Text

Proposed Tech Spec Changes Reflecting Revised 10CFR50.72 & New Section 50.73 LER Reporting Requirements
	ML20096A652
Person / Time
Site:	Quad Cities
Issue date:	08/23/1984
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20096A647	List: ML20096A646; ML20096A652;
References
	6312N, NUDOCS 8408310206
	Download: ML20096A652 (62)
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. TECHNICAL SPECIFICATIONS 4

APPENDIX A s LIST OF FIGURES s,- 4 .

- Number Title 2.1-1. ~APRM Flow Reference Scram and APRM Rod Block Settings 2.1-2 Deleted 2.1.3 APRM Flow Blas Scram Relationship to Normal Operating Conditions 4.1-1 Graphical Aid in the Selection of an Adequate Interval Between Tests 4.2-1 Test Interval vs. System Unavailability 3.4-1 Standby Liquid Control Solution Requirements 3.4-2i Sodium Pentaborate Solution Temperature Requirements 3.5-1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) vs. Planar Average Exposure 3.5-2 Kr Factor 3.6-1 Einimum Reactor Pressurization Temperature 3.12-1 Fire'0etection Instruments 3.12-2 Sprinkler Systems 3.12-3 CO2 Systems 3.12-4 Fire Hose Stations 4.6-1' Chloride Stress Corrosion Test Results at 5000F 4.8-1 Locations of FixedInvironmental Radiological Monitoring Stress 6.1-1 Corporate and Station Organization 6.1-2 Minimum Shift Manning Chart 4

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QUAD-CITIES i OPR-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 i film boiling. Transition boiling is the regime in which both nucleate and '

! film boiling occur intermittently, with neither type being completely stable.

l 88. Critical Power Ratio (CPR) - The critical power ratio is the ratio of that j assent)1y power which causes some point in the assembly to experience transition boiling to the assembly power at the reactor condition of interest i as calculated by application of the GEXL correlation (reference NEDO-10958).

CC. Minimum Critical Power Ratio (>CPR) - 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.

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

fraction of limiting power density (FLPD).

GG. Fraction of Rated Power (FIF) - The fraction of rated power is the ratio of 1 core thermal power to rated thermal power of 2511 MWth. l HH. Reportable Event - Any of those conditions specified in Section 50.73 to 10 ;

l CFR Part 50. l 1.0-4 Amendment No.

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' LIMITING CONDITIONS FOR OPERATIONS ' SURVEILL NCE REQlJIREbENTS Applicability: .

Applicability: *

- Applies to the fire protection systems whenever the Applies to the periodic testing requirements of the fire equiptr.ent or systems being protected are required to protection systems whenever the fire protection be operable. systems are required to bt operable.

. Objectiver , Objective: l s ,

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

maintained during all modes of facility operation. .

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, . SPECIFICATIONS A. Fire DetectionInstrumentation A Fire Detection Instrumentation .

1. As a minimum, th' 'e fire detection instru- 1. EacE of the~ fire detection instruments '

mentation for ea:h fire detection zone given by Table 3.12 l'shall be demon-shown in Table 3.12-1 shall,be operable strated operable. atc 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-s-pervised circuits ' 'shall be

. 2'. With the number of operable fire detec- '

demonstrated' operable once per month.

tion instruments lpss: than required by.

Table 3.121;

a. Perform an inspection of affected zone, within I hour.. Perform addi-tional inspections at. lease once per

' hour exceptin inaccessible aress- -

b. Restore the inopeuble instrument (s) to operable status within.14' days.or .

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prepare and- submit a_ report- to. the. -

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Commission pursuant.to Specification- ~

') 6.3.4.1.within the-next 30 days out- '

lining the cause of the malfunction, -

Ce action taken, and..the- plans for ,

restoring. the instruinent(s) to .oper-able status. "

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3. 'Ite provisions of specification-

. 3.0.A are roe applicable. ,_

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.L ' B. Fire f ,, . 'a Water System B. Fire Suppression Water System i

1.' Ihe Fire Suppression Water System shall ' l. 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.

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with a capacity- of 2000 gpm with gered test basis by starting each pump their discharge aligned to the fire and operatingit for atleast 20 minutes suppression header. on recirculation flow.

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

c. Art . operable flow path capable of Perated or automade) 6 de now path is in the correct postion.

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

able sectionalizing control orisolation

d. At least once per year by cycling each valves to the yard hydrant curb valves testable valve in the flow path through and the front valve ahead of the water at least one complete cycle of full flow alarm device on each sprinkler, hose stand pipe, or spray system riser. I'*"b

e. At least once per operating cycle

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.

l tion 6.3. A.1#ithin the next 30 days ott.

-* 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 restoring 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 conditiort within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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QUAD-CITIES DPR-29 simulated automatic actuation of the system throughout its opera-ting. sequence and verifying that

- each automatic valve in the now path actuates to its correct position.

(2) By verifying that each pump develops at least 2000 gpm at a

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system head of 123 psig.

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

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

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

s.,. . 2.

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-ment and inspect the area twice per shift. matic actuation of the system and l

Restore the system to operable status ver E &at me automatk des b

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the now path actuate to their cor--

within 14 days, or prepare and submit a reet positions.

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

l C- a e a sPected to or rest ring e s ebt to pe be status. i l

-! 3. At least once per 3 years by performing

4. 'Ihe provisions of Specificatica { an air flow test through each open head 3.0.A are ret: applicable. ;

spray / sprinkler header and verifying each open head spray / sprinkler nozzle is un-obstructed.

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DPR- 29

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, D.-CO2 Systems - D. CO 2 Systems

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1. The CO Storage 2

Tank shall have a mini-

- mum stand by level of 50 percent and a

1. At least once per 7 days the CO 2 38 f38' Tank level.and pressure will be verified.

minimura pressure of 250 psig. 7 ggg g

2. - The cop Systems given in Table 3.12 3 synem valves and associated dampers will shall be operable. ,

, be verified to actuate automatically and

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manually. A brief flow test shall be made

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

4. Wi.ht a CO System inoperable, establish 2

, backup fire suppression equipment for the unprotected ares (s) within I hour

,, and inspect the area twice per shift. ,

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

. Specification' 6.3.A.1 I within the next

( 30 days outlining the-cause of inoper. -

ability, the action taken, and the plans and schedule for restoring the system to ,

operable status.

,- ; 6. If actuated, the storage tank will be I restored to greater than the minimum level within 48 hou,rs.

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7. 'the provisions 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 E 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:

. Perable.

2. At least once per , operating cycle, the ,

2. With a hose station inoperable, route an hose will be removed for inspection and - '

additional equivalent capacity hose to the teracked. Degraded gaskets-in the coup.

unprotected ares frem an operable hose lingswillbe replaced.-

station within I hour'

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

' 3. 'the provisions of soecification tion valve will be partially opened .to

, p 3.0.A are not applicable, verify valve operability and no blockage.

[ 4. t'least once per 3 years a hydrostatic l test will be conducted on each hose at

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a pressure at least 50 psig greater than the

,, maximum pressure available at the hose station. -

.._ F' _ Penetration Fire Barriers F. Penetration Fire Batriers-T- 1. All penetration fire barriers protecting 1. Each of the penetration fire barrier shall _,

safety related areas i. hall be intact except be verified. to. be intact by visual in-as stated in Specification 3.12.F.2. spection; '

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i QUAD-CITIES DPR-29

- 6.0 ADMINISTRATIVE CONTROLS

-6.1 OfCANIZATION[ REVIEW, INVESTIGATION, AND AUDIT k (A. LThe Station Superintendent shall have overall full-time responsibility for safe

. operation of the facility. During. periods when the Station Superintendent 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.

f 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 is shown in Figure 6.1-1.

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-C. The shift manning for the station shall be as shown in Figure 6.1-2. The Operating Assistant Superintendent, Operating Engineer, Shift Engineers, and

' Shift Foremen shall have a senior operating license. The Fuel Handling Foreman.

'has a limited Senior Operating License. The Division Vice President and General Manager Nucle'ar Stations on the corporate level has responsibility for the Fire Protection' Program. The Maintenance Assistant Superintendent will be responsible

.for implementaton of the Fire Protection Program. A fire brigade of at least 5 i members shall be maintained on-site at all times. This excludes'the shift crew-necessary for safe shutdown of the plant, and any personnel required for other 4 essential functions during a fire emergency.

i 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 j

.. Power Plant Personnel", dated March 8, 1971. The Rad-Chem Supervisor shall meet the requirements of radiation protection manager of Regulatory Guide 1.8. The '

individual filling the position of Administrative and Support Services Assistant Superintendent 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 bachelors' 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 Station's ,

established Radiation / Chemical Technician training program, and shall have at l least a total of one year of. general power plant, chemical or radiation protection experience, or equivalent-training. TheRadiatIon/ChemicalTechnicians

.shall meet the criteria for " Individuals Qualified in Radiation Protection

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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: -

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QUAD-CITIES OPR-29

-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 academic training.

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

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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 Director of Nuclear Safety. The Audit Function shall be the l responsibility of the Manager of Quality Assurance and shall be independent of operations,

a. Offsite Review and Investigative Function The Supervisor of the Offsite Review and Investigative Function shall: (1) provide directions for the review and investigative 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 possess background and qualifications in the subject matter under review to provide comprehensive interdisciplinary review coverage under this function, (4) independently review and approve the .

findings and recommendations developed by personnel performing the review and investigative function, (5) approve and report in a timely manner all findings of noncompliance with NRC requirements to the Station

'Page 6.1-2 Amendment No.

, QUAD-CITIES DPR-29

' Superintendent, Division' Vice President Nuclear Stations, Manager of Quality Assurance, and.the Executive Vice President of. Construction, Production, and Engineering. During periods when the Supervisor of'Offsite Review and

. Investigative Function is unavailable, he shall 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 'Offsite Review and Investigative Function shall review:

1) The safety evaluations for (1) changes-to procedures, ' equipment, or systems

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.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 syst' ems 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 Specifications or NFC operating licenses.

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

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

7) Reportable events.

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

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

10)' Review and report findings and recommendations regarding all items referred

' by the Technical Staff Supervisor, Station Superintendent, Division Vice

. President Nuclear Stations, and Managei of Quality Assurance. '

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m QUAD-CITIES OPR-29 l

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 Staff Assistant to the Manager of Quality Assurance- 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 or less as designated below.

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

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 least once per year.

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

7) Audit onsite and offsite reviews.

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

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

10) The ODCM 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.

Page 6.1-4 Amendment No.

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-12)( : Report all-findings'of noncompliance with NRC requirements and recommenda-itions and results each auditLto the~ Station: Superintendent, Division Vicei

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President' Nuclear Stations,' Manager of-Quality: Assurance,K Vice President of Nuclear. Operations,' and to the Executive Vice PresidentLof Construction, Production, Land Engineering.-

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Authority LThe Manager of- Quality Assurance reports to the.Vice Chairman and the' Supervisor l of the Offsite Review and. Investigative Function reports to the Director of

. Nuclear Safety who reports to the Chairman' and President.' Either the Manager of 7 . Quality Assurance or the Director of Nuclear. Safety'has the authority to order

' unit. shutdown.or request any other action which he-deems necessary'to avoid

unsafe plant conditions.

1d.

Records

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

Copies of documentation, reports, and correspondence shall be kept on file

2) . at the station.-

e. Procedures Written administrative procedures shall be prepared and maintained for the

. offsite reviews and investigative functions described in Specifications 6.1.G.la. Those procedures shall cover the following:

1)- Content and method of: submission of presentations to the Supervisor of the Offsite Review and Investigative Function.

2) -Use of committees and consultants.

3) _ Review and approval.

-'4) : 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.

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

.findir gs and~ recommendations reported by personnel performing the review and-investigative function.

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f. Personnel

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

a) . nuclear power plant technology, b) reactor operations, c) utility operations, '

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

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

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

a) fisclear Power Plant Technology Engineering graduate or equivalent with 5 years experience in the nuclear power field design and/or operation, b) Reactor Operations Engineering graduate or equivalent with 5 years experience in nuclear power plant operations.

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

d) Power Plant Design j

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 experf ence in nuclear plant engineering, operation, and/or-graduate work in nuclear engineering or equivalent in reactor physics is required.

Page 6.1-6 f-Amendment No. F,'

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QUAD-CITIES 7- DPR-29 f) . Radiological Safety

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

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

4 h) Instrumentation and Control ~

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_ Engineering graduate or equivalent with at least 5 years of. .

experience in instrumentation and control design and/or operation. . 't

1) ;etallurgy-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 4

have experience and training which satisfy ANSI N18.1-1971 requirements 2-for plant managers.~

-2. The Onsite Review and Investigative Function shall be supervised by the ' '

Station Superintendent.

j a) Onsite Review and Investigative Function f

, . The Station Superintendent shall: (1) provide direction for the Review -

and Investigative Function and appoint the Technical Staff Supervisor, or other comparably qualified individual as a sanior participant to

provide appropriate directions, (2) approve participants for this-

- function; (3) assure that a complement of more than one participant who collectively, possess background and qualifications in the subject matter under review are selected to provide comprehensive interdisciplinary review' coverage under.this function; (4) independently review and approve the findings and recommendations developed by personnel performing the Review and Investigative Function;.(5) report all findings of noncompliance with NRC requirements, and provide

" z recommendations to Division Vice President Nuclear Stations and -!

the Supervisor of the Offsite Review and Investigative Function; and (6) submit to the Offsite Review and-Investigative Function for concurrence in a timely manner, those items described in Specification 6.1.G.1.a which have been approved by the Onsite Review and Investigative Function.

Page 6.1-7 Amendment No.

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QUAD-CITIES OPR-29 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 de*, ermined by the Plant' Superintendent to affect nuclear safety.

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

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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 recommendations to prevent recurrence to Division Vice President

' Nuclear Stations and to the Supervisor of the Offsite Review and Investigative Function.

6) Review of facility operations to detect potential .eafety 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 F2an and shall submit recommended changes to Division Vice President Nuclear Stations.

9) Review of the Emergency Plan and-station implementing procedures and shall submit recommended changes to Division Vice President Nuclear Stations.

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

-11) Review of any unplanned on-site release of radioactive material to the environs, including the preparation and forwarding of reports covering evaluation recommendations and disposition of the corrective action to prevent recurrence to the Division Vice President-Nuclear Stations, and to the Supervisor of the Offsite Review and Investigative Function.

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

Page 6.1-8 Amendment No.

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DPR-29~

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(b.: LAuthority '

'.The Tecnnical- Staff Supervisor- is responsible to .the ~ Station -

. Superintendent and shall make-recommendations in a timely manner:in' ail areas of review, investigation,-_ and quality control: phases of plant: .

maintenance,; operation,"and. administrative procedures relating to-

. facility: operations _ and .shall have the authority' to request _the action necessary to ensure compliance with rules, legulations and procedures Jwhen in his; opinion such action.is necessary. The Station SuperintendentE shall follow:such recommendations or select a course of action that is

' more' conservative regarding safe operation of the facility. . All such

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t disagreements shall be reported immediately to Division Vice President.

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Nuclear Stations and the Supervisor of the Offsite Review and Investigative Function.-

c. Records-s 1)- Reports,L review's, investigations, and recommendations shall be L

documented with copies to Division Vice President Nuclear Stations, the Supervisor of. the Offsite Review and Investigative Function, the Station Superintendent,._and the Manager of Quality Assurance.

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

d .- Procedures Written administrative 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 Superintendent, Division Vice President Nuclear-Stations, and the Supervisor of the-Offsite Review and Investigative Function..

2) Use of committees when necessary.

l

3) Review and approval.

4). Detailed listing of items to be reviewed.

5) : Procedures .for administration of the quality control activities.

6) Assignment of responsibilities.

Page 6.1-9 Amendment No.

-.- . - ~ .-

b ~

QUAD-CITIES.

OPR-29

-e.. Persomel l) The persomel perf0rmingithe Onsite' Review and Investigative.

. Function,Lin addition _to the Station Superintendent, shall consist of persons having expertise in:

a) nuclear power plant technology, b) reactor operations',

c) reactor engineering, d)_ _ radiological s'afety and chemistry,.

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

2) Persomel performing the Onsit'e 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 offsite licensee' persomel 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.

I-J t &

Page 6.1-10

- Amendment No.

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- - l DPR.29 .

Miff!Mt.H SRIFT MAJOIINO CHART $

CDCITION OF Ovt pulf -

. (No Fuel in SecoN: Unit) -

License Initial fuel Lossing Cold h tgown or . Above Cold Cetree-v or Dorian Refueltso tefuelin: Snu tco-a- Shutdown

~ ~

Senior ..

Operate,r -

License 2 1 1 CIptrator. -

I License 2 1 2 1

Red. Prot. fien l 1 1 d

gon.Litenseg (As Required)

1 I Shift Technical. -

Advisor' None Iteaufred m:me Recufred -

1

, CONDITION OF 51COND UNIT (One Unit at, Not htdown er at Power)

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License laitial Fuel Leading Co16 htdown or Above Cold Category or During Refueling Refueling Shotsown h tdo-a l

Senior * -

Sperator .

License 2 2 2 Operator' License 3 -

3- 3 1 1 1 I 148. Prot. Man 1 3* (As Renvired) 3 4

! Wen. Licensed Shift Technical .

! Advisor 1 1 1 C0clT10N OF SECOND UNIT (One Unit.A.t Cold h tdown or Refueling Shutdown)

. License Initial Fuel Leading Cold htdown er Above Cold i Category or During Refueling Refueline Shutdown shutdown ,

Senior

Operator License - 2 1 2 Operator * -

License . 3 'I . !

Red. Prot. Man 1* - 1 1

' Non-Licensed 3. (As neovired) 3 3

~

Shift Technical .

Advisor . None Requirst Mcme Itequired 1

' Assumes each individual is licensed on each facility. During initial fuel loading or during refueling, or.e sennr engineer (limited license) will supervise feel handling, f Shift arew co. position may be less than the minimum requirements for a period of time s'ot to anteed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to acco=nodate unexpected absence of en duty shift crew members provided in:nediate action is taker. to restore the shift crew composition to within the mitin.=a re-guirveents. .

Amendment' No. 74 .

FIGuat 6,1 -2 l

. ~ _ . - _, _

r.

QUAD-CITIES OPR-29 6.2 PLANT (PERATING PROCEDURES A. Detailed written procedures including applicable checkoff lists covering items

~~1isted 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. Emergency conditions involving potential or actual release of radioactivity - " Generating Stations Emergency Plan" and station emergency and abnormal procedures.

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

6. Preventive and corrective maintenance operations which could have an effect 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.

11. Fire Protection Program implementation.

12. ODCM implementation.

13. PCP implementation.

14. Working hours of the Shift Engineer, Station Control Room Engineer, Shift 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. These 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.

Page 6.2-1 Amendment No.

s QUAD-CITIES DPR-29 C. 1. Procedures for items identified in Specification 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 the Maintenance Assistant Superintendent and Technical- Staff Supervisor in the areas of plant maintenance and plant ,

inspection. Procedures for items identified in Specification 6.2.B and any changes to such procedures shall be reviewed and approved by the Technical Staff Supervisor and the Rad Chem Supervisor. At least one

, person approving each of the above procedures shall hold a valid senior operator license.- In addition, these procedures and changes thereto, must have authorization by the Station Superintendent before being implemented.

2. Work and instruction type procedures which implement approved maintenance'or modification procedures shall be approved and authorized by the Maintenance Assistant Superintendent where the written authority has been provided by the Station Superintendent. The " Maintenance /

Modification Procedures" 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 requirements of 6.2.A or 6.2.B may be approved by the Department Heads.

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

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

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

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

E. Drills of the emergency procedures described in Specification 6.2.A.4 shall be conducted at the frequency specified in the GSEP manual.

Page 6.2-2 Amendment No.

'l l

' QUAD-CITIES DPR-29 6.3 REPORTAB_E EVENT ACTION A. The following actions shall be _ taken for Reportable Events:

~1) The Commission shall be notified and a report submitted pursuant to the requirements of-Section 50.73 to 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 Division Vice President Nuclear Stations..

Page 6.3-1 Amendment No.

j QUAD-CITIES l OPR-29 4

i 6.4 ACTION TO BE TAKEN IN ilE EVENT A SAFETY LIMIT IS EXCEEDED J If a safety. limit is exceeded, the reactor shall be shut down immediately and reactor operation-shall not be resumed until authorized by the NRC. The conditions of shutdown shall be promptly reported to Division Vice President Nuclear Stations l or his designated alternate. The incident shall be reviewed pursuant to Specifications 6.1.G.l.a and 6.1.G.2.a and a separate report for each occurrence shall be prepared in accordance with _ Specification 6.3.A.l. I l

l l

Page 6.4-1 Amendment No.

- (0607d)- QUAD-CITIES DPR-29 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 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 reviews of tests and experiments to comply with 10 CFR 50.59.

6. records of radioactive shipments;

7. records of physic tests and other tests pertaining to nuclear safety;

8. records of changes to operating procedures;

9. shift engineers' logs; and

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

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

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

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

3. records of new and spent fuel inventory and assembly histories; l

4. updated, corrected, and as-built drawings of the plant; Page 6.5-1 Amendment No.

l

QUAD-CITIES '

OPR-29 6.5 PLANT OPERATING RECORDS (cont'd)

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 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 members 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-offsite and onsite review and audit functions.

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

Page 6.5-2 Amendment No.

I t

QUAD-CITIES OPR-29 6.6 REPORTING REQUIREENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations,- the following identified reports shall be submitted to the director of the appropriate Regional Office of Inspection and Enforcement 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 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 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 commitments shall be' included in this report.

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

2. A tabulation shall be submitted on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions (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 badoe 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 l major work functions; and Page 6.6-1 l Amendment No.

l 1 1

QUAD-CITIES DPR-29

3. Monthly Operating Report-Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, US 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 ODCM shall be submitted with the Monthly Operating Report within 90 days of the effective date of the change.

A report of major changes 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.

B. Unique Reporting Requirements

1. Radioactive Effluent Release Report (Semi-Annual)

A semi-annual report shall be submitted to the Commission within 60 days after January 1 and July 1 of each year specifying the quantity of each of the principal radionuclides released to unrestricted areas in liquid 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 An annual report containing the data taken in the standard radiological monitoring program (Table 4.8-4) shall be submitted prior to May 1 of each year. The content of the report shall include:

a. Results of all environmental measurements summarized 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. Summaries, interpretations, and analysis of trends of the results are to be provided.

b. An assessment of the monitoring results and radiation dose via the principal pathways of exposure resulting from the plant emissions of radioactivity including the maximum noble gas gamma and beta air doses in the unrestricted area. The assessment of radiation doses shall be performed in accordance with the Off-Site Dose Calculation Manual (00CM).

Page 6.6-2 Amendment No.

-J.

~

QUAD-CITIES

~

OPR-29'

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

.' pasture season feeding practices at; dairies-in the monitoring program

-(Table 4.8-4)..

.d. The reason for the emission if the nearest dairy to the station isE not in the monitoring program (Table 4'.8-4).

e. 'An annual l summary of meteorological conditions concurrent with the

-releases of- gaseous effluents in the form of joint frequency distributions and wind speed, wind direction, and atmospheric stability.

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. i

h. A summary of the monitoring program,' including maps showing sampling.

locations .and -tables giving distance and direction of sampling i locations from the Station.

3. -If a confirmed measured radionuclide concentration in an environmental sampling medium sveraged 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 Director of the NRC Regional Office, with a copy to the Director, Office of Nuclear Reactor Regulation, within 30 days from the end of the quarter.

(a) When more than one of the radiouclides in Table 4.8-5 are detected in the medium the reporting level shall have been exceeded if

, Ci y_1 R.L.i

'where C is the concentration of the ith 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 effluents, a' reporting level is exceeded if the )

potential annual dose to an individual is equal to or greater than j the design objective doses of 10 CFR 50, Appendix I. j i

1 Page 6.6-3 )

Amendment No. l l

)

J J

~

~ QUAD-CITIES DPR-29 (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 .

1 l

A Page 6.6-4 Amendment No.

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_QUAD-CITIES

'i

.g DPR-29 7

TABLE 6.6-1

~

1

.- i SPECIAL REPORTS-in.

Specification Area Reference Submittal Date

c. Secondary containment' leak rate test (2) 4.7.C. Upon completion of each test.

b. Summary status ofsfuel performance ~$.1-Baseu After each refueling outage. starting with

second refueling outage.

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

d. Evaluation of EGC operation 3.3.F Bases Upon completion of initial' testing.

c. Ra'dioactive Source Leak Testing (2) 4.8.F Annual Report

f. Special Effluents Reports 3.8.A. , 30 days following occurence 3.8.B.

3.8.D.

6.6.C.3.

Notes:

1. Each integrated leak rate test of the secondary containment shall be the subject of a summary technical report. This report should include data on the wind speed, wind direction, outside temperature 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 Jis required only if the tests reveal- the presence of 0.005 microcuries 1br more of removable contamination.

i

, Page 6.6-5 '

Amendment No.

t w

QUAD-CITIES OPR-29 6.7 ENVIRONENTAL QUALIFICATION '

A. By no later than December 1, 1980, complete and auditible records must be.

available and maintained at a central location which describe the environmen-

. tal 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. Thereafter, such records should be updated and maintained current as equipment is replaced,' further tested, or otherwise further qualified.

.f 1

6.7-1 Amendment No.

.p ith , , c h; 4, ,

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l:, .g . ATTACHMENT C y

w Quad Cities-Station' Units 1 and 2

M , ~ . ..

g. ' Proposed Changes 'to DPR-30 1 -

-b-2/

s 3 Mechnical', Specification :

g- (

he 3, , j-nit 3 u m- . Revised Pages: .v -(List of 'Tatiles cont'd)

. v.i (List of Figures)

,f; '~- .l.04- .

' }l' ~

i3il2/4 12 1 .

3.12/4.12-2 3.12/4;12-3 3.12/4.12-4 6.1-1

~6.1-2 6.1-3 6.1-4.

w:e > 6.1-5 6.1-6 u'

6.1-7 (new page)

, 6.1-8--(new page) 6.1-9 (new page);

6.1-10 (new page)

Figure 6.1-1 Figure 6.1-2 6.2-1 6.2-2 (new page)-

,* 6.3-1 9 py 6.4-1

. j' .s 6.5-1 p "L' '

.6.5-2 6.6-1 6.6-2*

i:jdl. 6.6-3*

W ' v- 3 g,g_gs 6.6-5*

a.. . , i 6.7-1

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c 1 c;s . ~ Deleted-Page: Figure 6.1-3 NOTE:';jThis submittal includes the Section 6 changes approved in

~

in Amendment No.'84.

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o-Paginat' ion only:

P,'. '

8654N N 4'My~ W-m ,. _o t,.

, m i i [ 1-. > *4- , , , + - ,- -- ,, , _

4.8-2 Maximum Permissable Concentration of Dissolved or ,

Entrained Noble Gases Released from the Site to !

Unrestricted Areas in Liquid Waste 3.8/4.8-21a 4.8-3 Radioactive Liquid Waste Sampling and Analysis Program 3.8/4.8-22 4.8-4' Radiological Environmental Monitoring Program 3.8/4.8-24 4.8-5 Reporting Levels for Radioactivity Concentrations in Environmental Samples 3.8/4.8-27 4.8-6 Practical Lower Limits of Detection (LLD) for

- Standard Environmental Monitoring Program 3.8/4.8-28 4.11-1 Surveillance Requirements for High Energy Piping Outside Containment 3.11/4.11-3 3.12-1 Fire Detection Instruments 3.12/4.12-7 3.12-2 Sprinkler Sytems 3.12/4.12-8 3.12-3 C07 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 l

Amendment No. 84 y I a

QUAD CITIES DPR-30 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 Se.lection of an Adequate Interval Between Tests 4 .2-l' 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 Kr Factor 3.6-1 Minimum Reactor Pressurization Temperature 3.12-1 Fire Detection Instruments 3.12-2 Sprinkler Systems 3.12-3 CO2 Systems 3.12-4 Fire Hose Stations 4.6-1 Chloride Stress Corrosion Test Results at 5000F

'4.8-1 Locations of Fixed Environmental Radiological Monitoring Stress 6.1-1 Corporate and Station Organization 6.1-2 Minimum Shift Manning Chart vi 6312N e

4' l i

,, , - m w I QUAD-CITIES OPR-30 ~

s

-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.

~

'l. . - 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 leas than 2120F.

Z. Simulated Automatic Actuation ~ - Simulated automatic actuation means 'appiping a simulated signal to the sensor to actuate.the circuittin 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 trentition boiling to ~the assembly power at the reactor condition of interest as calculated by application of the GEXL correlation (reference EDO-10958).

CC. Minimum Critical Power Ratio (>CPR) - The minimum incore critical power ratio ,

corresponding to the most limiting fuel assembly in the core.

DO 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 (WLPD) - The maximum fraction of limiting power density is the hicpest 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.

.-1 .;,,,,- ...- . QUAD-CITIES - - ~ # . . . . 4 v. . e -

m..

DPR-30

~~

.3.12/4.12 . FIRE PROTECTION SYSTEMS. , e

._ : ~ .u m

I: _

LIMITING CONDITIONS FOR OPERATIONS SURVEILLANCE" RE,QUIRD1ENTS r .. .

' Applicability: : Applicability: ,

Applies to.the fire protection sy:tems whenever the . Applies to the periodic testing requirements of the fire equipment or systems being protected are sequired to protection systems whenever the fire protection L be operable. systems are required to be operab!c.

Objective: Objectiver ,

s .

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

. maintained during all modes of facility operation. .

~

0 SPECIFICATIONS .

A. Fire Detection Instrumentation A Fire Detection Instrumentation

1. As a minimum, th'e fire detection instru. 1. Eacit of the' fire detectiort instruments mentation for each fire detection zone ~ given by Table 3.t21 shall be demon.

shown in Table 3.121 shall,be 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. A!I non-supervised circuits' shall .be

2. With the number of operab!c fire detec- demonstrated' operable once per month.

tion instruments less than required. by Table 3.1211

- a. Perform an inspection of - affected-

zone, withh I hour. Perform addi-

. tional. inspections at least. once per

i ' hour except.in inaccessible areas. ,

b. Restore.the inoperable instrument (s)

,to operable- status within 14 days, or

~

prepareland submit a report to the -

'. Commission pursuant to Specification l ; 6.3.A.1 lwithin the next 30 days out-

y lining the cause of the malfunction,.

the action taken, and the plans for , ,

~~

restoring the instrument (s) to oper-able status.

4 3. ne-pcovisions of specification -

3.0.A are not. applicable.

W ..

t b g

b -

g s.

1

, 3.12/4.12- 1. ,,

i

. .. ;- v.-f:

L-b .- _ _ . , _ , . _ _ _ . , . . - _ . . _ . . _ . . _ _ _ - - _ ,.

W QUAD 4TTIES DPR-30

- B. Fire Suppression 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 tunes 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 startmg each pump their discharge aligned to the fire and operatingitforatleast 20 minutes

- suppression header. on recirculation flow.

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

c. An operable ~ flow path capable of peratep or automade) h de now-path is m the correct postion.

taking suction from the M2ssissippi River and transferring the water c. At least once per year by performance through distribution piping with oper- of a system flush.

able sectionahzmg control or isolation

d. At least once per year by cycling each valves to the yard hydrant curb valves gg gg g and the t'ront valve ahead of the water mplete cyde of M at east ne flow alarm device on each sprinkler, I'**

hose stand pipe, or spray system riser.

e. At least nce per operating cycle

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 in:ludes days, or prepare and submit a report to the Commission pursuant to Specifica.

l tion 6.3.A.1 within the cut 30 days out.

lining the plans and procedures to be used to piovide 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. Establish a backup Fire Suppression Water System.

b. Notify- the Commission pursuant to l Specification 6.3. A .1 outlinmg the actions taken, the cause of the in-operability, and the plans and i schedule for restormg the system to operable status.

4 If the requirements of Specification l 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 condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

~

3.12/4.12 2 Amendment 44 effective 4/22t/S

QUAD 41 TIES -

' DPR-30

~., ,

simulated automatic actuation of- i the system throughout its opera.

ting sequence and verifying that each automatic valve in the flow j path actuates -to its correct a_ -

position.

(2) By verifying that each pump dev,elops at least 2000 gpm at a system head of 123 psig.

-(3.' Cycling each valve in the flow path that is not testable during plant operation through at least, one complete cycle of full travel, -

and .

.I

f. At least once per 3 years by perform-ing flow tests of the system in accor.

dance -with Chapter 5, Section 11, NFPA Fire Protection Handbook.

C. - Sprinkler Systems C. Sprinkler Systems

1. He sprinkler systems given in Table 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 / sprinkler least once complete cycle of full travel.

protected is required to be operable. 1 At lust a p gerate mie-

2. ,With _ the cable tunnel sprinkler system a. A system functional test shall be per.

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

watch with back up fire suppression. i matic actuation of the system and equipment for the unprotected area i verifying that the automatic valves in

! within I hour. the flow path actuate to their cor.

3. With any other prinkler. system in. l rect positions.

operable, establish back up fire sup. b. Ec sprinkler headers shall be in.

pression within I hour and inspect the spected to verify their integrity.

. area twice per shift. .

c. Each nozzle shall be inspected to

4. Restore the system to operable status ver bl @ e.

within 14 days, or prepare and -submit a report to the Commission pursuant 3. At least once per 3 years by performing to Specification 6.3. A .1 within the an air flow test through each open head l

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

the plans for restoring the system to ' obstructed.

j operable status.

' 5. W e provisions ~of specificatieni

[

,1 3.0.A are not applicable. 'l ;

.I .

l 3.12/4.12-3 g

~

C '

W, . . n;. . . x a. . ;m.c,u .

a e- . -

l, QUAD-CITIES. : ..e . . m w. .

-LDPR-30. !

2 D. .CO2Systems D..CO 2 Systems

.; 7

y[ il.4The CO Storage 2 Tank shall have a mini-mum stand by level of 50 percent and a

' 1. At'least bnce per 7 days the COj Storage Tank level.and pressure will be verified.

~

' minimum pressure of 250 psig. 2. At least 4nce per operating cycle, the

2. The CO Systems given in Table 3.12-3 . system valves and associated dampers will 2

- shall be operable.. , be verifie'd to actuate automatically and

~

manually. A brief flow test shallbe made

-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.:

~

i4.' With a CO System 2 inoperable, establish backup fire suppression equipment. for the unprotected ares (s) within I hour ~

and inspect the area twice per shift. ,:

5. Restore the system.to operable status within 14 days, or prepar'e and submit 2 report to the Commission pursuant to

. Specification' .6.3.A.1 Lwithin the next-

- 30 days outlining'the cause of inoper- .

^

ability, the. action taken, and the plans

. and schedule for restoring the system to ~ .

operable status.

6. If actuated.. the norage tank will: be-restored to greater 'than the minimum .

level within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

~

- 1 'Ihe pcovisions of Specification

.q 3.0,A are not applicable.

5. Fire Hose Stations E. Fire Hose Stations

1. The Fir 6 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 availabl:

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, route an ho'se will be removed for inspection and additional equivalent capacity hose to the teracked. Degraded gaskets in the coup-unprotected crea from an operable hose - lings will be replaced.

station within I hour.

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

3. 'Ihe provisions of specification t:en 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 :

i- <

i test will be . conducted on each hose at I

a pressure at least 50 psig greater than the maximum }ressure available 'at the hcs

.- station. .

i t -

F . Penett:, tion Fire Barriers F. Penetration Fire Batriers - ,

_t . .

' - 19 1. All penetration fire barriers protecting <

l. Each of the penetration fire barrier shall safety related areas sh.tll be intact except be verified to -be intact by visual in-i' ,

. as stated in Specification 3.12.F.2. spectio'n; .

~ ~ ~ ~ " ~

3.12/4.12-.4

l I

~ QUAD-CITIES DPR-30 6.0 ADMINISTRATIVE CONTROLS 6.1 OfCANIZATION, REVIEW, INVESTIGATION, AND AUDIT A. . The Station Superintendent shall have overall full-time responsibility for safe operation of the facility. During periods when the Station Superintendent 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.

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 is shown in Figure 6.1-1.

C. The shift manning for the station shall be as shown in Figure 6.1-2. The Operating Assistant Superintendent, Operating Engineer, Shift Engineers, and Shift Foremen shall have a senior operating license. The Fuel Handling Foreman has a limited Senior Operating License. The Division Vice President and General Manager Nuclear Stations on the corporate level has responsibility for the Fire Protection Program. The Maintenance Assistant Superintendent will be responsible for implementaton of the Fire Protection Program. A fire brigade of at least 5 members shall be maintained on-site at all times. This excludes the shift crew necessary for safe shutdown of the plant, and any personnel required for other essential functions during a fire emergency.

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 @, 1971. The Rad-Chem Supervisor shall meet the requirements of radiation protet. tion manager of Regulatory Guide 1.8. The individual filling the position of Administrative and Support Services Assistant Superintendent 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 bachelors' 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 Station's 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. Ziemann (NRC) letter to R. L. Bolger (CECO.) dated March 15, 1977. The Radiation / Chemical Technician training program consists of the following:

Page 6.1-1 Amendment No.

y . 1 4

i QUAD-CITIES OPR-30 1.: . Satisf'actory completion of a 12-week academic program. Topics of this course include mathematics, nuclear physics, radioactive _ decay, chemistry, sampling techniques, reactor coolant parameters, radi9 tion exposure, shielding, biological' effects of radiation' exposure, radiation survey techniques, personnel monitoring, and emergency-procedures.

2. Satisfactory performance on .1 comprehensive examination following completion of academic training.

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 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

-affccting quality during facility operations shall be constituted and have the

, responsibilities and authorities outlined below:

j 1. The Supervisor of the Offsite Review and Investigative Function shall be appointed by the Director of Nuclear Safety. TheAuditFunctionshallbethel responsibility of the Manager of Quality Assurance and shall be independent of operations.

a. Offsite Review and Investigative Function The Supervisnr of the Offsite Review-and Investigative Function shall: (1) provide directions for the review and investigative fl unction and appoint a senior participant to provide appropriate direction, (2) select e:1ch participant for this function, (3) select a complement of more than one participant who collectively possess background and qualifications in the-subject matter under review to provide comprehensive-interdisciplinary review coverage under this function, (4) independently review and approve the findings and recommendations developed by personnel performing the review and

~

investigative function, (5) approvo and report in a timely manner all findings of noncompliance with NRC requirements to the Station Page 6.1-2 Amendment No.

QUAD-CITIES OPR-30 Superintendent, Division Vice President Nuclear Stations, Manager of Quality l Assurance, and the Executive Vice President of Construction, Production, and

-Engineering. During periods when the Supervisor of Offsite Review and Investigative Function is unavailable, he shall 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 ~0ffsite 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 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 Specifications or NRC operating licenses.

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

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

4

7) Reportable events. !

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

9) Review and report findings and recommendations regarding all changes to the ,

Generating Stations Emergency Plan prior to implementation of such change, j

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

Page 6.1-3 l Amendment No. j

t 1

)

I t

QUAD-CITIES OPR-30 L 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 Staff Assistant to the Manager of Quality Assurance 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 or less as designated below.

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

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 least once per year. l

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

l

7) Audit onsite and offsite reviews.

8) Audit the Facility Fire Protection Program and implementing procedures at least once per 24 months,

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

10) The 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.

Page 6.1-4 Amendment No.

i:

u s

b ,

-QUAD-CITIES

, OPR-30 Y 12) Report all findings of noncompliance with NRC requirements and .

i;>-

recommendations.and results each audit'to the Station Superintendent, C : Division Vice President Nuclear Stations, Manager of Quality Assurance, Vice President of Nuclear Operations, and to the Executive Vice

!~ President.:of Construction, Production, and Engineering.

t

c. Authority.

L . The Manager of Quality Assurance reports to the Vice Chairman and the l Supervisor of. the Offsite Review' and Investigative Function ~ reports to the

-Director of Nuclear Safety who reports to the Chairman and President. Either

t. the Manager of Quality Assurance or the Director of Nuclear Safety 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,caudits,~and recommendations shall be documented and distributed as covered in'6.1.G.l.a and 6.1.G.l.b.

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

e. Procedures 1

Written administrative procedures shall be prepared and maintained for the j offsite reviews and investigative functions described in Specifications I 6.1.G.la. Those procedures shall cover the following:

1) . Content and method of submission of presentations to the Supervisor of

. the Offsite Review and Investigative Function.

2) Use of committees and consultants.

3) Review and approval.

4) 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. l

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

Page 6.1-5 Amendment No.

1 I

1

' QUAD-CITIES OPR-30

f. Personnel

1) The persons, including consultants, performing the review and investigative function, in addition to the Supervisor of the Offsite

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

a) nuclear power plant technology, b) reactor operations, c) utility operations, d) power plant design, e) reactor engineering, f) radiological safet g) reactorsafetyanahsis, 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 operation.

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

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

d) Power Plant Design Engineering graduate or equivalent with at least 5 years of experience in power 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 physics is required.

Page 6.1-6 Amendment No.

QUAD-CITIES DPR-30 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 1 ast 5 years of s 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 training which satisfy ANSI N18.1-1971 requirements for plant managers.

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

a) Onsite Review and Investigative Function The Station Superintendent shall: (1) provide direction for the Review and Investigative Function and appoint the Technical Staff Supervisor, or other comparably qualified individual as a senior participant to provide appropriate directions, (2) approve participants for this

, function; (3) assure that a complement of more than one participant who collectively possess background and qualifications in the subject matter under review are selected to provide comprehensive interdisciplinary review coverage under this function; (4) independently review and approve the findings and recommendations developed by personnel performing the Review and Investigative Function; (5) report all findings of noncompliance with NRC requirements, and provide recommendations to Division Vice President Nuclear Stations and l the Supervisor of the Offsite Review and Investigative Function; and (6) submit to the Offsite Review and Investigative Function for concurrence in a timely manner, those items' described ~ in Specification 6.1.G.l.a which have been approved by:the Onsite Review and Investigative Function.

Page 6.1-7 Amendment No.

t - - -' --i --

QUAD-CITIES OPR-30 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 Plant Superintendent to affect nuclear safety.

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

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

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

5) Investigation of all noncompliance with NRC requirements and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to Division Vice President Nuclear Stations and to the Supeivisor of the Offsite Review and Investicative 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 recommended changes to Division Vice President Nuclear Stations.

9) Review of the Emergency Plan and station implementing procedures and shall submit recommended changes to Division Vice President Nuclear Stations.

10) Review of reportable events and actions taken to prevent recurrence,

11) Review of any unplanned on-site release of radioactive material to the environs, including the preparation and forwarding of reports covering evaluation recommendations and disposition of the corrective action to prevent recurrence to the Division Vice President-Nuclear Stations, and to the Supervisor of the Off-Site Review and Investigative Function.

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

b. Authority The Technical Staff Supervisor is responsible to the Station Superintendent and shall make recommendations in a timely manner in all i areas of review, investigation, and quality control phases of plant Page 6.1-8 Amendment No.

'f:

QUAD-CITIES OPR-30 maintenance; operation, and administrative 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 Superintendent shall follow 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 Division Vice President Nuclear Stations and the Supervisor of the Offsite Review and investigative Function.

c. Records

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

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

d. Procedures Written administrative 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 Superintendent, Division Vice President Nuclear Stations, and the Supervisor of the Offsite Review and Investigative Function.

2) Use of committees when necessary.

l

3) Review and approval.

4) Detailed listing of items to be reviewed.

5) Procedures for administration of the quality control activities.

6) Assignment of responsibilities.

e. Personnel l) The personnel performing the Onsite Review and Investigative Function, in addition to the Station Superintendent, shall consist of persons having expertise in:

Page 6.1-9 Amendment No.

o

., :.+ : i .

'(

- "' ~

~ - .

s

. QUAD-CITIES 4

-OPR-30 ri)' fnuclear power plant-technology,

) reactor operations, c) reactor engineering,

' d) - radiological safety.and chemistry, e) instrumentation and control, and f) . mechanical and electric. systems.

2)~ oersonnel 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 offsite

3. 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. ,

i 4

?

i Page 6.1-10 Amendment No.

i 5

N, 4 &

k

- , . ,,-# - - i_~ _/_.- , . . _ _ ~ _ . - . _ _ , , _ . , , _ . . . . _ . . _ _ , , . _ . , . . . . _ _ , -

~

OunD-CITIES DPR-3D j - r-d custa.s,ius e . :-

sumunest 6 1 I I ?

maturver vies.se*sveer .

I' i

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aso un sausses I ,

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1 sm M natuttuasts goe Nam *

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Assesse3rtaffW) Wre spompenfad, '

' use rupts tuuttres saaessa peas.tsee i 9 s am amatms) smann g,7 g, i

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8 I _ . _ _

i * - Senior Operator's License .

I ** - Fuel Honoling Foresen has limited Senior Operator's license

required only during ruel Handling ;

NOTES - The Maintenance Assistent Superintendent is responsible F1-ureO 6.1-1

{

for implementing the Fire Protection Progree Corporate and -

- One Assistent Superintendent or the Staticn Superintendent Station Organization :

l has a Senior Operator's license.

P l

i 1

I

OPR-30 .

- MINIWM SWIFT MANNIN0 CHARTW _

C0Clfl0H OF O'4[ UNIT l

. (40 Fuel in SecoN: Unit) -

License Initial Feel Loacing Cold h tdown or . Above Cold I Cateeve or Durine Refuelmo Refve14n: Snutco-n Shutdown Senior .-

Operator .

License 2 1 . 1 Opgrator. -

License 2 1 2 1 1 Red. Prot. flan l 1 (As Reevired) 1 2 d

ten-Licensed S.h_if_t, Technical. -

Advisor

Ncme peaufred Ncme neoufred 1 I CONDITION OF SECOND UNIT (One Unit at, Not htdown or at Power) initial Fuel Loacing Cole htdown or Above Cold License Category or During Refueling Refuelirg htcown Shutso-n l Senior * -

i Operator 2 2 2 License ;

Operator

3 -

3- 3 License 1 1 1 1

Rad. Prot. Man 1 1

3* (Al Reewired) 3 4 Nen.ticensed

! Shift Technical .

I, Advisor 1 1 1 CDCITION OF SECOND UNIT (One Unit.A,t Cold htdown or Refueling Shutdown)

. License Initial Feel Leading Cold h tdown or Above Cold Category or During Refueling Refueling Shutdown Shutdown Senior' '

Operator License - 2 1 2 i . .

9perator' '

l License 3 'I . 2 l* - Rad. Prot. Man 1* - 1 1 I Non-Licensed 3. (Ag neovired) 3 3 I Shift Technical .

Advisor . Mme Requirati Ncme Require 6 1

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

f Shif t crew co position may be less than the minimum requirements for a period of time s'ot to encaed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to acco=modate unexpected

.aboenee of en duty shift trev members provided it:zediate action is -

taken to restore the shif t trev scoposition to within the citiar.:a re-eiuirements. .

Amendment" 110.67- ,

FIGuaC 6,1 -2 l

QUAD-CITIES

[PR-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. Emergency conditions involving potential or actual release of radioactivity - " Generating Stations Emergency Plan" and station emergency and abnormal procedures.

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

6. Preventive and corrective maintenance operations which could have an effect 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.

11. Fire Protection Program implementation.

12. 00CM implementation.

13. PCP implementation.

14. Working hours of the Shift Engineer, Station Control Room Engineer, Shift Foremen 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. These 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.

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C.- . cl. . -Procedures for : items identified in Specification 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 the Maintenance Assistant Superintendent and Technical Staff Supervisor in the areas of plant maintenance and plant

' inspection. Procedures ~ for' items identified in Specification 6.2.8 and any changes to such procedures shall be reviewed and approved by the Technical Staff Supervisor and the Rad Chem Supervisor.- At 'least one person approving each of the above procedures shall hold a valid senior.

operator license. In addition, these procedures and changes thereto, must have authorization by the Station Superintendent before being -

implemented.

2. Work anci instruction ' type procedures which implement approved maintenance' or modification procedures shall be approved and authorized by the Maintenance Assistant Superintendent where the written authority has been provided by the Station Superintendent. The " Maintenance /

Modification Procedures" 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 requirements of 6.2.A 'or 6.2.8 may be approved by the Department Heads.

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

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

2. The change is approved by two members of the plant management staff, at '

least one of whom holds a Senior Reactor Operator's License on the unit affected.

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

E. Orills of the emergency procedures described in Specification 6.2.A.4 shall be conducted at the frequency specified in the Generating Stations emergency plan.

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

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QUAD-CITIES DPR-30 6.3 REPORTAB E EVENT ACTION A. Die following actions shall be taken for Reportable Events:

1) The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 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 Division Vice President Nuclear Stations.

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DPR-30 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 until authorized by the NRC. The conditions of shutdown shall be promptly reported to Division Vice President Nuclear Stations l or his designated alternate. The incident shall be reviewed pursuant to Specifications 6.1.G.l.a and 6.1.G.2.a and a separate report for each occurrence 1 shall be prepared in accordance with Specification 6.3.A.l. I l

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? 6.5 PLANT ~(PERATING RECORDS p - 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:

e

1.- records of-normal plant operation, including power levels and periods of l operation at each power level;

2. records of principal maintenance and activities, including inspection and repair, regarding principal items of equipment pertaining to nuclear safety; j 3. records and reports of reportable events and safety lirr.it occurrences; .l-

4. records and periodic checks, inspection and/or calibrations performe'd to verify that the surveillance requirements (see Section 4 of these specificatioris) are being met (all equipment failing to meet surveillance requirements and the corrective action taken shall be recorded):

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

l l 6. records of radioactive shipments;

7. records of physic tests and other tests pertaining to nuclear safety;

8. records of changes to operating procedures;

9. shift engineers' logs; and

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

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

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

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

3. records of new and spent fuel inventory and assembly histories;

4. updated, corrected, and as-built drawings of the plant; l

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QUAD-CITIES DPR-30 6.5 PLANT OPERATING RECORDS (cont'd)

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 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 members indicating qualifications, experience, training, and retraining; 1

11. inservice inspections of the reactor coolant system; and

12. minutes of meetings and results of reviews and audits performed by the

, offsite and onsite review and audit functions. ,

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

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,i 6.6 REPORTING REQUIREENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the.following identified reports shall be submitted to the director of the appropriate Regional Office of Inspection 'and Enforcement 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 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 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 commitments shall be included in this report.

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

2. A tabulation shall be submitted on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions (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; and Page 6.6-1 ,

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3. Monthly Operating Report Routine reports of operating statistics and shutdown' experience shall be sutnitted on a monthly basis to the Director, Office of Management Information and Program Control, US 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 ODCM shall be submitted with the Monthly Operating Report within 90 days of the effective date of the change.

A report of major changes 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.

B. Unique Reporting Requirements

1. Radioactive Effluent Release Report (Semi-Annual)

A semi-annual report shall be submitted to the Commission within 60 days after January 1 and July 1 of cach year specifying the quantity of each of the principal radionuclides released to unrestricted areas in 11guld 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 An annual report containing the data taken in the standard radiological monitoring program (Table 4.8-4) shall be submitted prior to May 1 of each year. The cc.itent of the report shall include:

a. Results of all environmental measurements summarized 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. Summaries, interpretations, and analysis of trends of the results are to be provided,

b. An assessment of the monitoring results and radiation dose via the principal pathways of exposure resulting from the plant emissions of radioactivity including the maximum noble gas gamma and beta air doses in the unrestricted area. The assessment of radiation doses shall be performed in accordance with the Off-Site Dose Calculation Manual (00CM).

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

. and of nearby animals producing milk for human consumption, and .the pasture season' feeding practices at dairies-in the monitoring program

~(Table 4.8-4).

d. The reason for the emission if the nearest dairv 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 and wind speed, wind direction,'-and atmospheric.

stability,

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 sampling locations and tables giving distance and direction of sampling locations' from the Station.

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 Director of the NRC Regional Office, with a copy to the Director,.

Office of Nuclear Reactor Regulation, within 30 days from the end of the quarter.

(a) When more than one of the radiouclides in Table 4.8-5 are detected in the medium the reporting level shall have been exceeded if R L.i where C is the coTentration of the ith 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 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 I. .

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(c) This. report shall include an evaluation of any release conditions,

- environmental . factors, or other aspects Lnecessary to explain the ,

anomalous effect.

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

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QUAD-CITIES DPR-30 TABLE 6.6-1 SPECIAL REPORTS Specification Area Reference Submittal Date

, a. Secondary containment leak rate test (2) 4.7.C- Upon completion of each test.

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

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

d. Evaluation of EGC operation 3.3.F Bases Upon completion of initial testing.

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

f. Special Effluents Reports 3.8.A. 30 days following occurence 3.8.B.

3.8.D .

6.6.C.3.

Notes:

1. Each integrated leak rate test of the secondary containment shall be the subject of a summary technical report. This report should include data on the wind speed, wind direction, outside temperature 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 0.005 microcuries or more of removable contamination.

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-QUAD-CITIES DPR-30 6.7 ENVIRONENTAL QUALIFICATION A.' By no later than December 1,~ ~1980, complete and auditible records must be available and maintained at a central location which describe the environmen-tal 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.~ ' Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.

6.7-1 Amendment No.

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v ATTACHMENT D

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. ' Evaluation of Significant Hazards Consideration Description of-Amendment Request Changes to-Section 6 of the Technical Specifications. These changes contain revisions of our original submittal in order to conform to'the Technical ~ Specifications to changes in the regulations.

Basis for Proposed No Significant Hazards Consideration (NSHC)

Determination The Commission has provided guidance concerning the application of specific standards for determining on whether a significant1 hazards consideration exists by provided certain examples. Two of these examples are applicable here. First the majority of the changes were to conform the Technical Specifications-to recent changes to 10 CFR Part 50, Sections 50.72 and 50.73. Clearly these changes fall within example (vii)

"A chance to make a license conform to changes in the regulations...."

We consider the other changes merely administrative in nature which

-therefore fall within example (1).

Therefore, since the application for amendment involves a~

proposed change that is similar to examples for which no significant 4

hazards consideration exists, Commonwealth Edison'has made a-proposed determination that the application involves no significant hazards

. consideration.

8654N t

ML20096A652

Text

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