative procedures shall be prepared and maintained fot' conduct of the O "*it* R*Vla" 8"d I"V"*t195tiV" f"""ti "-

These procedures shall include the following (1) Content and method of submission and presentation to the Station Manage

-O Vi e Pre 8ident BWR Perations, aL.

the Superintendent of the offsite Review and Investigative Function.

(2) Use of committees when necessary.

(3) Revi W and approval.

O (4) Detailed listing of items to be reviewed.

(5) Pracadures for administration of the quality control activities.

)

(6) Assignment of responsibilities.

o. Personnel (1) The personnel performing the Onsite

4) Review and Investigative Function, in addition to the Station Manager, shall consist of parsons having expertise int a) nuclear power plant technology, 13 b) reactor operations, c) reactor engineering, d) radiological safety and chemistry,. . L e) instrumentation and control, and f) mechanical and electric systems.

6.1-14

O

,---r+ ..,,yr.-. .y.-e , e, ,-.w. -w. ,-- ,,-.......ymv. ,,.- m -. ..---v+c-e.~me.,wvve,---%.-*

QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 O (2) Personnel performing the Onsito Review and Investigative Function shall meet minimum acceptablo levels as described in ANSI N18.1 1971, I

Sections 4.2 and 4.4.

H. Firo Protection Program An indopondent fire protection and loss nrov6ntion program inspection and audit shall be r. 'ormed at least onco por 12 months utilizing eit!..t q.lalified offsito licenseo personnel er an outside fire

, protection firm.

An inspection and audit of the fire protection and loan provention program shall be performed by a qualified outsido firo consultant at least once por 36 months.

B 8

9 i

e D

D 6.1-15 D

l .

_ _ _ _ _ _ - _ - _ ~

10 1

i QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 8 MINIMUM SHIFT MANNING CHART l

j con 0!floa of one valt i (no tut) in licoss Unitt 2 AbOve Cold I Listelt 1n11981 futi 4048tel CO l d thW 199* er or Owrtrig 8tfwelleg Befueling thW10own $huteown j CategDry iO 50 ..,

Optrator i 1 2 titemit i

] ~

! Operator 2 2 3 j Littele i 1 l l 840. Prot. Men Rom *Licenseg (45 Atewirt0) t I l

f thtft techntca) sont Alguired i Avvisor sont teevtres e

C0m01110e Of itC040 Unli (06 Unit et Met Shutfown or et Powerl

{Q Cei shot... Or as.,t Coi.

tic.eit intii.i ruti 6...in, 1 Dr Ovring Refut1teg 8tfveling Shuteown Shutcown Cettgery J

1entor' Operato*

Ltcente i 2 2 L

O -Dete. tor-Littalt 3 3 3

~

tag. Prot. Man i t i 60makennt0 ). (&$ Stquift0) ) 4

$ntft tecnnical ' '

O ,

C0holfl04 Of SIC 0mg unti _

i (Dat unit at Cold shutsown or strueltng shutdown) tittent inttta) fus) toscing Cole lautpown or ocet Cold Cattgery or Ovring tefueling Af f ytling Shut 00ia lhwtcown lator' Operator Littelt  ! 'l 2 Operator' 3 2 3

-titemnt tag. Prot. Man i i 1 3 oe.tictated 3. i., St.w,,te, i

i

$hift Technital I adviser neee Atautet0 nome atowitti individ Ovring initial f wt1 lossing or during 4f woung.

' ,AllWPWS 44Chont seni. val 16 lit 4 Alt 0 on f aCh f at titty., toginter mmitt0 uit Sti .m io,te,ile rots h. .ung.

g

1. $htf t tet* ttmpolition edy be 1868 Inen tre eintpum regutrementi f or 4 perted Of time not to tattt0 2 howel th or0er to attont'ios4.t uetitectes 4Dichte of on Owty thif t tres armetr$ provided intecielt attion %l Leben te rettert int Shif t trte tort 05ttion to withth the mintsum Fttutrementi Of figVrt 6.la). >

w e I rL .1 -16 3 l a

O QUAD CITIr,S Ul4ITS 1 & 2 DPR-29 & DPR-30 0 6.2 PLA!1T OPERATI!1G PROCEDURES AllD PROGRAMS A. Detailed written procedures, including applicable checkoff lists covering items listed below shall be prepared, approved, and adhered to:

1. 11ormal startup, operation, and shutdown of the f

reacto", and other systems and components involv: rig nuclear safety of the facility.

2. Refueling operations.

l

1. 3. Actions to be taken to correct specific and

! foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary system leaks, and abnormal reactivity changes.

G 4. Emergency conditions involving potentiat or actual reluse of radioactivity - " Generating Station Emergenej Plan" and station emergency and abnormal procedures.

5. Instrumentation operation which could have an G effect on the safety of the facility.

6. Preventive and corrective maintenance operations which could have an effect on the safety of the facility.

3 7. Surveillance and testing requirements.

8. Tests and experiments.

9. Procedure to ensure safe shutdown of the plant.

} 10. Station Security Plan and implementation procedures.

11. Fire Protection Program implementation.

ODCM 1mplementation.

12.

I

13. PCP implementation.

14. Working hours of the Shift Engineer, Shift Control Room Engineer, Shift Foremaa, and the 11uclear Station Operator job classifications g such that the heavy use of overtime is not 6.2-1 B

O QUAD CITIES UNITS 1&2 DPR-29 & DPR-30 0 routinely required.

B. Radiation control procedures shall be maintained, made available to all station personnel, and adhered to. The procedures shall shew permissible radiation O exposure and shall be consistent with the requirements of 10 CTR 20. This radiation

] protection program shall be organized to meet the requirements of 10 CFR 20.

1 1 C. 1. Procedures for items identified in

' Specification 6.2. A and 6.2.B and any changes

O to such procedures shall be reviewed and approved by the Technical Staff Supervisor, an Superintendent or the Technical i Assistant Superintendent, and department head responsible for the activity performed. At least one person approving each of the above procedures

'O shall hold a valid senior operator's licence.

In addition, those procedures and changes j thereto must have authorization by the Station Manager before being implemented.

i

2. Work and instruction type procedures which

O' implement approved maintenance or modification procedures shall be approved and authorized by the Maintenance Assistance Superintendent where 4 the written authority has been provided by the i Station Manager. The Maintenance Modification 4 procedure" utilized for safety-related work O shall be so approved only if procedures referenced in the " Maintenance Modification

! Procedure" have been approved as reyd red by 6.2.A. Procedures which do not fall within the i requirement of 6.2. A or 6.2.B may be approved -

by the Department Heads.

D. Temporary changes to proceduren 6.2.A and 6.22B above may be made provided:

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

2. The change is- approved by two members of- the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

O 6.2-2

)

^h6WW9 W kM)@+1L W lC 3

Q4

,1; QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 i

j 3. The chango is documented, reviewed by the Onsite Review and Investigative Function, and approved by the Station Manager within 14 days of implementation.

t E. Drills of the emergency procedures described in g Specifitation 6.2. A shall be conducted in accordance a with the GSEP manual.

j F. Radioactive Effluent Controls Program i

l A program shall be provided conforming with 10 CFR 50.36a for the control of radioactivo effluents and

3 Ior maintaining the doses to MEMBERS OF THE PUBLIC i from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedia) actions y to be taken whenever the program limits are exceeded. The program shall include the following elements

1. Limitations on the OPERABILITY of radioactive liquid and gaseous monitoring y instrumentation including surveillance tests and sotpoint determination in accordance with the methodology in the ODCM.

2. Limitations on the concentrations of radioactive material released in liquid I

ef fluents to UNRESTRICTED AREAS conforming 1

to 10 CFR Part 20, Appendix B, Table II, Column 2.

3. Monitoring, sampling, and analysis of radioactive liquid and gaseous offluents I

in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM.

4. Limitatinns on the annual and quarterly doses oc dose commitment to a MEMBER OF I THE PUBLIC from radioactive materials in liquid ef fluents released from each unit

';o UNRESTRICTED AREAS conforming to Appendix 1 to 10 CFR Part 50.

'b 6.2-3 1

-?

w___. . _ 1

O  :

i QUAD CITIE9 UNITS 1&2 DPR-29 & DPR-30 O s. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the rnethodology and parameters in the ODCM at least every 31 days.

O

6. Liraitations on the OPERABILITY and use of the liquid and gaseous 2ffluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the O projected doses in a 31-day period would exceed 2 porcent of the guidelines for the  ;

annual dose-or dose commitment conforming ,

to Appendix I to 10 CFR Part 50.

7. Limitations on the dos.e rate resulting O from radioactive material released in gaseous ef fluents to areas beyond the SITE BOUl1DARY conforming to the doses associated with 10 CFR Part 20, . Appendix B, Table II, Column 1.

O 8. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50.

O 9. Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8-days in gaseous O ef flu nts released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50.

10. Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due t releases -of radioactivity and to O radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

O-6.2-4 O

O QUAD CITIES Ul1ITS 1 & 2 DPR-29 & DPR-30 0 G. Radiological Environmental Monitoring Program A progrcm shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) reprocentative measurements radioactivity in the highest o of potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conf orm to the guidance of Appendix I to 10 CFR part 50, and (3) include the following:

O

1. Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM.

O A Land Use Census to ensure that changes in the 2.

use of areas at and beyond the SITE BOU!1DARY are identified and that modifications to the monitoring program are made if required by the results of this census, and O 3. Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the qu lity assuran program for envircamental O monitoring.

O D

D 6.2-5 8

l ---

O QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 0 6.3 REI'ORTABLE EVENT ACTION A. The following actions shall be taken for Reportable Events:

1. The Commission shall be notified and a report O submitted pursuant to the requirements of Section 50.73 of 10 CFR Part 50.

2. Each Reportable Event shall be reviewed by the Onsite Review Committee, and the results of O this review shall be submitted to the Offsite Review and Investigative Funct4.on and to the Vice President-BW Operations.

O O

O O

1 3

6.3-1 3

- = _ . - _ _ _ . - -

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

i lO l

2 QUAD CITIES UllITS 1 &2 i DPR-29 & DPR-30 .

'O ACTIOli TO BE TAKEli Ill T!!E EVEllT A SAFETY LIMIT IS EXCEEDED

, 6.4 1 i

k If a SA. fY LIMIT is exceeded, the reactor shall be shut i down im.aed i a tely , and reactor operation shall not be i resumed until authorized by the liRC. The conditions of ,

!g shutdown shall be promptly reported to the Vice President

-BWR Operations or his designated alternato. The incident i l shall be reviewed pursuant to Specifications 6.1.G.1.a and 1 6.1.G.2.a and a separate report for each occurrence shall

]

be prepared in accordance with Specification 6.3.A.1.  ;

~  ;

1

'O i

1 l

.O s

I 4

a

=O 1

1 i

i T

D D-D 6.4-1 D.

O QUAD CITIES UllITS 1 & 2 DPR-29 & DPR-30 0 g,9 PLANT OPERATING RECORDS A. Records and/or logs relative to the follcwing items shall be kept in a manner convenient for review and shall be retained for et least 5 years:

O 1. Records of normal plant eperation, including power levels and periods of operation at each poWor level;

2. Records of principal maintenance activities, including inspection and repair, regarding 0 principal items of equipment pertaining to i nuclear safety;

3. Records and reports of REPORTABLE EVENTS and SAFETY LIMIT occurrences; O 4. Records and periodic checks, inspection and/or calibrations performed to verify that the surveillance requirements (see Section 4 of these specifications) are being met (all equipment failing to meet surveillance requirements and the corrective action taken O shall be recorded);

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

1. 6. Records of radioactive shipments;

7. Records of physics tests and other tests pertaining to nuclear safety; I

j 8. Records of changes to operating procedures; le

9. Shift engineer's logs; and '

10. Byproduct material inventory records and source l leak test results.

O 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; 8

6.5-1 S

O QUAD CITIES UNITS 1& 2 DPR-29 & DPR-30 0

2. Changes made to the plant as it is described in the SAR;

3. Records of new and spent fuel inventory and assembly histories; O

4. Updatod, corrected, and as-built drawings of i the plant;

5. Records of plant radiation and contamination

. surveys;

!O

6. Records of offsite environmental monitoring surveys;

7. Records of radiation exposure for all plant personnel, including all contractors and O visitors to the plant, in accordance with 10 CFR 20;

8. Records of radioactivity in liquid and gaseous wastes released to the environment; 3 9. Records of transient or operational cycling for those components that have been designed to ope ate safely for a limited number of transient or operational cycles;

10. Records of individual staff members indicating 9

qualifications, experience, training, and retraining;

11. Inservice inspections of the reactor coolant system; f 12. Minutes of meetings and results of reviews and audits performed by the Offaite and Onsite Review and Audit Functions; and

13. Records for Environmental Qualification which are covered under the provisions of paragraph g 6.7.

14. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

0 6.s-2

O QUAD CITIES UllITS 1 & 2 DPR-I9 & DPR-29 G.6 REPORTI!1G REQUIREME!iTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the US lluclear g Regulatory Commission Document Control Desk with copics to the Regional Of fice and liRC Resident In;pector.

I A. Routine Reports

1. Startup Report 3 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been 8 manufactured by a difforent fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the SAR and shall in general include a description of

1. the measured values of the operating conditions or characteristics obtained during the test 1 program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described.

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

Startup reports shall be submitted within (1) 90 days following completion of the startup 3 test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the startup report does not cover all three events (i.e., initial criticality, completion of startup test 3 program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least overy three months until all throc events have been completed.

6.6-1

D QUAD CITIES UNITS 1 & 2 DPR-29 & DPR-30 D

2. A tabulation shall be submitted on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according 3 to work and job function (Note: this tabulation supplements the requirements of Section 20.407 of 10 CFR 20), e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste p processing, and refueling. The dose assignments to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the g aggregate, at least 80% of the total whole body dose roccived from external sources shall be assigned to specific major work functions.

3. Monthly Operating Report

, Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basic, to arrive no later than the 15th of each month following the calendar month covered by the report.

, 4. CORE OPERATING LIMITS REPORT l a. Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or

any remaining part of a reload cycle for

, the following:

(1) The Rod Withdrawal Block Monitor Upscale Instrumentation Setpoint for Table 3.2-3 of Specification 3.2.C and for Specification 3.6.J.

' (2) The overall average of the 20%

insertion scram time data for Specification 3.3.E.

(3) The AVERAGE PLANAR LINEAR HEAT GENERATION RATE ( APLHGR) for I

Specification 3.5.M.

6.6-2 6

__ J

O QUAD CITIES UllITS 1 & 2 DPR-29 & DJ)R- 3 0 O (4) The LINEAR HEAT GENERATION RATE (LHGR) for Specification ,.5.N.

(5) The MI!1IMUM CRITICAL POWER RATIO (MCPR) for Specification 3.5.0 and 3.6.J.

(6) The K, core flow MCPR adjustment i factor for Specification 3.5.0.

s

b. The analytical motnods used to determine the core operating limits shall be those O previously reviewed and approved by NRC in NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel (latest approved revision).

c. The core operating limits shall be 3 determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis O are met.

d. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to 9 the NRC Document Control Deck with copies to the Regional Administrator and Resident Inspector.

j B. Unique Reporting Requirements 9 1. Semiannual Radioactive Effluent Release Report The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and 9 July 1 of each year. The report shall include a summary of the quantities' of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in

$ conformance with 10 CFR 50.36a and Section 6.C 1 8

n .

D QUAD CITIES Ul4ITS 1 & 2 DPR-29 & DPR-10 9

IV.D.1 of Appendix I to 10 CFR Part 50. A single submittal may be made for a multi-unit station. The submittal should combine thone sections that are common to all units at the station.

'3

2. Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the unit g during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries,

interpretations, and analysis of trends of the recults of the Radiological Environmental i V.onitoling Progran for the reporting period.

y The material provided chall be consistent with the objectives outlined in (1) the ODCM and (2)

Sections IV. B. 2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

3. Special Reports Special Feports shall be submitted as indicated in Table 6.6-1.

B

.x 1 i I

D D

6.6 ;  !

l

J

.O

, QUAD CITIES UllITS 1 & 2 DPR-29 & DPR-30 iO

TABLE 6.6-1

! SPECIAL REPORTS Description Reference Submittal Date

!Q

a. Secondary containment 4.7.I Upon completion of .

Icah rate test 03 each test. l

b. Summary status of fuel 1.1 Bases After each performance refueling outage.

.O I

c.  !!aterials radiation 4.6.B.3 After each specimen ,

surveillance specimens removal and comple-  !

tion of analyses.

g d. Radioactive Source Leak 4.8,0 Annual report.

Testing (2) days

~

e. Special Eff3uents ODCM 30 following Reports occurrence.

f. Explosive Gas Mixture - 3.8.A 30 days following O inoperable recombiner occurrence.

'O

Ro19.a l (1) Each integrated leak rate test of the secondary

! containment shall be the subject of a summary technical report. This report should include data on the wind

'g speed, wind direction, outside and inside temperatures during the test, concurrent reactor building pressure, and emergency ventilation flow rate. The report shall also include analyses and interpretations of those data which demonstrate compliance with the specified leak rate i limits.

(2) This report is required only if the test reveal the presence of the 0.005 microcuries or more of removable contamination.

1 0

6.6-5 2

O

f O

QUAD CITIES UllITS 1&2 DPR-20 & DPR-30

?

O 6.7 E!4VIRollME!3TAL QUALIFICATI0!l  !

) A. All safoty-related cloctrical equipment in the i facility shall be qualified in accordance with the j provisions of: Assistant of Operating Reactors i

~

I "Guido11nos for Evaluating Environmental Qualification of class IE Electrical Equipment in

'O Operating Reactors" (DOR Guidelines); or, NUREG-0588 l

" Interim Staff Position on Env.t ronmental Qualification of Safety-Related Electrical Equipment", December 1979. Copios of these documents are attached to Order for Modification of jQ Licenses DPR-29 and DPR-30 dated Octobor 24, 1980.

B. Complete and auditable records must be available and maintained at t contral location which describe tho

,- onvironreanta) qualification method used for all

safety-related electrical equipment in sufficient detail to document the degree of compliance with the

" O DOR Guidelines or llUREG-0588. Such records should i be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.

O

'O l

O ,

i.

f 0

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6.7-1 3

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

. -.- .- - . - _ - . . . - . . - . _ . . - . - -.- = - - _ _ - . . . _ _ - - - _ - . . -

O QUAD CITIES Ul1ITS 1 & 2 DPR-29 & DPR-30

'O 6.8 orFSITE CALCULATIO!1 MAliUAL (ODCrt) l 1

4 A. Changes to the ODCM:

l l 1. Shall be documented and records of reviews g perforraed shall be retained as required by

}

Specification 6.5.B.14. This documentation i

shall contain: .

k

a. Suffi. pent information to support the j change together with the appropriate g analyses or evaluations justifying the i change (s) and I

) b. A determination that the change will maintain the level of radioactive effluent

control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50 and not adversely impact the accuracy or reliability of offluent,

]

l dose, or setpoint calculations.

I 2. Shall become offective after review and

_g acceptance by the onsite review function and the approval of the Plant Manager on

)

J the date specified by the Onsite Review and Investigative Function. ,

3. Shall be submitted to the Commission in the form of a complete, legible copy.of O the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change chall be identified by markings in the margin of 3 the affected pages, clearly indicating the area of the - page that was changed, and shall indicate the date (e.g. , month / year) the change was implemented.

)

6.8-1 D

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l O I i

QUAD CITIES Ul11TS 1 & 2 DPR-29 & DPR-30 0

6.9 PROCESS CONTROL PROGRAM (PCP)

A. Changes to the PCP:

1. Shal) be documented and records of reviews O performed chall be retained ao required by Specification 6.5.B.14. This documentation shall contain:

a. Sufficient information to support the change together with the appropriate analyses or O evaluations justifying the change (c) and

b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

O 2. Shall become effective after review and acceptanco by the onsite review function and the approval of the Plant Manager.

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9 6.9-1 9