Text

Proposed Tech Specs,Revising Section 6 Re Organizational Changes in Corporate & Station Mgt Structure
	ML20137M917
Person / Time
Site:	Quad Cities
Issue date:	01/20/1986
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20137M895	List: ML20137M890; ML20137M917;
References
	1119K, 6312N, NUDOCS 8601290101
	Download: ML20137M917 (63)
	v • d • e

1 ATTACHMENT 1 Proposed Changes to DPR-29 Technical Specifications 8601290101 860120 PDR ADOCK 05000254 P PDR 1119K

o s

f QUAD CITIES DPR-29 4.8-2 Maximum Permissible Concentration of Dissolved or Entrained 3.8/4.8-21a Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste 4.8-3 Radioactive Areas in Liquid Waste Sampling 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.

6312N

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 Betwwen 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 Amendment No.

9

t 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 greater than 2120F

2. Cold Shutdown 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 assembly power which causes some point in the assembly to experience transition boiling to the assembly power at the reactor condition of interest as calculated by application of the GEXL correlation (reference NED0-10958).

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

DD Surveillance Interval - Each surveillance requirment shc11 be performed within the specified surveillance with:

a. A maximum allowable extension not to exceed 25% of the surveillance 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. Maximum Fraction of Limiting Power Density (MFLPD) - 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 thernal power to rated thermal power of 2511 MWth.

+

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

i 1.0-4 Amendment No.

t

. QUAD. CITIES . .r - ........ev . . . . - - . . ..

- DPR- 29

~

3.12/4.12 FIRE PROTECTION SYSTEMS. ,

u z. .

{ .

LIMITING CONDITIONS FOR OPERATIONS SURVEILLANCE REQtJIRDhENTS Applicability: .

Applicability:

Applies to the fire protection systems whenever the Ap" plies to the periodic testing requirements 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: ,

s ,

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

. maintained during all modes of facility operation.

. .- SPECIFICATIONS A. Fire DetectionInstrumentation A Fire Detection Instrumentation .

1. As a minimum, the fire detection instru-

1. Eacli of the' fire detection instruments mentation for each fire detection aone given by Table 3.121 shall be demon.

shown in Table 3.12-1 shall)e operable strated operable at least 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. AIL non-supervised circuits sh:ll be

' 2.. With the number of opersble fire detec. demonstrated operable once per month.

tion instruments lpss than requird by Table 3.121;

a. Perform an inspection of affected zone, within I hour. Perform addi.

. tional inspections at least once per

' hour exceptin inaccessible areas.

~

b. Restore the inopeiable instrument (s) to operable status witfun 14 days, or prepare and submit a. report to the. -

Commission pursuant.to Specification l 6.3.A.1within the next 30 days out-

lining the cause of the malfunction, the action takert, and, the plans for ,

restonng the instrument (s) to oper.

y able status.

l3. The prenrisions of specificatic:t I 3.0.A are not applicable. ,

.l '

l ..

8 e

~ ~ -

3.12/4.12-1

. 8 y, . e

1 e

i QUAD. CITIES DPR-29 B. Fire Suppresion Water System B. Fire Suppression Water System

1. The Fire Suppression Water System shall 1. The Fire Suppression Water System shall be operable at all times with; be demonstrated operable:

a. Two (2) high pressures pumps each a. At least once per 31 days on a stag.

with a capacity of 2000 gpm with gered test basis by starting each pump their discharge aligned to the fire and operatingitforatleast 20 minutes suppression header. on rectreulation flow.

b. Automatic initiation logic for each b. At least once per 31 days by verifying fire pump. that each valve (manual, power perated or automanc) e de Dow

c. An operable flow path capable of .

path is m the correct postion.

taking suction from the Mississipp River and transferrmg the water c. At least once per year by performance through distribution piping with oper. of a system flush. - - - -

able sectonalinng control or isolauon

d. At least once per year by cycling each valves to the yard hydrant curb valves ,g g and the front valve ahead of the water at east M C mplete cycle of fun flow alarm device on each spnnkler, hose stand pipe, or spray system nser. "' *"'I'

' ' ^ * ' 5* * * *

P M'* **"I 'Y' '

2. With inoperable fire pumps or associated water supply, restore the inoperable (1) By performing a system func.

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

tion 6.3. A.lmthin the next 30 days out.

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

3. With no Fire Suppression Water System 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 pursuant to Specification 6.3.A.1 outlining the l actions taken, the cause of the in.

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 shall be initiated, and the reactor shall be in a cold shut down condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

f iL 3.12/4.12 2

i i

QUAD-CITIES DPR-29 simulated automatic actuation of the system throughout its opera-ting. sequence and vertfying that each automatic valve in the flow path actuates to its correct position.

(2) By verifying that each pump develops at least 2000 gpm at a syste'm head of 123 psig.

(3) Cycling each valve in the flow path that is not testable durtng 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. Sprinkler Systems C. Sprinkler Systems

1. The sprinkler systems given in Tab!c 1. 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 ! cast one complete cycle of full travel.

protected is required to be operable. 2. At least once per operating cycle:

2. With a sprinkler system inoperable, a. A system functional test shall be per-establish back up fire suppression equip- formed which includes simulated auto-me'nt and inspect the area twice per shift. matic actuation of the system and

'*' I ** '"****I* **

3. Restore the system to operable status the flow path actuate to their cor-within 14 days, or prepare and submit a rect pos1tions.

report to the Commission pursuant to ,

Specification 6.3. A.1 within the next b. The sprinkler headers shall be in-l 30 days outlining the cause of inoper-spected to verify their integrity.

ability, the action taken, ed the plans c. Each, nozzle shall be m.spected to for restoring the system to operable verify no blockage.

status.

3. At least once per 3 years by performmg

4. 'Ihe pcovisions of Specifice.tien asb h@ M p W 3.0.A are not applicable. g g 7 open head spray / sprinkler nozzle is un.

r obstructed.

1 l

i I

I 3.12/4.12 3 l

l l

l

, QUAD.CITih5 ,# . ,r.....r.. .- . . . - 3....

, , Dl'R- 29 D. CO2 Systems D. CO 2Systems

1. The CO, Storage Tank shall have a mini- 1. At least once per 7 days the CO, Storage

~

mum stand by level of 50 per:ent and a Tank level.and pressure wal be vertfied.

minimura pressure of 250 pstg. 7 gg

2. The CO3Systems given in Table 3.12 3 system valves and asweisted dampers will shall be operable. , be verifie'd to actuate automatieslly and manu y. A r w test sH be mah

3. Specifications 3.12.D.1 and 3.12.D.2 to verify flow from each nozzle.

above apply when tae equipment in the areas given in Table 3.12.3 is required to be operable.

4. With a CO 2System inoperable, establish backup fire suppression equipment for the unprotected ares (s) within I hour and inspect the ares twice per shift. ,

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

. 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 mintmum level within 48 huu,rs.

7. 'ihe previsions of Specification 3.0.A are not applicable.

E. Fire Hose Stations E. Fire Hose Stations

1. The Fire Hose Stations given in Table 1. At least once per 31 days.a visualinspec.

3.12-4 shall 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 hose is required to be at the station.

. operable.

2. At least once per . operating cycle, the

2. With a hose station inoperable, toute an hose will be removed for inspection and additional equtvalent capactty hose to the teracked. Degraded gaskets in the coup-unprotected area frem an operable hose lings will be replaced.

station within I hour.

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

3. ite provisions of specification ti n valve will be partially opened to 3.0.A are not applicable. verify valve operability and no blockage.

4 At least once per 3 years a hydrostatic test will be conducted on each hose at a pressure at least 50 ps: greater thsn the ma.umum pressure available at the hose station. .

~

F Penetration Fire Barriers F. Penetration Fire Batriers

1. All penetration fire barriers protectmg ,

I. Each of the per!ctration fire bart:et shall .

safety related areas shall be intact except be verified to be utact by visual in.

as stated in Specification 3.12.F.2. spection;

, 3.12/4.12 -4 ..

QUA0 CITIES DPR-29 6.0 ADMINISTRATIVE CONTROLS jl l

1 6.1 ORGANIZATION. REVIEW INVESTIGATION. AND AUDIT

, A. The Station Manager shall have overall full-time responsibility for safe operation of the l facility. During periods when the Station Manager is unavailable, he shall designate this responsiht11ty to an established alternate who satisfies the ANSI N18.1 of March 8. 1971 experience requirements for plant manager.

B. The organization chart of the corporate management which relates to the operation of this station and the normal functional organization chart for operation of the station are shown in Figures 6.1-1 and 6.1-2. respectively.

E C. The shift manning for the station shall be as shown in Figure 6.1-3. The Assistant Superintendent Operating. Operating Engineer. Shift Engineers and Shift Foremen shall have a senior operating license. The Fuel Handling Foreman has a Ilmited Senior Operating License. The Assistant Vice President and General Manager Nuclear Stations on the corporate level has responsibility for the Fire Protection Program. The Assistant

. Superintendent Maintenance will be responsible for implementation of the Fire Protection Program. A fire brigade of a least 5 member shall be maintained on-stte at all times.

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

D. Qualifications of the station management and operating staff, excluding the Rad-Chem supervisor and the Radiation / Chemical Technicians, shall meet minimum acceptable levels as described in ANSI N18.1 " Selection and Training of Nuclear Power Plant Personnel", dated March 8. 1971. The Rad-Chem Supervisor or the Lead Health 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 minimum acceptable level for " Technical Manager" as described in Section 4.2.4 of ANSI 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 i and analysis of the plant for transients and accidents.

The Radiation / Chemical Technicians shall have successfully completed the established

! Radiation / Chemical Technician training program. and shall have at least a total of one J

year of general power plant. chemical or radiation protection experience, or equivalent training. The Radiation / Chemical Techntcians shall meet the criteria for "Indisiduals Oualified in Radiation Protection Procedures", as described in the D. L. Ziemann (NRC) letter to R. L. Bolger (Ceco.) dated March 15. 1977. The Radiation / Chemical Technician training program consists of the following:

1. Satisfactory completion of a 12-week academic program. Topics of this course include mathematics. nuclear physics. radioactive decay chemistry, sampling techniques.

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

2. Satisfactory performance on a comprehensive examination following completion of acaenetc tratning.

3. On-Shift training under the supervision of a qualified Radiation / Chemical Technician.

E. Retraining and replacement training of Station personnel shall be in accordance with ANSI

! N18.1 " Selection and Training of Nuclear Power Plant Personnel", dated March 8, 1971.

! A training program for the fire brigade shall be maintained under the direction of the j Station Fire Marshal and shall meet or exceed the requirements of Section 27 of the NFPA

! Code-1975 except that training sessions shall be at least quarterly.

F. Retraining for licensed operators. senior operators, and sentor operators (limited) shall f be conducted at intervals not exceeding 2 years.

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

, authorities outlined below:

! 1. The Supervisor of the Offsite Review and Investigative Function shall be appointed by j 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 1

03778/01352 I

i

QUAD-CITIES OPR-29

a. Offsite Review and Investigative Function The Supervisor of the Offsite 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 complement of more than one participant who collectively posses background and qualifications in the subject nutter under review to provide comprehensive interdisciplinary review coverage under this function (4) independently review and approve the findings and recommendations developed by personnel performing the review and investigattve function. (5) approve and report in a timely manner all findings of noncompliance with NRC requirements to the Station Manager. Asststant Vice President and General Manager Nuclear Stations. 1 Manager of Quality Assurance, and the vice President of Nuclear Operations. l During periods when the Supervisor of Offstte Review and Investigative Function is unavailable he shall designate this responsibility to an estabitshed alternate, who satisfies the fornul training and experience requirenents for the Supervisor of the Offsite Revtew and Investigative Function. The responsibilities of the personnel performing this function are stated below. The Offsite Review and Investigative Function shall review:

1) The safety evaluations for (1) changes to procedures, equipment, or systems as described in the safety analysis report and (2) tests or experiments completed under the provision of 10 CFR 50.59 to vertfy that such actions did not constitute an unreviewed safety question. Proposed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of Quality Assurance.

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

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

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) Significant operating abnormalittes or deviations from nornal and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function.

7) Reportable events.

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

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

10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor. Station Manger. Assistant vice President and General Manager Nuclear Stations, and Manager of Quality Assurance.

b. Audit Function The Audit Function shall be the responsibility of the Manager of Quality Assurance independent of the Production Department. Such responsibility is delegated to the 01 rector 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 of each audit. Audits shall be performed in accordance with the Company Quality Assurance Program and Procedures. Audits shall be performed to assure that safety-related functions are covered within a period of 2 years of less as detignated below.

1) Audit of the confernunce of facility operation to provtsions contained within the Technical Specifications and applicable license conditions at least once per year.

6.1-2 03778/01352

QUAD-CITIES OPR-29

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

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

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

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

6) Audit of the Facility Security Plan and imp'ementing procedures at least once l per year.

7) Audit onsite and offsite reviews.

8) 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.

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

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

12) Report all findings of noncompliance with NRC requirenants 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 Offstte Review and l Investigative Function reports to the Chairman and President. Etther the Manager of Quality Assurance or the Supervisor of the Offsite Review 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. Records

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

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

e. Procedures Written aeninistrative procedures shall be prepared and maintained for the off stte reviews and investigattve functions described in Specifications 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 connittees 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 findtngs and reconnendations of revtews and investigations. (4) approving reports, and (5) distributing reports.

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

6.1-3 03778/01352

OUAD-CI?!!S DPR-39

f. Personnel

1) The persons including consultants, performing the review and investigative function, in addition to the Supervisor the Offstte Review and Investigative Function, shall have expertise in one or more of the following disciplines as appropriate for the subject or subjects being reviewed and investigated; a) nuclear power plant technology.

b) reactor operations, c) utt11ty operations.

d) power plant design, e) reactor engineering, f) radiological safety, g) reactor safety analysis, h) instrumentation and control.

t) metallurgy.

j) any other appropriate disciplines required by unique characteristics of the facility.

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

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

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

c) Utility Operations

- Engineering graduate or equivalent with at least 5 years of experience in 4

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

e) Reactor Engineering Engineering graduate or equivalent. In addition at least 5 years of experience in nuclear plant engineering. operation, and/or graduate work in nuclear engineering or equivalent in reactor phystes is required.

f) Radiological Safety Engineering graduate or equivalent with at least 5 years of experience in radiation control and safety, g) Reactor Safety Analysis Engineering graduate or equivalent, with at least 5 years of experience in nuclear engineering.

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

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

3) The Supervisor of the Offsite Review and Investigative Function shall have experience and tratning which satisfy AN51 N18.1 1971 requirements for plant punagers.

6.1-4 03778/01352 1

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

. GUA0-CITIES DDR-39

2. The Onsite Review and Investigative Function shall be supervised by the Station Manager. g a) Onstte Review and Investigative Function The Station Manager shall: (1) provide direction for the Review and g Investigative Function and appotnt the Technical Staff Supervisor, or other comparably qualified individual as a sentor 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 comprehenstve interdisciplinary review coverage under this function; (4) I independently review and approve the findings and recomunendations developed by personnel performing the Revtew and Investigattve Function: (5) report all findings of noncompitance with NRC requirements, and provide recomunendations to the Assistant Vice President and General Manager Nuclear Stations and l the Supervisor of the Offsite Review and investigative Function; and (6) sutstit to the Offsite Review and Investigative Function for concurrence in a timely manner, those items described in Specification 6.1.G.1.4 which have been approved by the Onsite Revtew and Investigative Function.

The responsibilttles 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, j

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

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

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

$) Investigation of all noncompliance with NRC requirements and shall prepare and forward a report covering evaluation and reconnendations to prevent recurrence to the Assistant Vice President and General Manager Nuclear Stations and to l the Supervisor of the Offstte Review and Investigative Function.

6) Review 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 Offsite Review and Investigative Function.

8) Review of the Station Security Plan and shall submit reconnended changes to the Assistant Vice President and General Manager Nuclear $tations. l

9) Review of the Emergency Plan and station implementing procedures and shall sutuntt recomunended changes to the Assistant Vice President and General Manager Nuclear Stations.

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

11. Review of any unplanned on-site release of radtoactive material to the environs, including the preparation and forwarding of reports covering evaluation recomunendations and disposition of the corrective action to prevent recurrence to the Assistant Vice President and General Manager Nuclear Stations, and to the Supervisor of the Offsite Revtew and Investigative Function.

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

6.1-5 03778/0135Z

.~ -_ - - _ - - - . . - - - - - - - - . - __- _ - __ _-.= - . -- -- - . ~ _ - - _ - - - - - - _

OUAD-CITIES OPR-29

b. Authority The Technical $taff Supervisor is responsible to the Station Manager and shall i make recommendations in a timely manner in all area of review. investigations, and quality control phases of plant maintenance, operation, and administrattve procedures relating to f act11ty operations and shall have the authority to request the action necessary to ensure compliance with rules, regulations and procedures when in his opinion such action is necessary. The station Manager shall follow l such recommendations or select a course of action that is more conservative regarding safe operation of the facility. All such disagreements shall be reported immediately to the Assistant Vice President and General Manager Nuclear Stations and the Supervisor of the Offsite Review and Investigattve Function,

c. Records

1) Reports, reviews, investigations, and recommendations shall be documented with copies to the Assistant Vice President and General Manager Nuclear Stations, the Supervisor of the Of f site Review and Investigative function, the station Manager, and the Manager of Quality Assurance.

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

d. Procedures Written aeninistrative procedures shall be prepared and maintained for conduct of the Onsite Revtew and Investigative function. These procedures shall include the following:

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

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

2) Use of committees when necessary. l

3) Review and approval.

4) Detailed Itsting of items to be reviewed.

$) Procedures for aentnistration of the quality control activities.

6) Assignment of responsibilities.

e. Personnel

1) The personnel performing the Onsite Review and Investigative Function, in addition to the $tation Manager shall Consist of persons having espertise in: l a) nuclear power plant technology, b) reactor operations, c) reactor engineering, d) radiological safety and chemist.

e) instrumentation and control, and f) mechanical and electric systems.

2) Personnel performing the Onstte Review and Investigative Function shall meet minimum acceptable levels as described in ANSI Ml8.1 1971 Sections 4.2 and 4.4 H. Fire Protection Program An independent fire protection and loss preventton program inspection and audit shall be performed at least once per 12 months utilizing either qualified of fsite licensee personnel or an outside fire protection firm.

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

6.1-6 03778/0135Z l

1

QUAD-CITIES DPR-29 5 ,5 -3.

3.

-3 =

==g jjj su a ;

i e

'_i i

_ . air- ion s it!

!.1, E'il

- ia Et

'8-s s -

j[]

,3

.i 1

a- _1

.I n ;

=l g

fi I= [.l l .

llI!

il lI i, s- ."l .-

n

_gs .

5l 1 fu I ja .

il a

la y:1 vi !=.Iv c;= l-! l -

i li i

l!.i -- -

Vi.l.

if

!I,lP_s .li lli

. i!_

! .vi v a yl , 2 -

n!! ll -'

si * - - -

=_ !!; ji sp ,i i -

idi il l !!! !!er __ ..

g:

_. i I

=]=i

,=, ale . . - - . 8 't .

m saE

1 E!

>i ;!,

, :, 'i visi=[=a 5j

I Z, ij l l- <- -

E es li . <! g

" I I' _5i s r I:l

. i I !!= l. I i

!l

,i i"

i s!!

i ' l ll

's iji !i i

Ei i! E ji 11 ylI l

' 'T II f T jI --

5 I! :I

!- 3 Ee .'. il -

1 lel r ,--- .....i.

,---e

i. z-g ,l l l l c .

I

- , i i ! ! ,

1. - 1 _aI i! i 3

]

i 8 1 8 E

{E g g l ,I *I l I "

I ! ! l t

is ;'

T-j:i! -

3 j i

.! .E 1

5[

g[-

e.

!l 1

r1 cure 6.1-1 "l] - CORPORATE ORGANIZATION'

QUAD-CITIES DPR-29

_________________! a 2

s E a

E =8g

i i_.

I

!I g =a s II a

a

_g___ a

, ______________,_g U

E

g i

~

5,. a t la

-3E -----N,g

.s *:

gU ay cp 1

=E aj .

t _g v

q

_g=___________gI g

.! *N 5 g -et t

. N El es l

,___________ g,[I fr gij

! __si zn gg rs-s 113 I

)}]ti s v Sg g.g 5-l

!s - g*s s ja

-v.A .

t; "I i

g ,

gjd__________tt cdw *.g I I Ig ,!g E

E a

E I _____gi

.I

_g___ H --gE g ag ,

E g c "5r It --** Is

! n.

W 5

.c

_gg___________gg g 18 2 0 9 l3 s _ __ __ g r

Quad-Cities Station Organisation Figure 6.1 2

e Qua0-CITIES OPR-29 MINIMUM $HIFT MANNING CHART 8 CONDITION OF ONE UNIT (No Fuel in Second Unit)

Ltcense Initial Fuel Loading Cold Shutdown or Above Cold Category or During Refueling Refueling Shutdown Shutdown Senior Operator l 1 2 I License 2 Operator License 2 2 3 l

i i Rad. Prot. Man 1 Non-Licensed (As Required) 1 2 Shift Technical I Advisor None Required None Required CONDITIDN OF SECONO UNIT (One Unit at Hot Shutdown or at Power)

Ltcense Intttal Fuel Loadtng Cold Shutdown or Above Cold Category or During Refueling Refueling Shutdown Shutdown sentor*

Operator 2 2 2 License Operator

3 3 License 3 1 1 Rad. Prot. Man 1 3+ (As Required) 3 4 Non-Licensed Shift Technical 1 I Advisor 1 CONDITION OF SECONO UNIT (One Unit at Cold Shutdown or Refueling Shutdown)

Initial Fuel Loading Cold shutdown or Above Cold License Shutdown.

Category or During Refueling Refueling Shutdown Sentor*

Operator I 2 License 2 Operator

3 2

License 3 1 i Rad. Prot. Man 1 3* (As Required) 3 3 Non-LtCensed Shift Technical None Required Advisor None Required 1

Assumes each individual is Itcensed on each factitty. During initial fuel loading or during refueling, one senior engineer (1 tatted license) will supervise fuel handling.

8 shif t crew composttion may be less than the minimum 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 shtft crew members provided immediate action is taken to restore the shift crew composition to within the etntmum requirements of Figure 6.1-3.

Figure 6.1-3 03778/01352

OuaG-Cities OPR-39 6.2 PLANT OPERATING PROCEDURES A. Detailed written procedures, including applicable checkoff lists Covering items listed below shall be prepared, approved, and achered to:

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

2. Refueling operations.

3. Actions to be taken to correct specific and foreseen potential malfunctions of systens or components including responses to alarms, suspected primary system leaks, and abnormal reactivity changes.

4. Emergency conditions involvin) potential or actual release of radioactivity -

" Generating Station Emergency Plan

and station emergency and abnormal procedures.

S. Instrumentation operatton which could have an affect on the safety of the fact 11ty.

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

7. Surveillance and testing requirements.

8. Tests and experiments.

9. Procedure to ensure safe shutdown of the plant.

10. Station Security Plan and implementation procedures.

t

11. Fire Protection Program implementation.

l 12. 00CM implementation.

13. PCP taylementation.

14. Working hours of the Shif t 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.

B. Radiation control procedures shall be maintained, made available to all station personnel, and adhered to. The procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20. This radiation protection program shall be organized to meet the requirements of 10 CFR 20.

C. 1. Procedures for items identified in Specification 6.2-A and any changes to such procedures shall be reviewed and approved hy the Operating Engineer and the Technical Staff Supervisor in the areas of operetton or fuel handling and by Asst. Supt.

Maintenance and Technical Staff Supervisor in the areas of plant maintenance and plant inspection. Procedures for items identified in Specification 6.2.5 and any changes to such procedures shall be rev'ewed and approved by the Technical Staff Supervisor and the Radiation-Chemistry Supervisor. At least one person approving each of the above procedures shall hold a valid sentor operator's license. In addition, these procedures and changes thereto naast have authorization by a Station Superintendent before being implemented. l

! 2. Work and instruction type procedures which tmplement approved maintenance or modirication 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 work shall be so approved only if procedures referenced in the " Maintenance Modification Procedure

have been approved as required by 6.2.A. Procedures which do not fall within the requirement of 6.2.A or 6.2.5 may be approved by the Department Heads. ,

i

0. Temporary changes to procedures 6.2.A and 6.2.0 above may be made provided:

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

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

6.2-1 03778/01352 i

Quad-Cities DTR-29

3. The change is documented, reviewed on the Onstte Review and Investigative Function, and approved by the Station Manager within 14 days of tmplementation. l E. Drt11s of the emergency procedures described in Specification 6.2.A. shall be conducted in accordance with the GSEP Manual.

6.3 REPORTA4LE EVENT ACTION A. The following actions shall be taken for Reportable Events:

1. The Consnission 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-$tte Review Consnittee, 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.

1 1

i 6.3-1 03770/01352

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

Quad-Cities ope-29 6.4 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT !$ EXCEEDED If a safety limit is erceeded the reactor shall be shut down tamediately. and reactor operatton shall not be resumed untti authorized by the NAC. 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 Spectf tcations 6.1.G.I.a. and 6.1.G.2.a and a separate report for each occurrence shall be prepared in accordance with Spectftcation 6.3.A.I. l 9

l l

6.4=I 01779/013$2

Ouad-Cities OPR-29 6.5 PLANT OPERATING RECORD 5 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. tncluding power levels and periods of operatton at each power level.

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

3. Records and reports of reportable events and safety limit occurrences. l 4 Records and periodic checks, inspection and/or calibrations performed to verify that the surveillance requirements (see Section 4 of these specifications) are being met (all equipment failing to meet surveillance requirements and the corrective action taken shall be recorded).

5. Records of changes made to the equipment or revtews of tests and experiments to comply with 10 CFR 5s.59.

6. Records of radtoactive shipments.

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

8. Records of changes to operating procedures.

9. Shift engineers' logs, and

10. Byproduct matertal inventory records and source leak test results.

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

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

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

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

4. Ur. dated, corrected, and as built drawings of the plant.

5. Records of plant radiation and contamination surveys.

6. Records of offsite environmental monitoring surveys.

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

8. Records of radioactivity in 11guid and gaseous wastes released to the environment.

9. Records of transient or operational cycling for those components that have been des 10ned to operate safely for a Itmtted numoer of transient or operational cycles.

10. Records of individual staff memeers indicating 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 offstte and onsite review and audit functions.

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

6.5-1 03778/01352 1

. Quad-C it ies OPR-39 e.6 REPORTING REQUIREMENTS i

In addition to the applicable reporting requirements of Title 10. Code of Federal Regulations, the following tdentified reports shall be sutunttted to the aministrator of the appropriate Regional Office unless otherwise noted.

i A. Routine Reports

1. Startup Report A sungnary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating Itcense. (2) amen ment to the license involving a planned increase in power level. (3) Installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perf ormance 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 required to

' obtain satisfactory operatton shall also be described. Any additional specific details required in Itcense conditions based on other comunitments 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 comunencement of consnerctal power operatton, or (3) 9 months following inittal criticality, whichever is earitest. If the startup report does not cover all three events (i.e.. intttal criticality, completton of startup test program, and resumption or comunencement of

, comunerctal power operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.

i

(

i i

i, i

1 6.6-1 l

i 03778/01352

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

_____,__,.,_____,m_._.. _ _ _ _ _ _ . , . _ _ _ _ _ _ _ _

yww,,, - __. . .,.,_._..,_.,---___.,,_.,,-_.,_.,,,..,,,.m-__. . . , _ . _ ., , , _ .,

. Quad-Cities OPR-29

2. A tabulation shall be submitted on an annual bests of the number of station utt11ty, 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: thts tabulation supplements the requirements of Section 20.407 of 10 CFR 20).

e.g.. reactor operettons and surveillance inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing. and refueltng. The dose assignments to various duty functions may be estimates based on pocket dostmeter. TLO.

or ft1m badge measurements. Small esposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate. at least 80% of the total dele body dose received from external sources shall be assigned to spectf te major work functions.

3. Monthly Operating Report Routine report of operating statistics and shutdown expertence shall be submitted on a monthly basis to the Otrector. Of fice of Management Information and Program Control.

U.S. Nuclear Regulatory Cennission. 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 00CM shall be sutettted 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 revtewed and accepted by the onstte review function. If such change is re-evaluated and not installed, nottftcation of cancellation of the change should be provided to the NRC.

's 6.6 2 03778/01352

=

Quad-Cities OPR-29

8. Unteue Reporting Requirements

1. Radioactive Effluent Release Report ($emi-Annual)

A samt-annual report shall be submitted to the Comission within 60 days af ter January 1 and July 1 of each year specifying the quantity of each of the radtenac1 tees released to unrestricted areas in liquid and gaseous eff1t,ents during the previous 6 months. The format and content of the report shall be in accordance wit % Regulatory Guide 1.21 (Reviston 1) dated June. 1974 Any changes I 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 i program (Table 4.8-4) shall be submitted prior to May 1 of each year. The content I of the report shall include:

a. Results of all environmental measurements sumartzed 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 esplaining the reasons for the missing results. Sumeries. Interpretations, and analysis of trends of the results are to be provided.

b. As assessment of the monitoring results and radiation dose via the principal pathways of espesure resulting from plant emissions of radtoactivity including the maximum noble gas game and beta air doses in the unrestricted area. The assessment of radiation doses shall be performed in accordance with the Of f site 00se Calculation Manual (00CM).

c. Results of the census to determine the locations of nearest residences and of nearby animals producing milk for human consumption.

(Table 4.8-4).

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

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

wind direction and atmospheric stabiltty.

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

l l

{

l l

l 6.6-3 03778/01352

Quad-Cities DPR-29

3. If a confirmed measured radionuclide concentratton in an environmental sampling medtum averaged over any calendar quarter samp1tng pertod exceeds the reporting level gtven in Table 4.8-5 and if the radtoactivity is attributable to plant operation, a written report shall be submitted to the seministrator of the NRC l Regional Office, with a copy to the Director. Office of Nuclear Reactor l Regulation, within 30 days from the end of the guarter.

a. When more than one of the radionuclides in Table 4.8-5 are detected in the medium, the reporting level shall have been exceeded if ti R.L.1

)1 where C1 is the average guarterly concentratton of the 4 th radionuclide in the medium and RL 1s the reporting level of radionuclide 1.

b. If radionucitees 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 10 CFR

50. Appendix 1.

c. This report shall include an evaluation of any release conditions, environmental f actors, or other aspects necessary to esplain the anomalous effect.

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

l 6.6-4 1 1

GuaG-Cittes OPR-39 TABLE 6.6-1

$PECIAL REPORTS Speciftcatton ggga Rafarance tuhaittal Data

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

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

c. Materials radiation surveillance 4.6.B.2 After each specimen removal specimens and completton of analyses.

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.

3.8.0.

6.6.C.1 N0111

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

2. Thts report ts required only if the tests reveal the prasence of 0.005 microcurtes or more of removable contamination.

er 6.6-5 0377B/0135Z

~. _ ._ _ --- _ .

Qua d-r it les OPR-2' e.7 ENVIRONMENTAL QuaLIFICAf!0N A. All safety-related electrical equipment in the fact 11ty shall be q+titfied in accordance {

with the provisions of: Assistant of c p rattig Reactors " Guidelines for tvaluating' Environmental Qualification of Class It Liectrt6a1 Equipannt is operattig Reactors" (004 Guideltnes): or. NUREG-Olss " Interim Staff Position on inviron= ntal Qualtftcation of Safety-Related Electrical Equipment". December 1079. Coates of tnest documents are attached to Order for Modification of Lttense OPR 29 dated October 24. 1940.

b. Complete and auditable records nest be available .ud maintatred et a central location which describe the environmental qualiftCatton meth d u:ed fr.r all safety-related electrical equipment in sufficient dotatt to document the degree of compliance with the 004 Guidelines or mUREG-0588. Such recores sMuld be updated and m41ntained current as equipment is raptaced. Further tested, or otherwise further qualif ted.

6.7 1 03775/01352

,,_,_--_-.___.e, - - - - _v.m-r r-, - _y-

Cuad-Cities CPe-29 6.8 Offsite Oose Calculation Manual (00CM)

A, The 00CM shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid affluents and in the calculation of gaseous and 11guld effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCO's contained in these Technical specifications. Methodologies and calculational procedures acceptable to the Comission are contained in NUstG-0133.

The 00CM shall be submitted to the Consnission at the time of proposed Radiological Effluent Technical Specifications and shall be subject to review and approval by the Comentssion prior to implementation.

8. Licensee initiated changes to the 00CM may be made provided the change:

1. Sna11 he submitted to the Consnission by inclusion in the Monthly Operating Report pursuant to Specification 6.6.A.3. within 90 days of the date the change (s) was made effective and shall contain:

a. Sufficiently dotatted information to support the change. Information submitted should consist of a package of those pages of the 00CM to be changed together with appropriate analyses or evaluations justifying the changes (2);

t, . A determination that tne change will not reduce the accuracy of reliability of dose calculations or setpoint determinations; and

c. Documentation of the fact that the change has been reviewed and found acceptable by the ensite review functions.

2. Shall become effective upon review and acceptance by the onstte review function.

6.8-1 03779/01352

e Quad-Cities DDR-29 6.9 Process Control Program (PCP)

A. The PCP shall contain the sampling, analysis, and formulation determination by which solidification of redtoactive wastes from liquid systems is assured.

B. The PCP shall be approved by the Commission prior to implementation.

C. Licensee initiated changes may be sede to the PLP provided the change:

1. Shall be submitted to the Connission in the Radioactive Effluent Release Report for the period in which the change was made and and shall contain:

a. Sufficiently detailed information to support the change:

b. A determination that the change did not reduce the overall conformance of the solidtfied waste product to existing criteria for solid wastes; and

c. Documentation that the change has been reviewed and found acceptable by the onsite review function.

2. Shall become effective upon review and acceptance by the onsite review function.

i s

6.9-1 0377B/01352

. 's A

t

Quad-Cities OPR-29 6.10 Major Changes to Radioactive Waste Treatment Systems (Liquid. Gaseous. Solid)

A. Licensee initiated nujor changes to the radioactive waste systems may be made provided:

1. The change is reported in the Monthly operating Report for the period in which the evaluation was reviewed by the onsite review function. The discussion of each change shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

b. Sufficient detailed information to support the reason for the change;

c. A detatled description of the equipment, components, and process involved and the interfaces with other plant systems;

d. An evaluation of the change which shows the pred1Cated releases of radioactive materials in liquid and gaseous ef fluents and (or quantity of solid waste that differ from those previously predicted in the license application and amendments);

e. A comparison of the predicted releases of radioactive materials in liquid and gaseous effluents and in solid waste to the actual releases for the period in which the changes were made;

f. An estimate of the exposure to plant operating personnel as a result of the change; and

g. Documentation of the fact that the change was reviewed and found acceptable by the onsite review function.

2. The change shall become effective upon review and acceptance by onsite review function.

A 6.10 03775/0135Z

ATTACHMENT 2 Proposed Changes to DPR-30 Technical Specifications 1119K

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 Unrestricted 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 v

Amendment No.

6312N

QUAD-CITIES DPR-30 TECHNICAL FPECIFICATIONS APPEiDIX 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 Betwwen 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 ,

Amendment No, vi

QUAD-CITIES DPR-30 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 greater than 2120F

2. Cold Shutdown 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 assembly power which causes some point in the assembly to experience transition boiling to the assembly power at the reactor condition of interest as calculated by application of the GEXL correlation (reference NEDO-10958).

CC. Minimum Critical Power Ratio (MCPR) - 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. A maximum allowable extension not to exceed 25% of the surveillance 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. Maximum Fraction of Limiting Power Density (MFLPD) - 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 MWth.

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

1.0-4 Amendment No.

. QUAD 4TTIES - d . .* . . . . . e .- .- t. .

DPR- 30 3.12/4.12 FIRE PROTECTION SYSTDiS. ,

LIMITING CONDITIONS FOR OPERATIONS SURVEILLANCE REQVIRDIENTS Applicability: . Applicability: ,

~

Applies to the fire protection systems whenever the Applies to the periodic testin; requirements of the fire equipment or systems being protected are required to protection systems whenever the fire protection be operable. systems are required to br operable.

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

. maintained dunng all modes of facility operation.

e SPECIFICATIONS A. Fire DetectionInstrumentation A Fire Detection Instrumentation

1. As a minimum, the fire detection instru. 1. Each of the' fire detectiert instruments mentstion for each fire detection zone given by Table 3.121 shall be demon.

shown in Table 3.12-1 sh:11)e operable strated operable at least '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. All non-supervised ceuits , shall be

- 2. With the number of operable fire dette. demonstrated operaole onec per month.

tion instruments less than required by Table 3.121;

s. Perform an inspection of affected zone, withirt I hour. Perform addi-

. tional inspecuens at least once per hour except in inaccessible areas. -

b. Restore.the inoperable instrument (s)

,to operable status withm 14 days, or ,

preparetand submit a report to the -

Commission pursuant to Specificauon .

l 6.3.A.1 !within the next 30 days out-Aing the cause of the malfunction, the acnon taken, and the plans for restormg the instrument (s) to oper- '

~] ,

able status. ,

t 3. ne provisions of spe:ification 3

3.0.A are not applicable.

9 3.12/4.12 -1.

p **

b

QUAD. CITIES DPR-30

(.

i B. Fire Suppression Water Synem B. Fire Suppression Water System

1. The Fire Suppression Water Synem shall 1. The Fire Suppresnon Water System shall be operable at all tmes with; be demonstrated operable:

a. Two (2) high pressures pumps each a. At least once per 31 days on a stag.

with a capacity of 2000 gpm with gered test bans by narting each pump their discharge aligned to the fire and operatmgitforatleast 20 mmutes

- suppression header. on rec 2rculanon flow.

b. Automatic initiation logic for each b. At least once per 31 days by verifymg fire pump. that each valve (manual, power

c. An operable flow path capable of P.* *

' ""* ** ***) '" D ' N

pad 2s In de c neet ponion.

takmg sucuon from the Mitutupp River and transferrms the water c. At lean onz per year by performance through distribution pipmg with oper- of a synem Dush.

able sectonahung control or isolation

d. At least once per year by @g end valves to the yard hydrant curb valves testab.le valve in the flow path through and the front valve ahead of the water

- * * * * "* "*N' * * * "

flow alarm device on each spnnkjer, I'*"*

hose stand pipe, or spray system nser.

e. At Icast nce Per operating cycle

2. With moperable fire pumps or associated water supply, restore the inoperable (1) By performmg a system func.

equipment to operable status withm 7 tonal ten which includes days, or prepare and submst a report to the Commission pursuant to Spec: fica-l tion 6.3.A.1 withm the neat 30 days out-lirung the plans and procedures to be used to provide for the loss of redundancy m-this system.

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

a. Es:ablish a backup Fire Suppression Water System.

b. Notify- the Commisnon pursuant to l Specification 6.3. A .1 outlinmg the acuons taken. the cause of the in.

operability, and the plans and schedule for restormg the synem to operable status.

4. If the requirements of Specificauon 3.12.B.3.a cannot be met, an orderly shut i down shall be initiated, and the reactor shall be in a cold shut down condiuon withm 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.12/4.12 2 4 ;

. ~._ __

QUAD-CITIES DPR-30 simulated automatic actuation of the system throughout its opera-ting sequence and verifying that each automatic valve in the flow path suustes to its correct position.

(2) By verifying that each pump dev.elops at leas' 2000 gpm at a system 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 least once per 3 years by perform-ing flow tests of the system in accor-dance with Chapter 5, kuon '1, NFPA Fire Protection Handboct C. Sprinkler Systems C. Sprinkler Systems De sprinkler systems given in Table 1. At least once per yeai by cycling each 1.

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 once complete eye'. of full travel. ,

protected is required to be operable. 7 yy

2. With the cable tun'nel sprinkler system a. A synem functional test shall be p:r-inoperable, establish a contmuous fire formed which includes simulated auto-watch with back up fire suppression matic actuation of the system and equipment for the unprotected area verifying that the automatic valves in within I hour. the flow path actuate to their cor-With any other sprinkler system in- rect positions.

3.

operable, establish back up fire sup- b. De sprinkler headers shall be in-pression within I hour and inspect the spected to verify their integrity.

l area twice per shift.

! c. Each nozzle shall be inspected to

4. Restore the system to operable status g within 14 days, or prepare and submit a report to the Commission pursuant 3. At least once per 3 years by performing an air flow test through each open head

] to Specification 6.3. A.1 within the next 30 days outlining the cause of spray /spnnkler header and venfying each ,

I inoperability, the action taken, and open head spray /spnnkler nozzle is un-the plans for restoring the system to obstructed.-

operable status.

5. 'Ite provisions of specificctieni

3.0.A are not applicable. ,

t e

' ' ~ ~~ ~'

i 3.12/4.12-3 l l

l

. , .QUAD. CITIES , . , . .. . . . . . .c, . . . . .-s.. .

DPR-30 D. CO2 Systems i D. CO 2Systems

1. The CO Storage Tank shall have a mini- 1. At ienst 6nce per 7 days the CO2Storage .

2 mum stand by level of 50 percent and a Tank level.and pressure will be verified, minimum pressure of 250 psig. 7 g g, g

2. The CO Synen s given in Table 3.12 3 system valves and asmeisted dampers will 2

shall be operable.- . be verifwd to actuate automatically and

- " I* ^ * ***** ****

3. Specifications 3.12.D.1 and 3.12.D.2 to verify flow from each nozzle.

above apply when the equipment in the areas given in Table 3.12.3 is required to be operable.

4. With a CO 2System inoperable, establish backup fire suppression equipment for the unprotected ares (s) witlun I hour and inspect the ares twice per shift. ,

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

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

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

If. actuated, the storage tank will be 6.

- ; restored to greater than the minimum level within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

~

1 *the Provisions of Specificatien 3.0.A are not applicable.

' ~

5.' ' Fire Hose Stations E. Fire Hose Stations

1. The Fire Hose Stations given in Table 1. At least once per 31 days,a visualinspec.

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

peraWe.

2. At least once per operating cycle, the

2. With a hose station inoperable. route an ho'se will be removed for inspection and additional equivalent capacity hose to the reracked. Degrsded gaskets in the coup-unprotected area frem an operable hose lings will be rept:ced, station within I hour. 3. At least once per 3 years, each hose sta.

tion valve will be partially opened to

3. the provisions of specification 3.0.A are not applicable, verify valve operability and no blockage.

4 At least once per 3 years a hydrostatic test will be conducted on each hose at

- a pressure at least 50 psig greater than the maximum ' pressure available at the hose station. .

F Penetration Fire Barriers F. Penetration Fire Batriers

1. All penetration fire barriers protecting 1. Each of the penetration fire barrier shall safety related areas sh.tll be intact except be verified to be intact by. visual in.

as stated in Specificanon 3.12.F.2. spection:

3.12/4.12 -4

m .. .

QUAD CITIES DPR-30 6.0 ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION, REVIEW, INVESTIGATION AND AUDIT A. The Station Manager shall have overall full-time responsibility for safe operation of the facility. During periods when the Station Manager is unavailable. he shall designate this responsibility to an established alternate who satisfies the ANSI N18.1 of March 8, 1971 experience requirements for plant manager.

8. The organization chart of the corporate management which relates to the operation of this station and the normal functional organization chart for operation of the station are shown in . Figures.6.1-1 and 6.1-2. respectively.

C. The shift manning for the station shall be as shown in Figure 6.1-3. The Assistant Superintendent Operating. Operating Engineer. Shif t Engineers. and Shif t Foremen shall have a senior operating license. The Fuel Handling FSFeman has a limited Senior Operating License. The Assistant Vice President and General Manager Nuclear Stations on the corporate level has responsibility for the Fire Protection Program. The Assistant Superintendent Maintenance will be responsible for implementation of the Fire Protection Program. A fire brigade of a least 5 member shall be maintained on-stte at all times.

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

D. Qualifications of the station sunagement and operating staff, excluding the Rad-Chem supervisor and the Radiation / Chemical Technicians, shall meet minimum acceptable levels as described in ANSI N18.1. " Selection and Training of Nuclear Power Plant Personnel" dated March 8. 1971. The Rad-Chem Supervisor or the Lead Health 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 minimum acceptable level for " Technical Manager" as described in Section 4.2.4 of ANSI 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 analysis of the plant for transients and accidents.

The Radiation / Chemical Technicians shall have successfully completed the established Radiation / Chemical Technician training program, and shall have at least a total of one year of general power plant, chemical, or radiation protection experience, or equivalent training. The Radiation / Chemical Technicians shall meet the criteria for " Individuals Qualified in Radiation Protection Procedures", as described in the D. L. Ziesunn (NRC) letter to R. L. Bolger (Ceco.) dated March 15. 1977. The Radiation / Chemical Technician training program consists of the following:

1. Satisfactory completion of a 12-week academic program. Topics of this course include mathematics, nuclear physics, radioactive decay, chemistry, sampling techniques, reactor coolant parameters, radiation exposure, shielding, biological effects of radiation exposure, radiation survey techniques, personnel monitoring, and emergency procedures.

2. Satisfactory perforsunce on a comprehensive examination following completion of acadmeic training.

3. On-Shif t training under the supervision of a qualified Radiation / Chemical Technician, j E. Retraining and replacement training of Station personnel shall be in accordance with ANSI N18.1 " Selection and Training of Nuclear Power Plant Personnel", dated March 8, 1971.

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

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

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

1. The Supervisor of the Offsite Review and Investigative Function shall be appointed by 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 03778/01352 l

l

QUAD-CITIES OPR-30

a. Offsite Review and Investigative Function The Supervisor of the Offsite 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 complement of more than one participant who collectively posses background and qualifications in the subject matter under review to provide comprehensive interdisciplinary review coverage under this function (4) independently review and approve the findings and recompendations developed by personnel performing the review and investigattve 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. l Manager of Quality Assurance, and the Vice President of Nucicar Operations. l During periods when the Supervisor of Offsite Review and Investigative Function is unavailable he 55411 designate this responsibility to an established alternate, who satisfies the formal training and experience requirements for the Supervisor 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, aquipment, or systems as described in the safety analysis report and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question. Proposed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of Quality Assurance.

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

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

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

7) Reportable events. l

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

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

10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor. Station Manger. Assistant Vice President and General Manager Nuclear Stations, and Manager of Quality Assurance. ,

b. Audit Function The Audit Function shall be the responsibility of the Manager of Quality Assurance independent of the Production Department. Such responsibility is delegated to the Director of Quality Assurance for Operating and to the General Supervisor Quality '

Assurance Maintenance for maintenance quality assurance activities.

Either shall approve the audit agenda and checklists the findings and the report of each audit. Audits shall be performed in accordance with the Company Quality Assurance Program and Procedures. Audits shall be performed to assure that safety-related functions are covered within a period of 2 years of less as designated below.

i

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

6.1-2 03778/01352 l

a Qua0-CITIES DFR-30

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 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 Criteria of Appendix "B" 10 CFR 50.

5) Audit of the Facility Emergency Plan and implementing procedures at 4; Fir onct per year.

6) Audit of the Facility Security Plan and implementing procedures at least once per year.

7) Audit onstte and offstte reviews.

8) Audtt of Facility Fire Protection Program and implementing procedures at least once per 24 months.

9) The radiological environmental sonitoring program and the results thereof at least once per 12 months.

10) The 00CM and implementing procetares at least once per 24 months.

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

12) Report all findings of noncompliance with NRC requirements and recommendations 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 Offsite Review and l Investigative Function reports to the Chairren and President. Etther the Manager of Quality Assurance or the Supervtsor of the Offstte Review 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. Records

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

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

e. Procedures Written administrative procedures shall be prepared and maintained for the of f sitt reviews and investigative functions described in Specifications 6.1.G.I.a. Those procedures shall cover the following:

1) Content and method of submtssion of presentations to the Supervisor of the Offsite Review and Investigative Function.

2) Use of committees and consultants.

3) Review and approval.

4) Detailed listing of items to be reviewed.

5) Method of (1) appointing personnel. (2) performing reviews. investigations.

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

6) Determining satisfactory completion of action required based on approved !

findings and recompendations reported by personnel performing the review and l investigative function.

6.1-3 I 0377B/0135Z I

- i

. QUAD-CITIE5 DP3-30

f. Personnel

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

a) nuclear power plant technology.

b) reactor operations, c) utiltty operations.

d) power plant design, e) reactor engineering, f) radiological safety, g) reactor safety analysis, h) instrumentation and control.

1) metallurgy, j) any other appropriate disciplines required by unique characteristics of the facility.

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

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

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

c) Utt11ty Operations Engineering graduate or equivalent with at least 5 years of experience in utility operation and/or engineering.

d) Power Plant Design Engineering graduate or equivalent with at least 5 years of experience in power plant design and/or operation, e) Reactor Engineering Engineering graduate or equivalent. In addition, at least 5 years cf experience in nuclear plant engineering, operation. 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 b radiation control and safety.

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

h) Instrumentation and Control Engineering graduate or equivalent with at least 5 years of experience 1.1 instrumentation and control design and/or operation.

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

3) The Supervisor of the Offsite Review and Invettigative Function shall have experience and training which satisfy ANSI N18.1-1971 requirements for plant managers.

6.1-4 03778/0135Z

'. GUAD-CITI25 DPR-30

2. The Onsite Review and Investigative Function shall be supervised by the Stat 1or.

Manager.

a) Onstte Review and Investigative Function The Station Manager shall: (1) provide direction for the Review and g Investigative Function and appoint the Technical Staff Supervisor, or other comparably qualified individual as a sentor participant to provide appropriate directions, (2) approve particicants 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 recomendations developed by personnel performing the Review and Investigattve Function; (5) report all findings of noncompliance with NRC requirements, and provide reconynendations to the Assistant Vice President and General Manager Nuclear Stations and l 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 Specification 6.1.G.I.a which have been approved by the Onsite Review and Investigative Function.

The responsibilities of the Personnel performing this function are stated below:

1) Review of (1) procedures required by Specification 6.2 and changes thereto and (2) any other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety. l

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

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

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

5) Investigation of all noncompliance with NRC requirements and shall prepare and forward a report covering evaluation and reconenendations to prevent recurrence to the Assistant Vice President and General Manager Nuclear Stations and to [

the Supervisor of the Offsite Review and Investigative Function.

6) Review 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 Offstte Review and Investigative Function.

8) Review of the Station Security Plan and shall submit reconsnended changes to the Assistant Vice President and General Manager Nuclear Stations. l

9) Review of the Emergency Plan and station implementing procedures and shall submit recomended 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-stte release of radioactive material to the environs, including the preparation and forwarding of reports covering evaluation reconinendations and disposition of the corrective action to prevent recurrence to the Assistant Vice President and General Manager Nuclear Stations, and to the Supervisor of the Offstte Review and Investigative Function.

12. Review of changes to the PCP and ODCH, and major changes to the radwaste treatment systems.

6.1-5 03778/01352

. OVAD-CITIES DPR-30

b. Authority The Technical Staff Supervisor is responsible to the Station Manager and shall make recomendations in a timely manner in all area of review. investigations, and quality control phases of plant maintenance, operation, and a ministrative procedures relating to facility operations and shall have the authority to request the action necessary to ensure compliance with rules, regulations and procedures when in his opinion such action is necessary. The Station Manager shall follow l such recomendations or select a course of action that is more conservattve regarding safe operation of the facility. All such disagreements shall be reported imediately to the Assistant Vice President and General Manager Nuclear j Stations and the Supervisor of the Offsite eqview and Investigative Function. I

c. Records

1) Reports, reviews investigations, and reconsnendations 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 i Manager, and the Manager of Quality Assurance. I l

2) Copies cf all records and documentation shall be kept on file at the station, j

d. Procedures Written a ministrative procedures shall be prepared and maintained for conduct of the Onsite Review and Investigative function. These procedures shall include the

~

following:

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

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

2) Use of comittees when necessary.

3) Review and approval.

4) De' tailed listing of items to be reviewed.

5) Procedures for administration of the quality control activities.

6) Assignment of responsibilities.

e. Personnel

1) The personnel performing the Onsite Review and Investigative Function, in addition to the Station Manager shall consist of persons having expertise in: l a) nuclear power plant technology, b) reactor operations, c) reactor engineering, d) radiological safety and chemist, e) instrtunentation and control, and f) mechanical and electric systems.

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

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

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

6.1-6 0377B/01352

QUAD-CITIES DPR-30 3 E3 23.

.s.: ;:1 ::s '

, . . . . . . . . 555 stil

~

l:11 . .

I i \

s i

i kugs.

ar E s.:

I l- I!

Et '

Ii s 1 -

- E. .I 13

[

li!

!ls i

1 i

EE gII - '

E!

r:.

ll m fg iE ag .

. _... ___......,_9 yi._ g- -

,Ip i si Eji i 4l1 s T -

la It! ri i=.g - - .l! ,,

- ;E I

!! fil if:= - --

tI}g.* [1 - - "

IE !

1, ' :I ll l11l i

II yg- !-

j i C i-n!: !! i 3.s' !!g ll i i!!

e ll

~

!! ~' ~' I li Il lsi 553 l

' . 8.13... 3l

- , 1 l

_ ilc.j*la' . . . . .li .. !.iy I-3

-iE.I . !! l' is ng *IlI I

l li-.--- I 1

is l1 .

I g

~

ll li li 'i i!j 5 I i[ g -

e i

i i si, i , in

.i ll li i ?. ! Ei

!.: la 1g. I .

-i E *I. L, II

'. s i :

!: y ;-

- jE -- t -

E]" -

i I! 05 iTT T " 'T .

1 lel

~ll Ee 5

. . . .! .! I_"j i I I I I

-Il ;

Si- ., . . . ..

_ . , _ _ i ,

-ll e

l

- _l, il i

' [

l l. i . i.

8 13 [3 g g i

r- ,I

. gi' 2,

! ! ! 5

]sg -

is i l.

1 8 5 8 .1 l 4. .

g[- :gl E,

g l FIGURE 6.1-1 CORPORATE ORGANIZATION

QUAD-CITTES DPR-30 EE

$ Ta ci 5*aI! 8l i_

oa

's I=al g

E 35

_r___ _a ilt

, ______________t_r,-

2 I .e, d gg _3g

_____g!

g .g g_ g

R

_u =E_

t _I g

en _.e Q 5 IC s, _____ g gg

,i l

. fr

___________ = 1 :

US l

! __di gg sii et-E I.1I sg 5 I __e_w s- -i}5

_ =,

y ag-31 E _ tt

] E

_"gEij__________gij . .8 E. 3 5 - gs E 2 mk .k a

_g___ E --gg, _____gi

.g ,

8 5

i E I,: --E.jE.

aI II _

- Q E aG

_gg___________Ig:

~

$ 58 t 2 lE E _____=g w

l l

Quad-Cities Station Organisation ;

Figure 6.1-2

., e -

. QUAD-CITIES OP3-30 MINIMUM $HIFT MANNING CHARTS CONDITION OF ONE UNIT (No Fuel in Second Unit) l License Initial Fuel Loading Cold Shutdown or Above Cold i Category or During Refueling Refueling Shutdown Shutdown Senior i Operator <

Ltcense 2 1 2 l

Operator License 2 2 3 l

Rad. Prot. Man I 1 1 Non-Licensed (As Required) I 2 Shift Technical Advisor None Required None Required 1 CONDITION OF SECOND UNIT (One Unit at Hot Shutdown or at Power)

License Initial Fuel Loading Cold Shutdown or Above Cold Category or During Refueling Refueling Shutdown Shutdown Senior

Operator License 2 2 2 Operator

License 3 3 3 Rad. Prot. Man 1 1 1 Non-L1 Censed 3+ (As Required) 3 4 Shttt Technical Advisor 1 1 1 CONDITION OF SECOND UNIT (One Unit at Cold Shutdown or Refueling Shutdown)

Ltcense Initial Fuel Loading Cold Shutdown or Above Cold Category or During Refueling Refueling Shutdown Shutdown Senior

Operator License 2 1 2 Operator

License 3 2 3 Rad. Prot. Man 1 1 1 Non-Licensed 3+ ( As Required) 3 3 Shift Technical Advisor None Required None Required 1

Assumes each individual is licensed on each facility. During initial fuel loading or during refueling, one senior engineer (limited license) will supervise fuel handling.

8 Shif t crew composition may be less than the minimum 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 immediate action is taken to restore the shif t crew composttton to within the minimum requirements of Figure 6.1-3.

Figure 6.1-3 l 03778/0135Z

Quad-Cities DPR-30 6.2 PLANT OPERATING PROCEDURES A. Detailed written procedures, including applicable checkoff lists covering items listed below shall be prepared, approved, and adhered to:

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

2. Refueling operations.

3. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary system leaks, and abnormal reactivity changes.

4

4. Emergency conditions involving potential or actual release of radioactivity -

" Generating Station Emergency Plan" and station energency and abno-mal procedures.

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

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

7. Surveillance and testing requirements.

8. Tests and superiments.

9. Procedure to ensure safe shutdown of the plant.

10. Station security Plan and implementation procedures.

II. Fire Protection Program implementation.

12. ODCM implementation.

13. PCP teplementation.

14. Working hours of the Shif t 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.

B. Radiation control procedures shall be maintained, made available to all station personnel, and adhered to. The procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20. This radiation protection program shall be organized to meet the requirements of 10 CFR 20.

C. 1. Procedures for items identified in Spectftcation 6.2-A and any changes to such procedures 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. Supt. l Maintenance and Technical Staff supervisor in the areas of plant maintenance and plant l inspection. Procedures for items identified in Specification 6.2.5 and any changes to such procedures shall be reviewed and approved by the Technical Staff Supervisor and the Radiation-Chemistry Supervisor. At least one person approving each of the above procedures shall hold a valid senior operator's license. In addition, these procedures and changes thereto must have authortzation by a Station Superintendent l before being implemented.

2. Work and instruction type procedures which implement 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 Precedure" utilized for safety related work shall be so approved only if procedures referenced in the " Maintenance Modification Procedure " have been approved as required by 6.2.A. Procedur~. which do not fall within the requirement of 6.2.A or 6.2.5 may be approved by the Department Heads.

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

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

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

6.2-1 0377B/01352

Qua d-C 1t les OPR-30

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

and approved by the Station Manager within 14 days of implementation. l E. Drills of the emergentcy procedures described in Specification 6.2.A. shall be conducted in accordance with the GSEP Manual.

6.3 REPORTABLE EVENT ACTION A. The following actions stall 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 Prestdent and General Manager. Nuclear Stations.

1 6.3-1 03778/01352 i

i Quad-Cities OPR-30 ,

i 6.4 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED If a safety limit is exceeded, the reactor shall be shut down immediately, and reactor operation shall not be resumed untti authertzed by the NRC. The conditions of shutdown shall be gramptly reported to the Assistant Vice President and General Manager Nuclear Stations or l ht, designated alternate. The incident shall be reviewed pursuant to Specifications 6.1.G.I.a. and 6.1.G.2.a and a separate report for each occurrence shall be prepared in accordance with Specification 6.3.A.I. l 6.4-1 03778/0135Z

Quad-Cities DPR-30 6.5 PLANT OPERATING RECORDS A. Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained for at least 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 activities. including inspection and repair, regarding principal items of equipment pertaining .o nuclear safety.

3. Records and reports of reportable events and safety limit occurrences.

4. Records and periodic checks. inspection and/or calibrations performed to verify that the surveillance requirements (see Sec'ico 4 of these specifications) are being met (all equipment failing to meet surveillance requirements and the corrective action taken shall be recorded).

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

6. Records of radtoactive shipments.

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

8. Records of changes to operating procedures.

9. Shift engineers' logs, and

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

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

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

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

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

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

5. Records of plant radiation and contamination surveys.

6. Records of offsite environmental monitoring surveys.

7. Records of radiation exposurc for all plant personnel including all contractors and visttors to the plant. in accordance with 10 CFR 20.

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

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 memeers indicating qualifications, experience training.

and retraining.

II. Inservice inspections of the reactor coolant system: and 11!. Minutes of meetings and results of reviews and audits performed by the of f stte and onsite review and audit functions.

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

6.5-1 03778/01352 1

- . =.

Quad-Cities DPR-30 6.6 REPORTING REQUIREMENTS In addition to the applicable reporting requirenents of Title 10. Code of Federal Regulations, the following identified reports shall be submitted

o the administrator 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 license. (2) amendment to the 1; cnse involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) meaifications 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 required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other conettments 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. er (3) 9 months following initial criticality, whichever is earliest. If the startup report does not cover all three events (i.e.. initial criticality, completion of startup test program, and resenption or connencement of commercial power operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.

6.6-1 03778/01352

Quad-Cit 1Qs OPR-30

2. A tabulaticn shall be submitted on an annual basis of ihe number of station utility.

and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job 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. 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 CDCM 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 period in which the evaluation was reviewed and accepted by the onsite review function. If such change is re-evaluated and not installed, notification of cancellation of the change should be provided to the NRC.

6.6-2 03778/0135Z

i Quad-Cities DPR-30 B. Unique Reporting Requirements

1. Radioactive Effluent Release Report (Semi-Annual)

A sent-annual report shall be submitted to the Commission within 60 days after January 1 and July 1 of each year specifytng the quantity of each of the radionuclides released to unrestricted areas in ltquid 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 Data (Annual Report)

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

a. Results of all environmental measurements sumarized 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. Sumnaries. 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 emmissions of radioactivity including the maximum noble gas gamma and beta air doses in the unrestricted area. The assessment of radtation doses shall be performed in accordance with the Offsite Dose Calculation Manual (00CM).

c. Results of the census to determine the locations of nearest residences and of nearby animals producing milk for human consumption.

(Table 4.8-4).

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 summary of meteorological conditions concurrent with the releases of gaseous effluents in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stabtitty.

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

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

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

6.6-3 0377B/0135Z

Quad-Cities DPR-30

3. If a confirmed measured radionuclide concentration in an environmental sampling medium averaged over any calendar quarter 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 submitted to the Administrator of the NRC l Regional Office, with a copy to the Director, Office of Nuclear Reactor Regulation, within 30 days from the end of the quarter.

4. When more than one of the radionuclides in Table 4.8-5 are detected in the medium, the reporting level shall have been exceeded if ci >1 R.L.i where C1 is the average quarterly concentration of the t th radionuclide in the medium and RL is the reporting level of radionuclide 1.

b. If radionuclides other than those in Table 4.8-5 are detected and are due to plant ef fluents, a reporting level is exceeded if the potential annual dose to an individual is equal to or greater than the design objective doses of 10 CFR 50 Appendix I.

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

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

6.6-4 03778/0135Z

9 Ouad-Cities OPR-30 TABLE 6.6-1 SPECIAL REPORTS Specification er.ga Reference submittal Date

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.B.2 After each specimen removal specimens and completion of analyses.

d. Radioactive Source Leak Testing (2) 4.8.F. Annual Report

e. Special Effluents Reports 3.8.A. 30 days following occurrence.

3.8.B.

3.8.D.

6.6.C.3 IlQlEl

1. Each integrated leak rate test of the secondary containment shall be the subject of a sumary 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.

2. This report is required only if the tests reveal the presence of 0.00S microcuries or more of removable contamination.

f s

6.6-S 0377B/0135Z

1 Quad-Citles OPR-30 6.7 ENVIRONMENTAL QUALIFICATION A. All safety-related electrical equipment in the facility shall be qualified in accordance with the provtstons of: Assistant of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (00R Guidelines); or. NUREG-0588 " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment". Decenter 1979. Copies of these documents are attached to Order for Modification of License DPR-30 dated October 24. 1980.

D. Complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the D0R Guidelines or NUREG-0588. Such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further* qtalified, s

k

\ ~

s 4

5 i

1 6.7-1 0377B/0135Z s

Quad-Cities DPR-30 6.8 Offsite Dose Calculation Manual ICDCM) !

A. The ODCM shall describe the methodology and parameters to be used in the calculation of offstte doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LC0's contained in these Technical Specifications. Methodologies and l calculational procedures acceptable to the Connission are contained in NUREG-0133. l The 00CM shall be submitted to the Commission at the time of proposed Radiological Effluent Technical Specifications and shall be subject to review and approval by the Consnission prior to implementation. I B. Licensee initiated changes to the ODCM may be made provided the change:

1. Shall be submitted to the Commission by inclusion in the Monthly Operating Report i pursuant to Specification 6.6.A.3. within 90 days of the date the change (s) was made effective and shall contain:

a. Sufficiently detailed infornation to support the change. Information submitted should consist of a package of those pages of the 00CM to be charged together with appropriate analyses or evaluations justifying the changes (2);

b. A determination that the change will not reduce the accuracy of reliability of dose calculations or setpoint determinations; and

c. Documentation of the f act that the change has been reviewed and found acceptable by the onsite review functions.

2. Shall become effective upon review and acceptance by the onsite review function.

6.8-1 03778/0135Z

Quad-Cities DPR-30 6.9 Process Control Program (PCP)

A. The PCP shall contain the sampling. analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is assured.

B. The PCP shall be approved by the Commission prior to implementation.

C. Ltcensee initiated changes may be made to the PCP provided the change:

1. Shall be submitted to the Commission in the Radioactive Effluent Release Report for the period in which the change was made and and shall contain:

a. Sufficiently detailed information to support the change:

b. A determination that the change did not reduce the overall conformance of the solidtfied waste product to existing criteria for solid wastes: a.,d

c. Documentation that the change has been reviewed and found acceptable by the onstta review function.

2. Shall become ef fective upon review and acceptance by the onsite review function.

6.9-1 03778/01352 .

f i

Qua6-Cit 1Qs I OPR-30 a.10 Major Changes to Radioactive Waste Treatment Systems (L*-'Jid. Gaseous. Solid) i A. Licensee initiated major changes to the radioactive waste systems may be made provided.

I

1. The change is reported in the Monthly operating Report for the period in which the <

evaluation was reviewed by the onsite review function. The dtscussion of each change shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 1,0 CFR 50.59;

b. Sufficient detailed information to support the reason for the change; l

c. A detailed description of the equipment, components, and process involved and the interfaces with other plant systems;

d. An evaluation of the change which shows the predicated releases of radioactive materials in liquid and gaseous effluents and (or quantity of solid waste that differ f rom those previously predicted in the license application and amendments);

e. A comparison of the predicted releases of radioactive seterials in liquid and gaseous effluents and in solid waste to the actual releases for the period in which the changes were made;

f. An estimate of the exposure to plant operating personnel as a result of the change; and

g. Documentation of the fact that the change was reviewed and found acceptable by the onsite review function.

2. The change shall become effective upon review and acceptance by onsite review function.

l l

1 l

l 6.10 :

1 03778/0135Z )

l i

ATTAC10 GENT 3

SUMMARY

OF CHANGES The enclosed submittal includes the changes identified below with respect to the previous August 23, 1984 submittal. Due to retyping, page numbers have shifted in some cases. Page numbers indicated below refer to the enclosed submittal.

Pane (1/86 Submittal) Changes v Last entry, page number 6.6-6 changed to 6.6-5.

vi Description of Figures 6.1-1, 6.1-2, 6.1-3 updated. This page is now the same as the currently approved Tech. Spec.

6.1-1 Title changes to reflect the revised corporate and station organization shown in new Figures 6.1-1 and 6.1-2 were made in Sections 6.1.A and C.

Reference to Figures 6.1-1, 6.1-2 and 6.1-3 updated in Sections B and C.

Section D - Lead Health Physicist added as alternate individual meeting the requirements of Reg. Guide 1.8 for rad protection manager.

Title change to Assistant Superintendent -

Technical Services. Deletion of " Station" in identifying the established Rad / Chem training program (second paragraph).

Section G.1 - Supervisor of Off-Site Review now appointed by the Chairman and President.

6.1-2 Section a - title changes Section a.10 - title changes Section b - title change.

6.1-3 Section b.12 - title changes Section C - Manager of Q.A. and Supervisor of Off-Site Review now report to Chairman and President. Authority to order unit shutdown transferred from Director of Nuclear Safety to Supervisor of Off-Site Review.

l l

r~

~

ATTACHMENT 3

SUMMARY

OF CHANGES The enclosed submittal includes the changes identified below with respect to the previous August 23, 1984 submittal. Due to retyping, page numbers have shifted in some cases. Page numbers indicated below refer to the enclosed submittal.

Page (1/86 Submittal) Changes v Last entry, page number 6.6-6 changed to 6.6-5.

vi Description of Figures 6.1-1, 6.1-2, 6.1-3 updated. This page is now the same as the currently approved Tech. Spec.

6.1-1 Title changes to reflect the revised corporate and station organization shown in new Figures 6.1-1 and 6.1-2 were made in Sections 6.1.A and C.

Reference to Figures 6.1-1, 6.1-2 and 6.1-3 updated in Sections B and C.

Section D - Lead Health Physicist added as alternate individual meeting the requirements of Reg. Guide 1.8 for rad protection manager.

Title change to Assistant Superintendent -

Technical Services. Deletion of " Station" in identifying the established Rad / Chem training program (second paragraph).

Section G 1 - Supervisor of Off-Site Review now appointed by the Chairman and President.

6.1-2 Section a - title changes Section a.10 - title changes Section b - title change.

6.1-3 Section b.12 - title changes Section C - Manager of Q.A. and Supervisor of Off-Site Review now report to Chairman and President. Authority to order unit shutdown transferred from Director of Nuclear Safety to Supervisor of Off-Site Review.

r

~

Page (1/86 Submittal) Changes 6.1-5 Title changes in Sections 2, 2a, 2a.1, 5, 8, 9, 11.

6.1-6 Title changes in Sections b, c.1, d.1 and e.l.

Figure 6.1-1 Revised Corporate Organization Chart.

Figure 6.1-2 Revised Station Organization Chart.

Figure 6.1-3 Revised Shift Manning chart to conform with 10 CFR 50.54.m(2)(i).

6.2-1 Section 6.2.C.1, 2 - title changes and clarification of procedural approval authority.

6.3-1 Section 6.2.D.3 - title change Section 6.3.A.2 - title change.

6.4-1 Title change.

6.6-4 Title change - Regional Administrator vs Director.

6.6-5 Deletion of EGC report from Table 6.6-1 (report has been submitted).

6.7-1 Updated and more detailed description of EQ requirements.

The above described changes apply to both Quad Cities Units 1 and 2.

The enclosed Technical Specifications include revision bars indicating all changes with respect to he currently approved Technical Specification (i.e., those described above plus those identified in the August, 1984 submittal).

1119K

. e ATTACHMENT 4 l

EVALUATION OF SICNIFICANT HAZARDS CONSIDERATION l

Description of Amendment Request The proposed amendments to the Quad Cities Units 1 and 2 Technical Specifications incorporate changes in the Commonwealth Edison corporate and station organization. Additional administrative changes are included as described in Attachment 3. These changes supplement a previous amendment

request on August 23, 1984.

I Basis for Proposed No Significant Hazards Consideration Determination Commonwealth Edison has evaluated the proposed Technical Specifi-cation amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration established in 10 CFR 50.92(c), operation of Quad Cities Units 1 and 2 in accordance with the proposed amendments will not:

1) involve a significant increase in the probability or consequences of an accident previously evaluated because:

the proposed changes involve administrative changes in the management organizational structural and do not affect any plant equipment or operational procedures which could impact the probability or consequences of an accident, l

, 2) create the possibility of a new or different kind of accident from any accident previously evaluated for the same reason as 1) above. No new equipment or operating practices are being introduced.

3) involve a significant reduction in the margin of safety since the amendment does not affect any operating practices or limits nor any equipment or system important to safety.

1 In addition the Commission has previously provided guidance in the form of specific examples of amendments which do not involve a significant hazards consideration. The administrative nature of these changes falls within those examples.

In consideration of the above, Commonwealth Edison requests approval j of these amendments under the provisions of 10 CFR 50.91(a)(4).

1119K 1

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

_ _ _ _ _ _ _ . .

ML20137M917

Text

SUMMARY

SUMMARY

Navigation menu

Search