Text

Amends 100 & 97 to Licenses DPR-29 & DPR-30,respectively, Incorporating Numerous Changes to Tech Spec Section 6, Administrative Controls
	ML20210P201
Person / Time
Site:	Quad Cities
Issue date:	02/02/1987
From:	Zwolinski J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20210P210	List: ML20210P201; ML20210P295;
References
	NUDOCS 8702130331
	Download: ML20210P201 (57)
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g UNITED STATES

.8 NUCLEAR REGULATORY COMMISSION o

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I WASHINGTON, D. C. 20855 C0W90NWEALTH EDISON COMPANY AND 10WA-ILLINOIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 100 License No. DPR-29 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated February 17, 1983, as supplemented and superseded August 24, 1984 and January 20, 1986, respectively, Act'of 1954, as amended (the Act) quirements of the Atomic Energy complies with the standards and re and the Commission's rules and regulations set forth in 10 CFP Chapter I; B.

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

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health l

and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission'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 l

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 amend-ment, and paragraph 3.B of Facility Operating License No. DPR-29 is hereby amended to read as follows:

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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 100, are hereby incorporated in the-license. The licensee shall operate the facility in accordance I

with the Technical Specifications, t

3.

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

FOR THE NUCLEAR REGUl/T0lr' COMMISSION 2.

John A. Zwolinski, Director BWR roject Directorate #1 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 2, 1987

.v.

l ATTACHMENT TO LICENSE AMENDMENT NO.100 FACILITY!0 PEP.ATING LICENSE NO. OPR-29

DOCKET NO. 50-254 i

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 i

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vi vi 1.0-4 1.0-4 3.12/4.12-1 3.12/4.12-1 3.12/4.12-2 3.12/4.12-2 3.12/4.12-3 3.12/4.12-3 3.12/4.12-4 3.12/4.12-4 6.1-1 6.1-1 6.1-2 6.1-2 6.1-3 6.1-3 6.1-4 6.1-4*

6.1-5 6.1-5 6.1-6 6.1-6 Fig 6.1-1 Fig 6.1-1 Fig 6.1-2 Fig 6.1-2 Fig 6.1-3 Fig 6.1-3 6.2-1 6.2-1 6.3-1 6.3-1 6.4-1 6.4-1 6.5-1 6.5-1 6.6-1 6.6-1 6.6-2 6.6-2 6.6-3 6.6-3*

6.6-4 6.6-4 6.6-5 6.6-5 6.6-6 6.6-7 6.7-1 6.7-1

Pagination change only t

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8 QUAD CITIES DPR-29 4.8-2 Maximm Permissible Concentration of Dissolved or Entrained 3.8/4.8-21a l

Noble Gases Released from the Site to Unrestricted Areas in Liquid Weste 4.8-3 Radioactive Liquid Waste Sangling and Analysis

'3.8/4.8-22 Program s

4.8-4 Radiological Environmental Monitoring Program 3.8/4.8-24 4.8-5 Reporting Levels for Radioactivity Concentrations in 3.8/4.8-27 Environmental Samples 4.8-6 Practical Lower Limits of Detection (LLD) for Standard 3.8/4.8-28 Environmental Monitoring Program 4.11-1 Surveillance Requirements for High Energy Piping 3.11/4.11-3 Outside Containment 3.12-1 Fire Detection Instruments 3.12/4.12-7 3.12-2 Sprinkler Systems 3.12/4.12-8 3.12-3 CO2 Systems 3.12/4.12-8 3.12-4 Fire Hose Stations 3.12/4.12-9 6.6-1 Special Reports 6.6-5 v

Amendment No. 89,100

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QUAD-CITIES DPR-29 TECHNICAL SPECIFICATIONS APPENDIX A LIST OF FIGURES Number Title 2.1-1 APRM Flow Reference Scram and APRM Rod Block Settings 2.1-2 Deleted 2.1-3 APRM Flow Bias Scram Relationship to Normal Operating Conditions 4.1-1 Graphical Aid in the Selection of and Adequate Interval Between l

Tests 4.2-1 Test Interval vs. System Unavailability 3.4-1 Standby Liquid Control Solution Requirements 3.4-2 Sodium Pentaborate Solution Temperature Requirements 3.5-1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) vs. Planar Average Exposure 3.5-2 K factor 3.6-1 Minimum Temperature Requirements per Appendix G of 10 CFR 50 4.6-1 Chloride Stress Corrosion Test Results at 500'F 4.8-1 Locations of Fixed Environmental Radiological Monitoring Stress 6.1-1 Corporate Organization 6.1-2 Station Organization Chart 6.1-3 Minimum Shift Manning Chart i

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i Amendment No. S9, 100 9

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O QUAD-CITIES DPR-29 Y.

Shutdown - The reactor is in a shutdown condition when the reactor mode switch is in the Shutdown position and no core alterations are being performed.

1.

Hot Shutdown means conditions as above, with reactor coolant temperature grestri than 2120F 2.

Cold Shutdown means conditions as above, with reactor coolant temperature aquel to or less than 2120F.

Z.

Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question.

AA. Transition Boiling - Transition boiling means the regime between nucleate and film boiling. Transition boiling is the regime in which both nucleate and film boiling occur intermittently, with neither type being cospletely stable.

BB. Critical Power Ratio (CPR) - The critical power ratio is the ratio of that assembly power which causes some point in the assembly to experience i transition boiling to the assembly power at the reactor condition of interest i

as calculated by application of the GEXL correlation (reference EDO-10958).

CC. Minimum Critical Power Ratio (MCPR) - The miniaJm incore critical power ratio corresponding to the most limiting fuel assent)1y in the core.

DD Surveillance Interval - Each surveillance requirment shall be performed within the specified surveillance with:

f A maximum allowable extension not to exceed 255 of the surveillance a.

interval.

b.

A total maximum combined interval time for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surviellance interval.

EE. Fraction of Limiting Power Density (FLPD) - The fraction of limiting power density is the ratio of the linear heat generation rate (LHGR) existing at a given loction to the design LHGR for that bundle type.

FF. MaximJm Fraction of Limiting Power Density (WLPD) - The maxinun fraction of limiting power density is the highest value existing in the core of the fraction of limiting power density (FLPD).

I GG. Fraction of Rated Power (FRP) - The fraction of rated power is the ratio of core thermal power to rated thermal power of 2511 *th.

IM. Reportable Event - Any of those conditions specified in Section 50.73 to 10 CFR Part 50.

1.0-4 Amendment No. 6I.100

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. QUAD. CITIES DPR-29 3.12/4.12 FIRE PROTECTION SYSTEhiS 1.DtITING CONDITIONS FOR OPERATIONS SURVEILI.ANCE REQUIRDfE!CS Applicability:

Applicability:

Applies to the fire protection systems whenever the Applies to the periodic testing requimnents of the fire equipment or systems being protected are required to protection systems whenever the fire protection be operable.

systems are required to bp operable.

Objectiver Objective:

i To ensure that adequate protection assinst fires is To verify operability of the fue protection systems.

l gnaintained during all modes of facility operation.

SPECIFICATIONS A. Fire Detection Instrumentation A. Fire Detection Instrumentation

1. As a minimum,the fue detection instru.

1. Each of the

fire detection instrumenu inentation for each fae detection zone given by Table 3.121 sha!! be demon.

shown in Table 3.121 shall)e operable strated operable at least once per 6 at all times when equipment in that fue months by a channel functioral test.

detecuan zone is required to be operable.

2. All non supervised circuits shs!1 be

2. With the number of operab! Tre detec.

demonstrated operable once per month.

non instruments lyss than requeed by Table 3.121;

a. Perform an inspection of affected j

l rene, within I hour. Perform addi.

l tional inspecuens at least once per

' hour exceptin inaccesable areas.

b. Restore the inopeuble instrument (s) to operable status within 14 days, or prepare and submit a. report to the Commission pursuant to Specification j

6.3.A.1within the next 30 days out-liams the cause of the malfunction,

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the-action taken, and, the plans for l

restonns trw instrument (s) to oper.

able status.

3. 'the provisions of specification 3.0.A are not applicable.

l Amendment No. 72,100 3.12 4.12-1 1

QUAD CITIES DPR-29 B. FireSuppremienWaterSyssen B. Fire Suppenemon Water System

1. The Fire Suppresson Water System shan

1. The Fire suppresnon Water System shan be operable at all tirnes with; be demonstrated operable:

a. Two (2) high pressures pumps each

a. At less once per 31 days on a stag.

with a capacity of 2000 gym with gered test bans by sartag each pump their discharge aligned to the fire and operathgitforstisest 20 muutes suppresana header.

on recirculation flow.

b. Automatic hitiation logic for each

b. At Issa once per 31 days by verifying fire purnp.

that each valve (manual, power

Pented or autans@ h ee Bow

c. An operable flow path capable of Path k h h canct Wa.

taking maction frorn the Minassippi River and transferrms tbs water

c. At least once per year by performance through distribution piphs with oper.

of a symem flush.

able actionalnag control or isolaten y g, valves to the yard hydrant curb valves k

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and the front valve ahead of the water k d fd flow alarm device on each sprmkler, hose stand pipe, or spray system riser.

e. At least once per operstmg cycle

2. With fnoperable fire pumps or asociated water supply, restore the hoperable (1) By performmg a system func.

equipment to operable natus within 7 tional sest which includes l days, or prepare and submit a report to the Commission pursuant to Specifica.

l tion 6.3. A.1mthin the next 30 days out.

lining the plans and procedures to be used to provide for the loss of redundancy in th.s system.

3. With no Fire Suppression Water Sysem operable,within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ;

a. Establish a backup Fire Suppression Water System.

b. Notify the Commission purniant to j

Specification 6.3. A.1 outlining the actions taken, the cause of the b.

operability, and the plans and schedule for restorms the system to operable status.

4 If the requirements of Specification 3.12.B.3.a cannot be met,an orderly shut down shaU be trutasted, and the reactor sha!! be in a cold shut down condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I Amendment No. 6, 100 3.12/4.12 2

QUAD. CITIES DPR-29 simulated automatic actuation of the symem throughout its opera.

ting. sequence and verifymg that each automatic valve h the Dow path actuates to its correct position.

(2) By verifyhg that each pump develops at least 2000 spm at a

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system hand of 123 peig.

(3) Cycling each valve in the now path that is not testable dunng plant operation through at least one complete cycle of full travel, and

f. At least once per 3 years by perform.

ing flow tests of the system in accor.

dance with Chapter 5,Section II, NFPA Fire Protection Handbook.

C. SprinklerSystems C. Sprinkler Systems

1. The sprinkler systems given in Table I. At least once per year by cycling each 3.12 2 shall be operable at all times when testable valve in the flow path through at equipment in the areas spray /sprmkler least one complete cycle of full travel.

protected is required to be operable.

2.

Atleast once per operating cycle:

2. With a sprmkler. system inoperable,

s. A system functional test shall be per.

formed which includes simulated auto-establish back up fire suppression equip.

l me'nt and inspect the area twice per shift.

matic actuatan of the system and ymg that the summa

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3. Restore the system to operable status O'* P

l withm 14 days, or prepare and submit a met Poutbus.

aport to the Commission pursuant to l

Specification 6.3.A.1 within the next

b. The sythkler headers shall be in.

30 days outlining the cause of inoper.

spected to verify their integrity.

abairy, the action taken, and the plans

c. Each, nor21e shall be inspected to for testoreg the system to operable

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status.

3. At least once per 3 years by performing

4. 'the Provisions of Specificatien an air flow test through each open head 3.0.A are ret applicable.

spray / sprinkler header and verifying each open head spray / sprinkler nor.r.le is un.

obstructed.

i 3.12/4.12 3 Amendment No. 72, 100 l

QUAD LITit5 DPR-29 2 SY 5* 8 D. CO2 Systems D. CO

1. The CO Storage Tank shall have a mini.

1.

At least 6nce per 7 days the CO 380'38' 2

2 snum stand by level of 50 per:ent and a Tank level.and pressure will be verified.

snuumam pressure of 250 psig.

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2. The CO Systems given in Table 3.12 3 synem valves and associated dampers wdl 2

shall be operable.

be verified to actuate automatically and I* ^

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3. Specifications 3.12.D.1 and 3.12.D.2 to wrMow han ud nod, above apply when tae equipment in the areas given in Table 3.12.3 is required to be operable.

With a CO System inoperable, establish 4.

2 backup fire suppression equipment for the unprotected area (s) within I hour and inspect the area twice per shift.

3. Restore the system.to operable status within 14 days, or prepare and submit a report to the Commission pursuant to

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Specification 6.3.a.1 within the next 30 days outlining the cause of inoper.

abdity, the action taken, and the plans and schedule for restormg the system to operable status.

6. If actuated, the storage tank will be restored to greater than the minunum kwel within 48 huurs.

1 'lhe Provisions of Specification 3.0.A are not applicaole.

E. Fire Home Stations E. Fire Hase Stations

1. The Fire Hose Stations given in Table

1. At least once per 31 days,a visualinspec.

3.12-4 ahall be operable at all times tion of each fire hose station shall be when the equipment in the areas pro-made to assure all equipment is available tected by the fire bone is required to be at the station.

Perable.

2. At least once per operating cycle, the

2. With a hoie station inoperable,toute an hoie will be removed for inspect on and i

additional equivalent capacity hose to the teracked. Degraded gaskets i:i the coup.

unprotected area frem an operable hose lings will be replaced, station withm I hour.

3. At least once per 3 years,each hose sta.

3. 'rhe provisions of specification tion valve wal be partially opened to 3.0.A are not applicable, verify valve operability and no blockage.

4.

t least once per 3 years a hydrostatic sea w0l be conducted on each hose at a pressure at least $0 psig greater than the manmum pressure available at the huse station.

F Pesetration Fire Barriers F. Penetration Fire Baniers

1. All penetration fire barners protectml

1. Each eif the penettstion fire bart:er shall safety related areas shall be Witact except be verified to be intact by visual in.

as stated in Specification 3.12.F.2.

spection; Amendment No. 72, 100 3.12/4.12-4

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l guAD CITIES SPR-29 6.g ADMINISTRATIVE CONTROLS l

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6.1 GRGANIZATION. REVIEW. INVESTIGATION. Ane AUDIT A.

The Statten Manager shall have overall full-ttee responsibiltty for safe operation of the facility. During periods when the Station Manager is unavailable, he shall designate this responsitt11ty to an established alternate who satisfies the ANSI R18.1 of March 8. 1971 i

emperience requirements for plant manager.

l S.

The organization chart of the corporate management editch relates to the operation of this station and the normal functional ergentsatten chart for operetten of the statter.3re shoun in Figures 6.1-1 and 6.1-2. respectively.

C.

The shift meaning for the statten shall be as shown in Figure 4.1-3.

The Assistant Superintendent Operating. Operating Engineer. Shift Engineers, and Shift Foramen shall have a senter operato/s license. The Fuel Handling Foreman has a Itatted Senior Operator)

License. The Assistant Vice President and General Manager Nuclear Stattens en the corporate level has responsibility for the Fire Protectten Program. The Assistant Superintendent Maintenance will be responsible for taplementatten of the Fire Protection Program. A fire brigade of a least 5 mester shall be usintained on-site at all times.

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

3.

Sualificattens of the station management and operating staff. excluding the Rad-Chan supervisor and the Radiation / Chemical Technicians shall meet mintaun acceptable levels as described in ANSI N18.1. " Selection and Training of Nuclear Power Plant Personnel *, dated March 8. 1971. The Rad-Chem Supervisor er the Lead Health Physteist shall meet the requirements of radiation protection manager of Regulatory Guide 1.0.

The individual l

filling the position of Assistant Superintendent - Technical Services shall meet the minimum acceptable level for " Technical Manager" as described in Section 4.2.4 of Ams!

518.1 1971. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysts of the plant for transients and accidents.

The Radiation / Chemical Technicians shall have successfully completed the established Radiation / Chemical Techntetan training program, and shall have at least a total of one year of general power plant, chantcal, or radiation protection esperience, or equivalent training. The Radiation / Chemical Technicians shall meet the criteria for

Individuals Qualified in Radiation Protection Procedures", as described in the D. L. Ziemann (eRC) letter to R. L. Solger (CECO.) dated March 15. 1977. The Radiation / Chemical Technician j

training program consists of the following:

I 1.

Satisfactory completion of a 12-meek academic program. Tepics of this course include mathenettes. nuclear physics, radioactive decay, chemistry, samp11pg techniques, j

reactor coolant parameters. radiation esposure. shielding, biological effects of l

radiatten esposure, radiation survey techniques ptrsonnel monitoring, and emergency j

procedures.

2.

Satisf actory performance on a comprehensive examination following completion of acaemetc training.

3.

On-Shift training under the superviston of a qualtf ted Radiation / Chemical Technteten.

E.

Retraining and replacement training of Station personnel shall be in accordance with AN5!

f N18.1. "$ election 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 Station Fire Marshal and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 escept that training sessions shall be at least quarterly.

i F.

Retraining for Itcensed operators. senior operators, and senior operators (iteited) shall i

he conducted at intervals not esteeding 2 years.

C.

The Review and Investigative Function and the Audit Function of activities affecting quality during facility operations shall be constituted and have the responsittlilles and l

autherttles outilned below:

I 1.

The Supervisor of the Offstte Review and Investigative Function shall be appointed by 4

the Chatraen and President. The Audit Function shall be the responsibility of the l

Manager of Gua11ty Assurance and shall be independent of operations.

I 6.1-1 Amendment No. 74, 100 i

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Quad-CITIES DPR-2g I

l 4.

Offstte Review and Investigative Function The Superviser of the Offstte Review and Investigative Functlen shall (1) provide directions for the review and investigatiwfunction and appotnt a senter participant to provide appropriate direction (2) select each participant for this function. (3) select a templement of more than one parttelpent de collectively posses background and qualtf tcattens in the subject matter under review to provide camershensive interetscipitnery rewtow coverage under this functlen (4) sneapondently review and approve the findings and recommendettens developed by i

personnel performing the review and investigative functten. (5) approve and report se a tteely manner all findtags of noncespliance with mRC requirements to the Station Manager. Assistant Vice President and General Manager Suclear Stattens.

g nanager of Suality Assurance, and the Vice President of Butlear gperettens.

l suring porteds toten the Superviser of Offs 1to tevtom and Investigattwe Functten is unavailable he shall designate this responsiblitty to an established alternate, edge satisfies the formal training and espertence requirements for the Superviser of the Offstte Sovtew and Investigative Function. The responsitt11ttes of the personnel perferming th1s functien are stated below. The Offsite Review and Investigative Function shall review:

1) The safety evaluattens for (1) changes to precedures epigment, or systems as described in the safety analysts report and (2) tests er esperiments coupleted under the provtsien of 18 CFR 54.59 to verify that such actions did not constitute an unreviewed safety guestion. Proposed changes to the Quality Assurance Program descriptten shall be reviewed and approved by the Manager of Ouality Assurance.

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2) Proposed changes to procedures. egulpment er systems editch involve an unreviewed sarety westten as defined in le CFR 59.59.

3) Proposed tests or esperiments editch involve an unreviewed safety question as defined in le CFR $9.5g.

4) Proposed chaages in Technical Specification NRC operating licenses.

5) Wencomp11ance with NAC requirements, or of internal procedures. er instructions causing nuclear safety significance.

6) Significant operating abnerinalttles or deviations from normal and espected performance of plant egutament that affect nuclear safety as referred to it by the Onsite Review and Investigative Functten.

7) Reportable events.

1

0) All recognized indications of an unanticipated def tetency in sene aspect of design er operatten of safety-related structures, systens or components.

r

9) Review and report findings and receumendations regarding att changes to the Generating Stations Emergency Plan prior to the seplementation of such change.

10) Revt'ow and report findings and recommendations regarding all items referred by the Technical Staff Superviser. Station Manger. Assistant Vice President and l

General Manager nuclear Stations and Manager of Ouality Assurance.

I t.

Audit function The Audit Function shall te the respensttt11ty of the Manager of Quality Assurance independent of the Production Department. Such responsibility is delegated to the strector of Gua11ty Assurance for Operating and to the General Superviser Quality Assurance Maintenance for matntenance quality assurance activities.

Either shall approve the audit agenda and checklists, the findings and the report of each audit. Audits sha11 he performed in accordance with the Company Ovality Assurance Program and Procedures. Audits shall t,e performed to assure that safety-related functtens are covered within a perted of 2 years of less as designated below.

I I) Audit of the confermance of fact 11ty operetten to previsions contained within the Technical Specifications and app 1tcatie Itcense condittens at least once

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per year.

4.1-2 Amendment No. M, 100 i

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Quad-CITIES DPR-29

2) Audit of the adherence to procedures, training and qualification of the station staff at least once per year.

3) Audit of the results of actions taken to correct deficiencies occurring in f acility equipment. structures. systems, or methods of operation that affect nuclear safety at least once per 6 months.

4) Audit of the performance of activities required by the Ouality Assurance Program to meet the Criteria of Appendix *s* 10 CfR 50.

5) Audit of the Factitty Emergency Plan and implementing procedures at least once l

per year.

6) Audit of the Fact 11.ty security Plan and implementing precedures at least once per year.

7) Audit enstte and offstte reviews.

8) Audit of Facility Fire Protection Program and tuplementing procedures at Least l

ence per 24 months.

9) The radtological environmental monitoring program and the results thereof at least once per 12 senths.

It) The 00CM and taplementing procedures at least once per 24 months.

11) The PCP and taplementing procedures for solidification or radioactive waste at least once per 24 months.

12) Report all findings of noncomp11ance with mRC requirements and receumendations and results each audit to the Station Manager. Assistant Vice President and General Manager Nuclear Stations. Manager of Guellty Assurance. Vtte President of Nuclear Operattens and to the Esecutive Vice President of Construction.

Production, and Engineering.

c.

Authority The Manager of Ouality Assurance and the Supervisor of the Of f stte Review and l

Investigative Function reports to the Chairman and President. Elther the Manager of Gua11ty Assurance or the supervisor of the Offstte Revtew and Investigative Function has the authority to order unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions.

d.

escords

1) Reviews, audits. and roccamendations shall be documented and distributed as covered a 6.1.G.I.a add 6.1.G.1.b.

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

e.

Precedures Written senintstrative procedures shall be prepared and maintained for the offstte reviews and investigative functions described in spectf tcations 6.1.G.I.a.

Those procedures shall cover the following:

1) Content and method of submission of presentations to the Supervisor of the Offsite Review and Investigative function.

2) Use of committees and consultants.

3) Review and approval.

4) Detatted Itsting of items to be reviewed.

$) Method of (1) appotnting personnel. (2) performing revtews, investigations.

(3) reporting findings and reconnendations of reviews and investigations. (4) approving reports, and (5) distributing reports.

6) Determining satisfactory cespletion of action required based on approved findings and reconnendations reported by personnel performing the review and investigative function.

6.1-3 Amendment No. 45, 89, 100

OuaD-CIf!L1 DPR-It o

f.

Personnel

1) The persons, including consultants, performing the review and investigative function. in additten to the Superviser the Offstte Review and Investigative Functlen, shall have espertise in one or more of the following discip1tnet as appropriate for the subject er subjects being reviewed and investigated:

al nuclear power plant technology, b) reacter operattens, c) utt11ty operattens, d) power plant design, el reacter engineering.

f) rettelegical safety.

g) reactor safety analysts, h) instrumentatten and centrol.

1) estallurgy.

j) any other appropriate disciplines reptred by entes characteristics of the factitty.

2) Individuals perfereing the sevtew and Investigative Funciten sha11 possess a einlansa formal training and espertence as Itsted below for each discipitne.

a) Nuclear power Plant Technology i

Engineertng graduste er o p twalent with 5 years emportance in the nuclear power fleid design and/or operattens.

b) Reactor Operattens Enginearing graduate or equivalent with 5 years espertence in nuclear power plant operations.

j c) Utility Operattens l

Engineering graduate or equivalent with at least 5 years of espertence in j

utt11ty operatten and/or engineering, d) Power Plant Design i

Engineering graduate er equivalent with at least 5 years of esperience in power plant design and/or operetten, e) Reactor Engineering Engineering graduate er equivalent. In additten, at least 5 years of espertence in nuclear plant engineering, operetten, and/or graduate work in nuclear engineering er equivalent in reacter phystes is required.

f) Radtelogical Safety Engineering graduate er equivalent with at least 5 years of esperience in radiatten control and safety.

g) Aeactor Safety Analysts Engineering graduate or equivalent, with at least 5 years of espertence in nuclear engineering.

h) Instrumentation and Control Engineering graduate er equivalent with at least 5 years of espertence in instrumentation and centrol desten and/or operatten.

t) Meta 11urgy Engineering graduate or equtvalent with at least 5 years of espertence in the metallurgical field.

3) The Superviser of the Offstte Review and Investigative functlen shall have espertence and training unich satisfy ANSI Nig.1 tg71 requirements for plant managers.

6.1-4 Amendment flo. M. M, 100

QUAO-CITIES OPR-29 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 Staff Supervtsor, or other l

comparably qualtfied individual as a senior participant to provide appropriate directions. (2) approve participants for this function: (3) assure that a complement of more than one participant who collectively posses 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 recornwndations developed by personnel performing the Review and Investigative Function:

(5) report all findings of noncompliance with NRC requirements, and provide recommendations to the Assistant Vice President and General Manager Nuclear Stations and the Supervisor of the Offsite Review and investigative Function

and (6) submit to the Offstte Review and Investigative Function for concurrence in a timely manner.

those items described in $pecification 6.1.G.I.a which have been approved by the Onstte Review and Investigative Function.

The responsiblitties 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 or changes thereto as determined by the Station Manager to affect nuclear safety.

2) Review of all proposed tests and experiments that affect nu, clear safety.

3) Review of all proposed changes to the Technical Spectfications.

4) Review of all proposed changes or modifications to plant systems or 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 prevent recurrence to the A$ststant Vice President and General Manager Nuclear Stations and to the Supervisor of the Offstte Review and Investigative Function.

6) Revtew of facility operations to detect potential safety hazards.

7) Performance of special reviews and investigations and reports thereon as requested by the Supervisor of the Of fsite Review and Investigative Function.

8) Review of the Station Security Plan and shall submit recommended changes to I

the Assistant vtce President and General Manager Nuclear $tations.

I

9) Review of the Emergency Plan and station implementing procedures and shall j

submit recommended changes to the Assistant.Vice President and General Manager i

Nuclear Stations.

10. Review of reportable events and actions taken to prevent recurrence.

11. Revtew of any unplanned on-site release of radioactive material to the environs, including the preparation and forwarding of reports covering evaluation recommendattons and disposition of the corrective action to prevent recurrence to the Assistant Vice President and General Manager Nuclear

$tations. and to the Supervisor of the Offsite Review and Investigative Function.

12. Review of changes to the PCP and 00CM. and major changes to the radwaste treatment systems.

l Amendment No. 39, 89, 100 6.i-$

QUAO-CIf!ES OPR-29 i'

b.

Authertty

-The Technical Staff Superviser is responsitie to the Station Manager and shall I

make receumendettens in a timely menner in all area of review, investigations, and quality centrol phases of plant maintenance, operatten, and a ministrative precedures relating to factitty operations and shall have the authority to request the action necessary to ensure compliance with rules, regulattens and precedures uhen in his opinten such action is necessary. The Statten Manager shall fellow l

such recommendations er select a course of action that is more conservative l

regarding safe operetten of the factitty. All such disagreements shall be reported tamediately to the Assistant Vice President and General Manager Nuclear Stattens and the Superviser of the Offa1te Review and Invest 1getive Functten.

c.

Records

,1) Begerts, reviews, investigattens, and resemmendations shall be documented with coptes to the Assistant Vice President and General Manager Nuclear $ttttens, the Superviser of the Offstte Review and Investigative Function, the Statten g

Manager, and the Manager of quality assurance.

I

2) Copies of all records and documentatten shall be kept en file at the statten.

d.

Procedures Written setnistrative precedures shall be prepared and maintained for conduct of the Onsite Review and Investigative function. These precedures shall include the fe11 ewing:

1) Centent and mothed of sutetssten and presentatten to the Statten Manager.

Assistant Vice President and General Manager nuclear Stations. and the j

Superviser of the Offstte Review and Investigattve Function.

l

2) Use of cemetttees ideen necessary.

1

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3) Revtew and approval.

i

4) Detailed listing of items to be reviewed.

$) Precedures for aministratten of the esality centrol activities.

4) Assignment of respensttt1tties.

e.

Personnel I

1) The personnel perferetag the enette Review and Investigattve Function. in addttten to the Statten Manager shall consist of persons having espertise in:

l al nuclear power plant technology.

b) reactor operettens.

c) reacter engineering.

d) redtelegical safety and chemist.

el instrueentatten and centrel, and f) sechanical and electric systems.

2) Personnel performing the Onstte Review and Investigattve Functlen shall meet mintassa acceptable levels as described in AoSt NIs.1 1971. Secttens 4.2 and j

4.4.

{.

M.

ftre Pretettten Program An independent fire protectten and less preventten progree inspectten and audit shall be performed at least once per 12 months uttilaing either quellfted offsite Itcensee

,j; personnel er an outside fire protectten fire.

4 An inspectten and audit of the fire protection and less preventten progree shall be performed by a qualtfled outside fire censultant at least once per 34 months.

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CORPORATE ORGANIZATION Amendment No. 6,100

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Amendment No. AE, 100 w -cies.. se.it o e n. ts.it Figur. 6.1-2

Qua0-CITIts OPR-29 MINDtff $HIFT MAMMING CHARTe

.g CONDITION OF ONE UNIT

~

(No Fuel in Second Unit)

License Intttal Fuel Loading Cold shutdoom or Above Cold Category or During Refueling Refueling shutdoom Shutdown sen1or Operator l

License 2

1 2

I Operator l

License 2

2 3

Rad. Prot. Man 1

i 1

ston-Licensed (As Required) 1 2

Shift Technical Advisor None Required Ilone Required l'

CONDITION OF SECOMO UIIIT (One Unit at Hot shutdown or at Power)

License Initial Fuel Leading Cold Shutdown or -

Above Cold Category or Ouring Refueling Refueling shutdoom Shutdown Sentor*

Operator License 2

2 2

Operator

Ltcense 3

3 3

Rad. Prot. Man 1

1 1

Non-Ltcensed 3+ (As Required) 3 4

Shttt Technical Advisor 1

1 1

COWOITION OF SECONO UIIIT (One Unit at Cold shutdown er Refueling shutdoem)

License Inttial Fuel Leading Cold Shutdoom or Above Cold Category or During Refueling Refueling Shutdown Shutdoom.

Senior

Operator Ltcense 2

1 2

Operator

Ltcense 3

2 3

Rad. Prot. Man i

1 1

Non-Licensed 3+ (As Require 1) 3 3

Shift Technical 1

g Advisor None Required Ilone Required

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Assumes each incividual is licensed on each facility. During initial fuel loading or during j

t refueling. one senior engineer (limited Itcense) will supervise fuel handitng.

1

Shif t crew composition may be less than the mintaum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on duty shif t crew members provided tonediate action is taken to restore the shtf t crew composition to within the minimum requirements of Figure 6.1-3.

Figure 6.1-3 Amendment No. 74, 100 v

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DPR-29 6.2 PLANT OPERAT!aG PROCEDURES A. ' Detailed written procedures. including applicable checkoff lists covering items listed l

below shall be prepared, approved and adhered to:

1.

aorms1 startup. operation, and shutdown of the reactor, and other systems and components involving nuclear safety of the facility.

2.

Refueltag operations.

I 3.

Actions to be taken to correct specific and foreseen potential malfunctions of systems or components. tr.cluding responses to alarms. suspected primary system leaks, and l

abneruel reactivity changes.

I 4.

Emergency candittens involving potential er actual release of radteactivity -

" Generating Statten Emergency Plan' and station emergency and abnormal precedures.

5.

Instrumentatten operation etch could have an effect en the safety of the factitty.

6.

preventive and corrective maintenance operations dich could have an effect en the safety of the facility.

l 7.

Surveillance and testing requirements.

8.

Tests and experteents.

g.

Precedure to ensure safe shutdown of the plant.

10. Statten Security Plan and teplementation procedures.

11. Fire Protection Program tuplementation.

12. 13 08 W iesentattom.

13. PCP tuplementation.

14. Wortting hours of the Shift Engineer. Station Control Room Engineer. Shif t Foreman and the nuclear Station Operator job classifications such that the heavy use of overtime is not routinely required.

3.

Radiation cor. trol procedures shall be maintained, made available to all station personnel, and seered to. The procedures shall show permissible radiation exposure and shall be f

consistent with the requirements of 10 CFR 20. This radiation protection program shall be l

organtaed to meet the requirements of 10 CFR 20.

l C.

1.

Procedures for items identified in Specification 6.2-A and any changes to such proceestes shall be reviewed and approved by the Operating Engineer and the Technical Staff Supervisor in the areas of operation or fuel handling and by Asst. Sept.

Maintenance and Technical Staff Supervisor in the areas of plant maintenance and plant i

inspection. Procedures for items identified in Specification 6.2.5 and any changes to I

such procedures shall be reviewed and approved by the Technical Staff Supervisor and I

the Radiation-Chemistry Supervisor. At least one person approving each of the above precedures shall hold a valid senior operator's license. In addition, these procedures and changes thereto aust have authorization by a Station Superintendent l

before being taplemented.

2.

Woric and instruction type procedures uhtch teplement approved maintenance or modification procedures shall be approved and authorized by the Asst. Supt.

Maintenance where the written authority has been provided by a Station Superintendent. The " Maintenance Modification Procedure" utilized for safety related wortt shall be so approved only if procedures referenced in the " Maintenance Modification Procedure

have been approved as required by 6.2.A.

Procedures m ich do not fall within the requirement of 6.2.A or 4.2.5 any be approved by the Department Needs.

O.

Temporary changes to procedures 6.2.A and 6.2.5 above may be made provided:

j 1.

The intent of the original procedure is not altered.

l 2.

The change is approved by two meeers of the plant management staff. at least one of d em holds a Senior Reactor Operator's license on the unit affected.

l 6.2-1 Amendment No. 89,100

Quad-cities OPR-29 4

'3. The change is documented reviewed on the Onsite Review and Investigative Function, l

and approved by the Station Manager 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.

6.3 REPORTA8LE EVENT ACTION A.

The following actions shall be taken for Reportable Events:

1.

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

2.

Each Reportable Event shall be reviewed by the On-Site Review Committee, and the results of this review shall be submitted to the Off-site Review and Investigative Function and to the Assistant Vice President and General Manager. Nuclear Stations.

Amendment No. 39, 89, 100

Quad-Cities ope-29 4

6.4 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED If a safety Itmit is exceeded, the reactor shall be shut doun immediately, and reactor operation shall not be resumed untti authorized by the NRC. The conditions of shutdown shall be promptly reported to the Assistant vice President and General Manager Nuclear Stations or j

his designated alternate. The incident shall be reviewed pursuant to Specifications 6.1.G.I.a. and 6.1.G.2.4 and a separate report for each occurrence shall 6e prepared in accordance with Spectf tcation 4.3.A.I.

l 6 4-1 Amendment flo. 39,100

Ouac-Cities DPR-39 o.5 PLANT' OPERATING RECORDS A.

Records and/or logs relative to the following items shall be kept in a mannar convenient for review and shall be retained for at least 5 years.

1.

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

2.

Records of principal maintenance and activities, including inspection and repair.

regarding principal items of equtpment pertaining to nuclear safety.

3.

Records and reports of reportable events and safety Itatt occurrences.

l 4.

Records and periodic checks. inspection and/or caltDrations performed to verify that the survet11ance requirements (see Section 4 of these specifications) are being met (all equipment failing to meet surveillance regtrements 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 18 CFR 58.59.

6.

Records of radioactive shipments.

7.

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

8.

Records of changes to operating procedures.

9.

Shif t engineers' logs. and

10. Syproduct material inventory records and source leak test results.

S.

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

3.

Records of new and spent fuel inventory and assemely histories, 4.

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

f l

5.

Records of plant radiatton and contamination surveys.

6.

Records of offsite environmental monitoring surveys.

7.

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

(

8.

Records of radioactivity in liquid and gaseous wastes released to the environment.

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9.

Records of transient or operational cycling for those components that have been designed to operate safely for a limited nuncer of transient or operational cycles, l

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10. Records of individual staff meneers indicatino qualifications experience. training, and retraining.

11. Inservice inspections of the reactor coolant system: and

12. Minutes of meetings and results of reviews and audits performed by the off site and i

onsite review and audit functions.

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

(

OfAff AAL66 Dit% ff 2&, 1980 l

Amendment No. 38, 100

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Quad-Cities OPR-29 6.6 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10. Code of Federal Regulations, the following identified reports shall be submitted to the sentnistrator of the appropriate Regional Office unless otherwise noted.

A.

Routine Reports 1.

Startup Report A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating Itcense (2) amendment to the Itcente involving a planned increase in power level. (3) installation of fuel that has a different design or has been manufactured by a different fuel suppiter, and (a) modtf tcations that any 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 the measured values of the operating conditions or characteristics obtained durin,1 the test 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. Any additional specific dotatis 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 test program. (2) 90 days following resumption or connancement of commercial power operation, or (3) 9 months following intttal criticality, whichever is earliest. If the startup report does not cover all three events (t.e.. initial criticality, completion of startup test program, and resumption or connencement of commercial power operation), supplementary reports shall be submitted at least every 3 months untti all three events have been completed.

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Amendment No. 4,100

Quag-Cities OPR-29 2.

A tabulatton shall be submitted on an annual bests of the number of station utility.

and other personnel (including contractors) receiving exposures greater than 100 mram/yr and their assottated man rem exposure according 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), teste 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 aggregate, at least 80% of the total whole body dose received from anternal sources shall be assigned to specific major work functions.

3.

Monthly Operating Report Routine report of operating statistics and shutdown expertence shall be submitted on a monthly bests to the Strector. Office of Management Information and Program Control.

U.S. auclear Regulatory Commission. Washington. DC 20555. with a copy to the appropriate Regional Office to arrive no later than the 15th of each month following the calendar month covered by the report. In addition, any changes to the ODCM shall be submitted with the Monthly Operating Report within 90 days of the effective date of the change.

A report of major change to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the perted ist which the evaluation was revleued and accepted by the ensite review function. If such change is re-evaluated and not installed, nettf tcation of cancellation of the change should be provided to the NRC.

1 l

l l

6 8-2 Amendment No. 89, 100

Ouao-Cities OPR-29 5.

Untgue Reporting Requirements 1.

Radioactive Effluent Release Report (Semi-Annual)

A sant-annual report shall be sutunttted to the Comunission within 60 days after January 1 and July 1 of each year spectfying the quantity of each of the radionuclides released to unrestricted areas in 11guid and gaseous effluents during the prevteus 6 months. The forinat and content of the report shall be in accordance with Regulatory Guide 1.21 (Revision 1) dated June. 1974. Any changes to the PCP shall be included in this report.

2.

Environmental Program Data (Annual Report)

An annual report containing the data taken in the standard radiological monitoring program (Tatte 4.0-4) shall be submitted prior to May I of each year. The content of the report shall include:

Results of all environmental measurements suunarized in the format of a.

Regulatory Guide 4.8 Table 1 (Decenter 1975). (Individual sample results will he retained at the Station). In the event that same results are not available for inclusten with the report, the report shall be submitted noting and emplaining the reasons for the missing results. Sumneries, interpretations, and analysts of trends of the results are to be provided.

b.

As assessment of the monitoring results and radiation dose via the principal pathways of expcsure resulting from plant emntssions of radioactivity including the semianan noble gas gamma and beta air doses in the unrestricted area. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (00CM).

Results of the census to determine the locations of nearest residences and of c.

nearby animals producing stik for human consumption.

(Table 4.5-4).

d.

The reason for the omission if the nearest dairy to the station is not in the monitoring program (Table 4.8-4).

An annual summary of meteorological conditions concurrent with the releases of e.

gaseous effluents in the form of joint frequency distributtons of wind speed.

wind direction, and atmospheric stability.

f.

The results of the Interlaboratory Comparison Program described in section 3.8.D.7.

The results of the 40 CFR 190 urantum fuel cycle dose analysts for each g.

calendar year.

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h.

A summary of the monitoring program, including maps showing samplings locations and tables giving distance and direction of sappling locations fron t

l the Station.

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Amendment No. 89,100

Quad-Cittes OPR-29 0

3 If a confirmed measured radionuclide concentration in an environmental sampling

=

medtum averaged over any calendar guarter sampling period exceeds the reporting level given in Table 4.8-5 and if the radioactivity is attributable to plant operation, a written report shall be submittee to the aantnistrator of the NRC l

Regional Office, with a copy to the Director. 0.'fice of nuclear Reactor l

Regulation, within 30 days from the end of the quarter.

a.

leen more than one of the radionuclides in Table 4.5-5 are detected in the medium, the reporting level shall have been exceeded if et p1 R.L.1 th radionuclide in emere C1 is the average guarterly concentration of the 9 the medium and RL is the reporting level of radienuclide 1.

h.

If radionuclides other than those in Table 4.8-5 are detected and are due to plant effluents, a reporting level is exceeded if the potential annual dose to an individual is equal to or greater than the design objective doses of it CFR

58. Appendix 3.

c.

This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to emplain the anomalous effect.

4.

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

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i Amendment No. 89, 100 6.6-4 I

Ouad-tities DPR-29 TASLE 6.6-1 SPECIAL REPORTS

~

Specification Reference Submittal Data ALRA a.

Secondary containment leak rate test (1) 4.7.C Upon cogletion of each test.

b.

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

Materials radiation surveillance 4.6.5.2 After each specimen removal specimens and completion of analyses.

d.

Radioactive leurge Leak Testing (2) 4.8.F.

Annual Report e.

Special Effluents Reports 3.5.A.

30 days following occurrence.

3.8.8.

3.8.D.

6.6.C.3 ElI11 1.

Each integrated leak rate test of the secondary containment shall be the subject of a sunnary technical report. This report should include data on the wind speed, wind direction, outside and inside tageratures during the test. concurrent reactor building pressure, and emergency went11ation flow rate. The report shall also include analyses and interpretations of those data which damnstrate compliance with the specified leak rate limits.

2.

This report is required only if the tests reveal the presence of 0.005 microcurtes or more of removable contamination.

Amendment No. 89, 100

Quad-Cities OPR-29

.s e.7 ENVIRONMENTAL OU4LIFICATION A.

All safety-related electrical equipment in the faciltty shall be qualifted in accordance l

with the provisions of: Assistant of Operattng Reactors ' Guidelines for Evaluating

Environmental Qualificatten of class It Electrical Equipment in Operating Reactors" (00R Guidelines): or. NUREG-0548 *Interie Staff Position oe Environmental Qualtftcation of Safety-Related Electrical Equipment". Becaneer 1979. Copies of these documents are attached to Order for Modtftcatten of License DPR-29 dated October 24. 1980.

6.

Complete and auditable records sust be available and maintained at a central location which describe the anytrennental qualification method used for all safety-related electrical equipment in suff tetent detail to document the degree of compilance with the 00R Guidelines or NUREG-0588. Such records should be updated and maintained current as egulpment is replaced. Further tested. or otherwise further qualifted.

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pn Recoq'o, UNITED STATES NUCLEAR REGULATORY COMMISSION n

g WASHINGTON D. C. 20555 h

%,*****4 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINDIS GAS AND FLECTRIC COMPANY DOCKET NO. 50-265

.I OUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. DPR-30 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licenseel dated February 17, 1983, as supplemented and superseded August 24, 1984 and January 20, 1986, respectively, 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 re' ulations of the g

Commission; C.

There is reasonable assurance (i) that the activities authorized and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i

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.

Accordingly, the license is amended by changes to the Technical 2.

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:

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6.

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 97, 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

\\

r wJ John A. Zwolinski, Director BWR troject Directorate #1 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 2, 1987 I

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6 ATTACHMENT TO LICENSE AMENDMENT NO. 97 FACILITY OPERATING LTCENSE NO. DPR-30 DOCKET NO. 50-265-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 y

v 1.0-4 1.0-4 3.12/4.12-1 3.12/4.12-1 3.12/4.12-2 3.12/4.12-2 3.12/4.12-3 3.12/4.12-3 3.12/4.12-4 3.12/4.12-4 i

6.1-1 6.1-1 6.1-2 6.1-2 6.1-3 6.1-3 6.1-4 6.1-4*

6.1-5 6.1-5 6.1-6 6.1-6 Fig 6.1-1 Fig 6.1-1 Fig 6.1-2 Fig 6.1-2 Fig 6.1-3 Fig 6.1-3 6.2-1 6.2-1 i

6.3-1 6.3-1 6.4-1 6.4-1 6.5-1 6.5-1 6.6-1 6.6-1 6.6-2 6.6-2 6.6-3 6.6-3*

6.6-4 6.6-4 6.6-5 6.6-5 6.6-6 6.6-7 6.7-1 6.7-1

Pagination change only

D QUAD CITIES DPR-30 4.8-2 Maximum Permissible Concentration of Dissolved or Entrained 3.8/4.8-21a

' Noble Gases Released from the Site to threstricted Areas in Liquid Waste 4.8-3 Radioactive Areas in Liquid Waste Sampling and Analysis 3.8/4.8-22 Program 4.8-4 Radiological Environmental Monitoring Program 3.8/4.8-24 4.8-5 Reporting Levels for Radioactivity Concentrations in 3.8/4.8-27 Environmental Samples 4.8-6 Practical Lower Limits of Detection (LLD) for Standard 3.8/4.8-28 Environmental Monitoring Program 4.11-1 Surveillance Requirements for High Energy Piping 3.11/4.11-3 Outside Containment 3.12-1 Fire Detection Instruments 3.12/4.12-7 3.12-2 Sprinkler Systems 3.12/4.12-8 3.12-3 CO2 Systems 3.12/4.12-8 3.12-4 Fire Hose Stations 3.12/4.12-9 6.6-1 Special Reports 6.6-5 i

w P

1 I

v l

Amendment No. M,97 I

QUAD-CITIES DIR-30 Y.

Shutdown - The reactor is in a shutdown condition when the teactor mode switch is in the Shutdown position and no core alterations are being performed.

1.

HDt Shutdown means conditions as above, with reactor coolant temperature greater than 2120F 2.

Cold Siutdown means conditions as above, with reactor coolant temperature equal to or less than 2120F.

Z.

Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question.

AA. Transition Boiling - Transition boiling means the regime between nucleate and film boiling. Transition boiling is the regime in which both nucleate and film boiling occur intermittently, with neither type being completely stable.

BB. Critical Power Ratio (CPR) - The critical power ratio is the ratio of that asse 21y power which causes some point in the asse21y to experience i transition boiling to the assembly power at the reactor condition of interest as calculated by application of the GEXL correlation (reference EDO-10958).

CC. Minimum Critical Power Ratio (EPR) - The minimum incore critical power ratio corresponding to the most limiting fuel assembly in the core.

DD Surveillance Interval - Each surveillance requirment shall be performed within the specified surveillance with:

A maximum allowable extension not to exceed 25K of the surveillance a.

interval.

b.

A total maximum combined interval time for any 3 cen.a utive surveillance intervals not to exceed 3.25 times the specified surviellance interval.

EE. Fractim of Limiting Power Density (FLPD) - The fraction of limiting power density is the ratio of the linear heat generation rate (LHGI) existing at a given loction to the design UCR for that bundle type.

FF. Maximtsn Fraction of Limiting Power Density (WLPD) - The maximum fraction of limiting power density is the highest value existing in the core of the fraction of limiting power density (FLPD).

GG. Fraction of Rated Power (FRP) - The fraction of rated power is the ratio of core thermal power to rated thermal power of 2511 Mith.

Mi. Reportable Event - Any of those conditions specified in Section 50.73 to 10 CFR Part 50.

1.0-4 Amendment No. 51,97

. QUAD <1 TIES DPR-30 3J2/4.12 FIRE PROTECTION SYSTDiS.

LIMITING COhDITIONS FOR OPERATIONS SURVEII. LANCE REQVIRDIENTS Applicability:

Applicability:

Applies to the fire protection systems whenever the Applies to the periodic testing requirementi cf the fire equipment or systems being protected are seguired to protection systems -whenever the fire protection be operable.

systems are required to bp operable.

Objective:

Objectiver To ensure that adequate protection against fires is To verify operability of the fire protection systems.

ensuitained during all modes of facihty operation.

SPECIFICATIONS A. Fire Detection Instrumentation A. Fire Detection Instrumentation

~

2. As a minimum.the fire detection instru-

1. Each of 'the' fire detectiert instruments mentation for each fire detecuon zone

~ given by Table 3.121 shall be demon.

l ahown in Table 3.121 shall)e operable rated operable at leas:'once per 6 at all times when equipment in that fire months by a channel functional test.

detection zone is required to be operable.

2. M m. pud h iu' M be

2. With the number of operable fire detec.

demonstrated operable one: per month.

tion instruments less than required by Table 3.121; j

a. Perform an inspection of affected l

anne, withist I bour. Perform addi.

tional inspections at least once per

'bour emcept in inaccessible artss.

b. Restors tie inoperable histrument(s)

,no operable status wahm 14 days, or preperstand submit a report to the Comrrussion pursuant to Specification l

6.3.A.1 Iwnhin the next 30 days out.

@g the cause of the malfunction, the action taken, and the plans for restonng the instrument (s) to oper-able status.

3. ne pecwisions of specification 3.0.A are not appl.icable.

Amendment No. 6, 97 3.12/4.12-1.

t

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4 i

l i

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QUAD.CTMS DPR-30 l

l

3. Fire SuppressonWaerSysem B. Fhe Suppresson Waaer System f~

1. The Fra Suppression Water Syssa shaB

1. The Fue Suppresson Water Synem shad be operable at au tunes wah; be demonstrated operable:

a. Two (2) high pressares panps each

a. At least once per 31 days on a stag.

with a capacity of 2000 gym with gered test basis by sarang each pump ther dascharge aligned to the fue and operathgitforstisast 20 nunutes suppresson header.

on acirculanon Dow.

b. Amosnatic hitiation logic for each

b. At lean onor per 31 days by verifymg fue pump.

that each v.dvs (manual, power 8Perated or auma@ h the now

c. An operable Dow path capable N Pat h a the meet ponen.

talang macuon from the Masasupp River and transferring the water

c. At lesa once per 3sar by performance through distribution pipes with oper.

of a synem Dush.

able secuonalizmg control or isolauon

d. At Isast once per year by cycling each valves to the yard bydrant curb valves tenable valve a. tr.e Bow path through and the front valve ahead of the water at st one emnpkte cycle of fuu Dow alarm device on each sprmkler,

""I" how stand pipe, or spray system ruer.

e. At least once per operates cycle

2. Wah moperable fue pumps or assocanted water sapply, restore the moperable (1) By performmg a system func.

equipment to operable aarus withm 7 nonal test which includes days, or prepare and sabmit a report to the Commisson pursuant to Specifica.

I tion 4.3.A.1 within the next 30 days out.

linmg the plans and procedures to be used to provide for the loss of redundancy in-this system.

3. With no Fire Suppression Water Syne'm j

operable,within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ;

a. Enablish a backup Fire Supprssnon l

Water Synem.

l l

b. Notify-the Commisson pursaant to l

l Specificatson s.3.a.1 outimmg the

)

acuons taken, the cause of the in.

operability, and the plans and achedule for restorms the synem to i

i operable status.

4.

If the requirements of Specificanon 3.12.B.3.a cannot be met, an orderly shut down shan be irutisted, and the reactor j

shall be in a cold shut down condiuon I

l withan 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l I

Amendment No. AA, 97 3.12/4.12 2

QUAD CITIES DPR-30 simulated automatic actuation of the system throughout its opera.

ting squence and verifying that each automatic valve in the flow path actuates to its correct position.

(2) By verifying that each pump dev.elops at leam 2000 gym at a symem head of 123 psig.

(3) Cycling each valve in the flow path that is not testable durmg plant operation through at least one complete cycle of full travel, and

f. At lean once per 3 years by perform.

ing flow tests of the system in accor.

dance with Chapter 5 Section II, NFPA Fire Protection Handbook.

C. SprinklerSystems C. SprinklerSystems

1. The sprinkler syrems given in Table 1.

At least once per year by cycling each 3.12 2 shall be op rable at alltimeswhen tenable valve in the Dow path through at equipment in the areas spray /sprmkler least once complete cycle of full travel.

Proter.ed is required to be operable.

2. Atleast once per operating cycle:

1. With the cable tunnel sprinkler system

a. A fuM ten Ad be p.

inoperable, establish a continuous fire formed which includes simuisted auto.

watch with back up fire suppression snatic actuation of the system and equipment for the unprotected area verifying that the automatic valves in within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

the flow path actuate to their cor.

3. With any other sprinkler synem in.

rect positions.

l operabe, establish back up fire map.

b. W er M ad m e d k h.

l pression within 1 hout and inspect the spected to verify their integrity.

area twice per shift.

c. Each nozzle shall be inspected to 4.

Restcre the system to operable matus fy no blockap l

within 14 days. or prepare sad submit

3. At least once per 3 years by performing i

a report to the Commission pursuant to Specification 6.3. A.1 within the an air flow test through each open head

]

next 30 days outhning the cause of spray / sprinkler header and verifymg each inoperability, the action taken, and open head spray /sprmkler nozzle is un.

obstructede the plans for motoring the symem to operable status.

5. the pecwisiens of specification 3.0.A are not aplicable.

l l

Amendment No. 65, 97 3.12/4.12-3

QUAD-CITIES DPR-30 2 Systems D. CO2 Systems D. CO

1. The CO Storage Tank shall have a mini-

1. Atiesst ince per 7 days th: CO Storage 2

2 snum mand by level of 50 percent and a Tank level.and preuure wn! be verifad.

sninimum prenure of 250 psig.

2. At least 4nce per operating cycle, the

2. The CO Synerns given'in Table 3.12 3 system valves and asociated dampers wH1 2

shallbe operable.-

be verire'd to actuate automatically and manually. A brdw ten M be made

3. Specifications 3.12.D.1 and 3.12.D.2 I'"'N above apply when the equipment in the areas given in Table 3.12.3 is required to be operable.

With a CO Syneminoperable, establish 4.

2 backup fue suppreuion equipment for the unprotected ares (s) within I hour and inspect the area twice per shift.

S. Restore the system.to operable status within 14 days, or prepare and submit a report to the Commission pursuant to l

Specification 6.3. A.1 within the next 30 days outlining the cause of inoper.

ability, the action taken, and the plans and schedule for restonng the system to operable status.

6. If actuated, the storage tank will be restored to greater than the minimum level within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

7. She provisions of Specificatien 3.0.A are not applicable.

E. Fire How Stations E. Fire Hose Stations

1. The Fire Now Stations given in Table

1. At least once per 31 days,a visualinspec.

l 3.12-4 sha!! be operable at all times tion of each fire how station shall be when the equipment in the areas pro.

, made to assure all equipment is available sected by tin fue how is required to be at the station:

PeraMe.

2. At least once per operating cycle, the

2. With a how nation inoperable. route an hose will be removed for inspection and

~

additions) equivalent capacity hose to the reracked. Degraded gaskets m the coup-unprotected area frem an operable hose lings will be rep! aced.

station within I hour.

3. At lean once per 3 years, each hose ca.

tion valve wi!! be partially opened to

3. The provisions of Specification 3.0.A are not applicable, wrify valve operability and no blockage.

t 4.

t least once per 3 years a hydrostatic l

test will be conducted en each how at a pressure at least 50 psig greater than the i

maximum pressure available at the hose

~

station.

F Penetration Fire Barriers F. Penetration Fire Basviers i

l

1. All penetration fire barners protecting 1.

Each of the penetration fire barrier shall safety related areas shall be intact except be verified to be intact by visua! in-l as stated in Specification 3.12.F.2.

speetion; L

Amendment No. 63, 97 3.12/4.12 -4 w,-e-.------ - -, - -

---,,,,_,,,.,vy,

,----,---e--,-m

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-- +-

T

f 6

e' quad CITIES SPR-30 6.0 ADMINISTRATIVE CONTROLS l

6.1 ORGANIZAT105. REVIEW. IWWESTIGATION AND AUDIT The Statten Manager shall have evere11 full-ttee responsibility for safe operation of the l

A.

facility. During perleds uhen the Statten Manager is unavailable, he shall designate this I

responsthtlity to an established alternate de satisfies the AN51 N18.1 of March S.1971 espertence requirements for plant manager.

The organisation chart of the corporate management e tch relates to the operation of this S.

statten and the normal functtenal organtaatten chart for operation of the station are i

shown in Figures 6.1-1 and 6.1-2. respectively.

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

The Assistant C*

Superintendent Operating. Operatin[ Engineer Shift Engineers, and Shift Foremen shall have a senter operating license. Yne Fuel Nandling Foreman has a limited Senior Operating License. The Assistant Vice President and General Manager nuclear Stations on the corporate level has responsthtlity for the Fire Protection Program. The Assistant superintendent Mstntenance will be responsible for taplementation of the Fire Protection A fire brigade of a least 5 member shall be maintained on-stte at all times.

l Progree.

This escludes the shift crew necessary for safe shutdown of the plant, and any personnel required for other essential functions during a f tre emergency.

gualifications of the station management and operating staff. excluding the Rad-Chem 9.

supervisor and the Radiation / Chemical Technicians, shall meet etntman acceptable levels as i

described in ANSI N18.1.

selection and Training of Nuclear Power Plant Personne1* dated March 8. 1971. The Rad-Chem Supervisor or the Lead Nealth Physicist shall meet the requirements of radiation protection manager of Regulatory Guide 1.8.

The individual filling the position of Assistant Superintendent - Technical Services shall meet the etnianam acceptable level for

Technical Manager" as described in Section 4.2.4 of Ams!

N18.1-1971. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design. and response and analysts of the plant for transients and accidents.

The Radiation / Chemical Technictans shall have successfully coupleted the established Radiatten/ Chemical Technician training program, and shall have at least a total of one year of general power plant. chemical, or radiation protection expertence, or equivalent training. The Radiation / Chemical Technicians shall meet the criteria for " Individuals Sus 11f ted in Radiation Protection Procedures". as described in the D. L. Ziemann (mRC) letter to R. L. Bolger (Ceco.) dated March 15. 1977. The Radiation / Chemical Technician i

training program consists of the following:

Satisfactory completion of a 12-week academic program. Toptes of this course include 1.

mathematics. nuclear physics, radioactive decay chemistry, sampling technteues.

reactor coolant parameters, radiation esposure shielding biological effects of radiation esposure, radiation survey techniques, personnel monitoring, and emergency procedures.

i 1

Satisfactory performance on a comprehensive examination following completion of l

2.

acaduate tratning.

3.

On-Shif t training under the Supervision of a qualified Radiation / Chemical Technician.

Retraining and replacement training of Station personnel shall be in accordance with AN!!

E.

N18.1. *$ election and Training of nuclear Power Plant Personnel", dated March 8,1971.

f l

A training program for the fire brigade shall be maintained under the direction of the l

Station Fire Marshal and shall meet or exceed the requirenents of Section 27 of the NFPA Code-1975 encept that training sessions shall be at least quarterly.

i Retraining for licensed operators, senior operators. and senior operators (limited) shall l

F.

be conescted at intervals not exceeding 2 years.

The Review and Investigative Function and the Audit function of activities affecting G.

quality during factitty operations shall be constituted and have the responsibilities and authorittes outlined below:

The Supervisor of the Offsite Review and Investigative Function shall be appointed by

(

l.

the Chairman and President. The Audit Function shall be the responsibility of the l

Manager of Quality Assurance and shall be independent of operations.

6.1-1 Amendment No. $/, 97 i

~ - --

Quad-CITIES OPR-30 s

i a.

Offsite Review and Investigative Function The Supervtsor of the Offstte Review and Investigative Function shall (1) provide directions for the review and investigate function and appoint a senior participant to provide appropriate direction (2) select each participant for this function. (3) select a caglement of sore than one participant who collectively l

l posses background and qualifications in the subject matter under review to provide comprehensive interdisciplinary review coverage under this function (4) l independently review and approve the findings and recommendations developed by personnel performing the review and investigative function. (5) approve and report in a timely manner all findings of noncompitance with NRC requirements to the Station Manager. Assistant Vice President and General Manager Nuclear Stations, a

l Manager of Quality Assurance and the Vice President of Nuclear Operations.

l During periods seen the Supervisor of Offsite Review and Investigattve Function is unavailable he shall designate this responstbtitty to en estabitshed alternate, who satisftes the formal training and empertence requirements for the Supervtsor of the Offsite Review and Investigative Function. The responsibilities of the personnel performing this function are stated below. The Offstte Review and Investigative Function shall review:

1) The safety evaluations for (1) changes to procedures, equipment, or systems as described in the safety analysis report and (2) tests or emperiments completed under the provisten of Ig CFR f

50.5g to vertfy that such actions did not constitute an unreviewed safety question. Proposed changes to the Ouality Assurance Program description shall be reviewed and approved by the Manager of Quality Assurance.

2) Proposed changes to procedures, equipment or systems which involve an unreviewed safety guestion as defined in 10 CFR 50.5g.

3) Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.5g.

4) Proposed changes in Technical Specification NRC operating licenses.

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

6) 5tgnificant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the Onstte Review and Investigative Function.

l I

7) Reportable events.

g) All recognized indications of an unanticipated deficiency in some aspect of design or operatton of safety-related structures, systems, or components.

g) Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to the tuplementation of such change.

10) Review and report findings and recommendations regarding all items referred by l

the Technical Staff Supervisor. Station Manager. Assistant Vice President and General Manager Nuclear Stations, and Manager of Quality Assurance.

l I

b.

Audit Function The Audit Function shall be the responsibility of the Manager of Quality Assurance independent of the Production Department. Such responsiblitty is delegated to the Otractor of Quality Assurance for operating and to the General supervisor Quality i

Assurance Maintenance for maintenance quality assurance activities.

l Either shall approve the audit agenda and checklists. the findings and the report i

of each audit. Audits shall be performed in accordance with the Company Oualtty Assurance Pro 6 ram and Procedures. Audits shall be performed to assure that l

safety-related functions are covered within a period of 2 years of less as designated below.

1) Audit of the conformance of facility operation to provisions contained within the Technical Specifications and appitcable license conditions at least once per year.

6.1-2 Amendment No. 84, 97

Qua0-CITIES DPR-30 s

2) Audit of the adherence to procedures. tratntng and qualif tcation of the station staff at least once per year.

3) Audit of the results of actions taken to correct def tetencies occurring in facility equipment, structures. systems or methods of operation that affect nuclear safety at least once per 6 months.

4) Audit of the performance of activities required by the Quality Assurance Program to meet the Crtteria of Appendix *B" 10 CFR 50.

5) Audit of the Facility Emergency Plan and implementing procedures at least once per year.

6) AJdit of the Facility security Plan and implementing procedures at least once per year.

7) Audit onsite and offstte reviews.

3) Audit of 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.

Ig) The 00CM and implementing procedures at least once per 24 months.

11) The PCP and taglementing procedures for solidtfication of radioactive waste at least once per 24 months.

12) seport all findings of noncongliance with mRC requirements and reconnendations and results each audit to the station Manager. Assistant Vice President and General Manager nuclear stations. Manager of Quality Assurance. Vice President of nuclear Operations, and to the Executive Vice President of Construction.

Production, and Engineering.

c.

Authority The Manager of Quality Assurance and the supervisor of the Offstle Review and l

Investigative Function reports to the Chairman and President. Etther the Manager of Gua11ty Assurance or the supervisor of the Offstte Review and Investigattve Function has the authority to order untt shutdown or request any other action which he deems necessary to avoid unsafe plant condtttons.

d.

Records

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

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

e.

Procedures Written senintstrative procedures shall be prepared and maintained for the of f site reviews and investigative functions described in specifications 6.1.G.I.a.

Those procedures shall cover the follt, wing:

1) Content and method of submission of presentations to the Supervisor of the Offstte 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 reconnendations of reviews and investigations. (4) approvtng reports, and (5) distributing reports.

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

6.i-2 Amenciment No. AA, SA, 97

QUAD-C175E3 00R-30 e

o f.

Personnel

1) The' persons including consultants, performing the revtew and investigative function, in addition to the Supervisor the Offstte Revtew and Investigative Function, shall have expertise in one or more of the following disetplines 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, el reactor engineering, f) radiologic 41 safety, g) reactor safety analysis, h) instrumentation and control, t) metallurgy, j) any other appropriate disciplines required by unique characteristics of the fact 11ty.

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

a) auclear Power Plant Technology Engineering graduate or equivalent with 5 years expertence 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 f

Engineering graduate or equivalent with at least 5 years of experience in utility operation and/or engineering, d) Power Plant Design I

Engineering graduate or equivalent with at least 5 years of expertence in

(

power plant design and/or operation.

I e) Reactor Engineering Engineering graduate or equivalent. In addition, at least 5 years of expertence in nuclear plant engineering, operatton, and/or graduate work in nuclear engineering or equivalent in reactor physics is required.

f) Radiological Safety Engineering graduate or equivalent with at least 5 years of expertence in radiation control and safety.

l g) Reactor Safety analysis Engineering graduate or equtvalent, with at least 5 years of expertence 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

1) Metallurgy Engineering graduate or equivalent with at least 5 years of expertence in the metallurgical fteld.

3) The Supervisor of the Offstte Review and Investigative Function shall have expertence and tratntng which satisfy Anst mis.1-1971 requirements for plant managers.

6.1-4 Amendment No. 37, 97 l

~ - -

OUa0-C27tES OPR-30 e'

2.

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

a) Onsite Review and Investigative Function t

The Statteh Manager shall: (1) provide direction for the Review and g

Investigative Function and appoint the Technical Staff Supervisor, or other camparably qualtfled individual as a sentor participant to provide appropriate directions. (2) approve part?cipants for this function; (3) assure that a complement of more than one participant une collectively posses background and qualtftcattens in the subject metter under review are selected to provide comprehenstve interdisciplinary review coverage under this function: (4) independently review and approve the findtags and recommendations developed by personnel performing the Review and Investigative Function: (5) report all findings of noncompitance with NRC requirements, and provide recenuendations to the Assistant Vice President and General Manager Nuclear Stations and g

the Superviser of the Offsite Review and investigative Function; and (6) submit to the Offstte Review and Investigative Function for concurrence in a timely menner.

those items described in Spectrication 4.1.E.1.a uhich have been approved by the l

Onsite Review and Investigative Function.

7 The respenstbilities of the Personnel performing this function are stated below:

1) Review of (1) procedures required by Specificatten 4.2 and changes thereto and (2) any other proposed procedures er changes thereto as determined by the Statten Manager to affect nuclear safety.

l

2) Review of all proposed tests'and emperiments that affect nuclear safety.

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

4) Review of all proposed changes or modtftcations to plant systems or egutament that affect nuclear safety.

5) Investigation of all noncompliance with NBC requirements and shall prepare and?

forward a report covering evaluation and receumendettens to prevent recurrence to the Assistant Vice President and General Manager Nuclear Stations and to l

the Superviser of the Offs 1te Review and Investigattwe Functien.

6) Review of fact 11ty operations to detect potential safety hazards.

y) Performance of special reviews and investigattens and reports thereon as requested by the Superviser of the Offstte Review and Investigative Function.

8) Review of the Station Security Plan and shall sutett recommended changes to i

the Assistant Vice President and General Manager Nuclear Stations.

l t

g) Review of the Emergency Plan and station implementing procedures and shall I

sutett recommended changes to the Assistant Vice President and General Manager l

?

Nuclear Stations.

10. Review of reportable events and actions taken to prevent recurrence.

}

l+

11. Review of any unplanned on-site release of radioactive material to the environs. including the preparation and forwarding of reports covering i

evaluatton recommendations and disposition of the corrective action to prevent l

recurrence to the Assistant Vice President and General Manager Nucleer l

Stations, and to the Supervisor of the Offstte Review and Investigative l

Function, j

12. Review of changes to the PCP and 00CM. and major changes to the ratsaste treatment systems.

l' 6.1-s Amendment No. 37, M, 97 i

i i

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--.co

--w

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r vw o-ad.,--=,-,,-.

- - - - - - - - = -

+---w-ew

-ep-------h-e-m-w--w-- - - - -. - - - - - - - - - - - -

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-*-a

y QUAD-CIflES OPR-30 e

b.

Authority m

The Technical Staff Supervisor is responsible to the Station Manager and shall make recomunendations in a timely manner in all area of review. investigations. and quality control phases of plant maintenance, operation, and a ministrative precedures relating to facility operations and shall have the authority to request the action necessary to ensure compliance with rules, regulations and procedures essen in his opinion such action is necessary. The Station Manager shall follow g

such receumendations or select a course of action that is more conservative regarding safe operation of the factitty. All such disagreements shall be reported launedtately to the Assistant Vice President and General Manager Nuclear i

t Stations and the Supervisor of the Offstte Review and Investigative Function.

l I

l

c. Records

1) Reports, reviews investigations, and recenumendations shall be documented with copies to the Assistant Vice President and General Manager Nuclear Stations, the Supervisor of the Offsite Review and Investigative Function, the Station Manager, and the Manager of Quality Assurance.

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

d.

Precedures I

Written seministrative procedures shall be prepared and maintained for conduct of the Onstte Review and Investigative function. These procedures shall include the following:

1)' Content and method of sutuntssion and presentation to the Station Manager.

Assistant Vice President and General Manager Nuclear Stations, and the Supervisor of the Offsite Review and Investigative Function.

2) ' Use of comunittees when necessary.

l

3) Review and approval.

4) Detailed listing of items to be reviewed.

5) Procedures for senintstration of the quality control activities, f.

6) Assignment of responsibilities.

e.

Personnel

1) The personnel performing the Onsite Review and Investigative Function, in addttton to the Station Manager shall consist of persons having expertise in:

l a) nuclear power plant technology.

b) reactor operations.

c) reactor engineering.

l d) radiological safety and chemtst.

e) instrumentation and control, and I

f) mechanical and electric systems.

l

2) Personnel performing the Onsite Review and Investigative Function shall meet N

mtntmum 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 per 12 months utilizing either qualified offsite licenset personnel or an outside fire protection firm.

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

l l

Amendment No. AA, BA, 97 s

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Amendment No. AA, 97 w.

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QUAD-CITIES OPR-30 MINIMUM SHIFT MANNING CHAPT 8 CONDIT10N OF ONE UNIT (No Fuel in Second Unit)

Ltcense Intttal Fuel Loadtng Cold Shutdown or Above Cold Category or During Refueling Refueling Shutdown Shutdown Senior Operator l

License 2

1 2

Operator l

License 2

2 3

Rad. Prot. Man 1

1 1

Non-Licensed (As Required) 1 2

Shtft Technical Advisor None Required None Required 1

CONDITION OF SECOND IMIT (One Unit at Hot Shutdown or at Power)

License Initial Fuel Loading Cold shutdown or Above Cold Category or During Refueling Refueling Shutdown Shutdown Sentor*

Operator License 2

2 2

(

Operator

License 3

3 3

Rad. Prot. Man 1

1 1

Non-Ltcensed 3+ (As Required) 3 4

Shtft Technical l

Advisor 1

1 1

CONDITION OF SECOND UNIT (One Unit at Cold Shutdown or Refueling Shutdown) l License Initial Fuel Loading Cold Shutdown or Above Cold t

l Category or During Refueling Refueling Shutdown Shutdown Sentor*

Operator License 2

1 2

Operator

License 3

2 3

Rad. Prot. Man i

1 1

l Mon-Licensed 3+ (As Requtred) 3 3

1 ShtfL Techn1 cal 1

l Advisor None Required None Required

Assumes each individual is licensed on each facility. During initial fuel loading or during j

refueling. one sentor engineer (limited license) will supervise fuel handling.

8 Shtft crew composition may be less than the minineam requirements for a period of time not to l

I exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to acconunodate unexpected absence of on duty shtf t crew members provided tausediate action is taken to restore the shif t crew composition to within the minimum requirements of Figure 6.1-3.

Figure 6.1-3 Amendment No. 67, 97

Ouad-Cities Dre-30 6.2 PLANT OPERATISG PROCEDURES A.

Detailed written procedures. including applicable checkoff lists covering items Itsted below shall be prepared, approved, and seered to:

1.

Normal startup operatten, and shutdemn of the reactor, and other systems and components involving nuclear safety of the fact 11ty.

2.

Refueling operattens.

3.

Actlens to be taken to correct specific and foreseen potential selfunctions of systems or components, including responses to alarus, suspected primary systen leaks, and anneruel reactivity changes.

4.

guergency conditions involving potential er actual release of radteactivity -

" Generating Statten Emergency Plan" and statten energency and abnormal precethares.

5.

Instrumentatten operatten uhtch could have an affect en the safety of the factitty.

6.

Preventive and corrective enintenance operations edlich could have an affect en the safety of the factitty.

7.

Surveillance and testing requirements.

l g.

Tests and emperiments.

g.

Precedure to ensure safe shutdemn of the plant.

Ig. Statten Security Plan and leplementation procedures.

11. Fire Protection Program implementatten.

12. ODOI implementation.

13. PCP toplementation.

14. Working hours of the Shif t Engineer. Station Control Room Engineer. Shift Foreman and the Euclear Station Operator Db classifications such that the heavy use of evertime is not routinely required.

5.

Radiation control procedures shall be maintained, made av6tlable to all station personnel.

and aeered to. The procedures shall show permissible radiation exposure and shall be consistant with the requirements of 10 CFR 20. This radiation protection program shall be organtand to meet the requirements of Ig CFR Ig.

C.

1.

Precedures for items identified in spectf tcation 6.2-A and any changes to such precedures shall he revieund and approved P-the Onorating Engineer and the Technical Staff Supervisor in the areas of operation c fue1 hand 11ag and by Asst. Sept.

l Maintenance and Technical Staff Supervisor in the areas of plant asintenance and plant l

inspectten. Procedures for ttens identified in specification 6.2.5 and any changes to such precedures shall be reviewed and approved by the Technical Staff Supervisor and the Radiation-Chemistry Supervisor. At least one person approving each of the above precedures shall hold a valid senior operator's Itcense. In addition, these procedures and cha.aes thereto sust have authortsation by a Station Superintendent l

tefore being teplemented.

2.

Wort and instruction type procedures which teplement approved maintenance or modification procedures shall be approved and authorized by the Asst. Supt.

Maintenance where the written authority has been provided by a Station Superintendent. The " Maintenance Modification Procedure" utilized for safety related wort shall te so approved only if procedures referenced in the " Maintenance Modificatten Procedure

have been approved as required by 6.2.A.

Procedures uhtch do not fall within the respatrement of 6.2.A or 6.2.g esy be approved by the Department Meads.

D.

Temporary changes to procedures 6.2.A and 6.2.5 above any be ende provided:

1.

The intent of the original procedure is not altered.

2.

The change is approved by tuo emebers of the plant management staff, at least one of edies holds a Senior Reactor Operator's Itcense on the unit affected.

' ' ' ^

Amendment No. BA, 97

Quac-Cities DPR-30 3.

The change is documented reviewed on the Onsite Revtew and Investigative Function.

and approved by the Station Manager within 14 days of iglementation.

l E.

Ort 11s of the emergency procedures described in Spectf tcation 6.2.A. shall be conducted in accordance with the G5EP Manual.

6.3 REPORTABLE EVENT ACTION A.

The following actions shall be taken for Reportable Events:

1.

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

2.

Each Reportable Event shall be reviewed by the On-Site Review Committee and the results of this review shall be submitted to the Off-Site Review and Investigative Function and to the Assistant Vice President and General Manager, nuclear Stations.

l 6

l l

Amendment No. 37, 84, 97

Ouad-Cities DPR-30 e

e.4 ACTI()N TD BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED If a safety limit is exceeded, the reactor shall be shut down tunedtately. and reactor operation shall not be resumed untti authorized by the NRC. The conditions of shutdown shall be promptly reported to the Assistant Vice President and General Manager Nuclear Stations or l his designated alternate. The incident shall be reviewed pursuant to Spectftcations 6.1.G.1.a. and 6.1.G.2.a and a separate report for each occurrence sna11 be prepared in accordance with Spectf tcation 6.3. A.I.

l l

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l 6 4-1 Amendment No. 37, 97

Quad-Ctties DPR-30

~6.5 PLANT 0*ERATING 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 5 years.

1.

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

2.

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

3.

Records and reports of reportable events and safety limit occurrences.

4 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 (a11 ogipment failing to meet surveillance requirements and the corrective actlen taken shall be recorded).

5.

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

6.

Re ords of radioactive shipments.

7.

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

l S.

Records of changes to operating procedures.

9.

Shift en31neers' logs, and

10. syproduct material inventory records and source leak test results.

B.

Records and/or logs relative to the following itens shall be recorded in a manner convenient for resiew and shall be retained for the Itfe 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 SAR.

3.

Records of new and spent fuel inventory and assently histories.

4.

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

i 5.

Records of plant radiation and contamination surveys.

[

6.

Records of offsite environmental monitoring surveys.

7.

Records of radiation exposure for all plant personnci including all contractors and I

visitors to the plant. in accordance with 10 CFR 20.

l l

8.

Records of radioactivity in liquid and gaseous wastes releasej to the environment.

I l

9.

Records of transient or operational cycling for those components that have been designed to operate safely for a limited number of transient or operational cycles.

10. Records of individual staff members indicating qualtftcations, experience. training, and retraining.

11. Inservice inspections of the reactor coolant system: and

12. Minutes of meetings and results of reviews and audits performed by the offsite and i

onsite review and audit functions.

I

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

I 9/d#f d#dd 10/4/80

M j

Amendment No. M, 97 l

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Ouad-Cities DPR-30 e

4.6 REPOR. TING REQUIREMENTS In addition to the applicable reporting requtrements of Title 10. Code of Federal Regulations, the following identified reports shall be submitted to the seministrator of the appropriate l

Regional Office unless otherwise noted.

A.

Routine Reports 1.

Startup Report A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating Itcense. (2) amendment to the license involving a planned increase in power level. (3) installation of fuel that has a different design er has been manufactured by a different 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 the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were reeutred to obtain satisfactory operation shall also be described. Any additional specific dotatis required in license conditions based on other couaitments shall be included in this report.

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

I earliest. If the startup report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or connencement of commercial power operation), supplementary reports shall be submitted at least every 3 months untti all three events have been completed.

l l

l Amendment No. 42, 97 6.6-1 l

l l

I 4

Quac-Caties DPR-30 2.

A tabulation shall be submitted on an annual basis of the number of station utiltty.

and other personnel (including contractors) recetving exposures greater than 100 mrom/yr and their associated man rem exposure according 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 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 aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

3.

Monthly Operating Report Routine report of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director. Office of Management Information and Program Control.

U.S. Nuclear Regulatory Commission. teashington, DC 20555, with a copy to the appropriate Regional Office, to arrive no later than the 15th of each month folleming the calender month covered by the report. In addition. any changes to the 00CM shall be submitted with the Monthly Operating Report within 90 days of the effective date of the change.

A report of major change to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the perted in which the evaluation was reviewed and accepted by the onsite review function. If such change is re-evaluated and not installed, nottf tcation of cancellation of the change should be provided to the NRC.

i l

1 1

Amendment No. 84, 97

Quad. Cities ope-30 i

3.

Untque Reportit.g Requirements 1.

Radioactive Lffluent Release Report (Semi-Annual)

A samt annual report shall be submitted to the Comunission within 60 days af ter January 1 and July 1 of each year specifytng the quantity of each of the redtenuclides released to unrestricted areas in 11guid and gaseous effluents during the previous 6 months. The format and content of the report shall be in accordance with Regulatory Guide 1.21 (Revision 1) dated June,1974. Any changes to the PCP shall be included in this report.

2.

Environmental Program Oata (Annual Report)

An annual report containing the data taken in the standard radtalogical monitoring program (Table 4.8-4) shall be submitted prior to May I of each year. The content of the report shall inclute:

a.

Results of all environmental measurements sununarized in the format of Regulatory Guide 4.8 Table 1 (December 1975). (Individual sample results will be retained at the Station). In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. Sammaaries. interpretations, and analysts of trends of the results are to be provided.

b.

As assessment of the monitoring results and radiation dose via the principal pathways of exposure resulting from plant ensnissions of radioactivity including the moutsun noble gas gatna and beta air doses in the unrestricted area. The assessment of radiation doses shall be performed in accordance with the Offstte Dose Calculatton Manual (00CM).

c.

Results of the census to determine the locations of nearest residences and of nearby acimals producing milk for hisman consumption.

(Table 4.5-4).

d.

The reason for the omission if the nearest dairy to the station is not in the monitoring program (Table 4.8-4).

e.

An annual sungnary of meteorological conditions concurrent with the releases of gaseous effluents in the form of joint frequency distributtons of wind speed.

wind direction, and atmospheric stability.

t f.

The results of the Interlaboratory Comparison Program described in section 3.8.0.7.

g.

The results of the 40 CFR 190 uranium fuel cycle dose analysis for each calendar year.

h.

A sungnary of the monitoring program, including maps showing samplings locations and tables giving distance and direction of sampling locations from the Station.

l 1

-3 Amendment No. 84, 97 l

l

Quad-Cities DPR-30 e

3.

If a confirmed measured radionuclide concentration in an environmental samp1tng medtum averaged over any calendar quarter sampling period exceeds the reporting level given in Table 4.5-5 and if the radioactivity is attributable to plant operation, a written report shall be sutunitted to the Aenintstrator of the NRC l

Regional Office, with a copy to the Otrector. Office of nuclear Reactor l

Regulation, within 30 days from the end of the quarter, a.

leen more than one of the radionuclides in Table 4.5-5 are detected in the sodium, the reportir.3 level shall have been exceeded if ft

>1 R.L.1 th radionucitee in where C1 is the average guarterly concentration of the 4 the medium and RL is the reporting level of radionuclide 1.

6.

If radionuclides other than those in Table 4.5-5 are detected and are due to plant effluents, a reporting level is exceeded if the potential annual dose to l

an individual is equal to or greater than the design objective doses of 10 CFR

50. Appendix 1.

l c.

This report shall include an evaluation of any release conditions.

environmental factors, or other aspects necessary to explain the anomalous I

effect.

4.

Special Reports l

Special Reports shall be sutunitted as indicated in Table 6.6-1.

l l

l I

6 6-4 Amendment No. 84, 97

Quad-Cities OPR-30 p'

TABLE 6.6-1 SPECIAL REPORTS Specification Rafarence submittal Date Agga a.

Secondary containment leak rate test (1) 4.7.C Upon completion of each test.

b.

Sunnary status of fuel performance 1.1 Bases After each refueling outage.

c.

Materials radiation surveillance 4.6.8.2 After each specimen removal and completion of analyses.

specimens d.

Radioactive Source Leak Testing (2) 4.8.F.

Annual Report e.

Special Effluents Reports 3.8.A.

30 days following occurrence.

3.8.8.

3.8.D.

6.6.C.3 EQ.Ill 1.

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

This report is required only if the tests reveal the presence of 0.005 microcurtes or more of 2.

removable contamination.

l l

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l l

l t

6.6-5 Amendment No. 84, 97

Quad-Cities OPR-30 ti.7 ENVIRONMENTAL QUALIFICATION A.

All safety-related electrical equipmurnt in the facility shall be qualifted in accordance with the provtstons of: Assistant of Operating Reactors "Guideltnes for Evaluating Environmental Qualtftcation of Class IE Electrical Equipment in Operating Reactors" (00R Guidelines); er. NUREG-0548

Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment". December 1979. Copies of these documents are attached to Order for Modification of Ltcense DPR-30 dated October 24. 1980.

D.

Complete and auditable records ausst be available and maintained at a central location which describe the environmental qualtf tcation method used for all safety-related electrical agutpment in sufficient dotati to document the degree of compliance with the 00R Guidelines or NUREG-0544. Such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualif ted.

1 P

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9fffTddHd 10/24/80 Amendment No. 84,97 6.7-1

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