Text

Amends 86 & 79 to Licenses DPR-19 & DPR-25,respectively, Revising Tech Specs to Reflect Changes in Corporate & Station Organizations
	ML20112G216
Person / Time
Site:	Dresden
Issue date:	03/20/1985
From:	Zwolinski J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20112G219	List: ML20112G216; ML20112G237;
References
	NUDOCS 8503280117
	Download: ML20112G216 (76)
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UNITED STATES g

NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

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COMMONWEALTH EDISON COMPANY DOCKET NO. 50 937 DRESDEN NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO PROVISIONAL OPERATINIi LICENSE Amendment No. 86 License No. DPR-19 1.

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

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A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated February 17, 1983, as supplemented by letters dated April 27 and October 24, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter It B.

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

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

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

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

8503200117 050320 PDR ADOCK 05000237 p

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.R of Provisional Operating License No. DPR-19 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised thrnuph Amendment No. 86, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION h$,k. 4.Anu 2/ John A. Zwolinski, Chief Operating Reactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: March 20, 1985 9

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0 ATTACHMENT TO LICENSE AMENDMENT NO. 86 PROVISIONAL OPERATING LICENSE DPR-19 DOCVET NO. 50-237 Revise Appendix A Technical Specifications by removing the pages identified below ard inserting the attached pages. The revised paces are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT vi vi*

vii vii*

viii viii*

3/4.12-2 3/4.12-2 3/4.12-5 3/4.12-5 3/4.12-6 3/4.12-6 3/4.12-8 through 3/4.12-10 3/4.12-8 through 3/4.12-10 6-1 through 6-29 6-1 through 6-25*

Please note that these pages supersede their counterparts issued by previous amendments including Amendment 83 (Radiological Effluent Technical Specifi-cations) which, although issued November 16, 1984, became effective on March 15, 1985.

DRESDEN II DPR-19 Amendront ND. p, p$, 86 (Table of Contents. Cont'd.)

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4.9 Auxiliary Electrical Systems 4.9.A Station Batteries 3/4.9 - 1 4.9.B (N/A) 3/4.9 - 1 4.9.C Diesel Fuel 3/4.9 - 4 4.9.D Diesel Generator Operability 3/4.9 - 4 4.10 Refueling 3/4.10- 1 4.10.A Refueling Interlocks 3/4.10- 1 4.10.8 Core Monitoring 3/4.10- 1 4.10.C Fuel Storage Pool Water Level 3/4.10- 2 4.10.D Control Rod Drive and Control Rod Drive Maintenance 3/4.10- 3 4.10.E Extended Core Maintenance 3/4.10- 4 4.10.F Spent Fuel Cask Handling 3/4.10- 5 4.11 High Energy Piping Integrity 3/4.11-1 4.12 Fire Protection Systems 3/4.12-1 4.12.A Fire Detection Instrumentation 3/4.12-1 4.12.B Fire Suppression Water System 3/4.12-2 4.12.C Sprinkler Systems 3/4.12-5 4.12.D CO2 System 3/4.12-7 4.12.E Fire Hose Stations 3/4.12-8 4.12.F Penetration Fire Barriers 3/4.12-9 4.12.G Fire Pump Diesel Engine 3/4.12-10 4.12.H Halon System 3/4.12-13 5.0 Design Features 5-1 5.1 Site 5-1 5.2 Reactor 5-1 5.3 Reactor Vessel 5-1 5.4 Containment 5-1 5.5 Fuel Storage 5-1 5.6 Seismic Design 5-2 6.0 Administrative Controls 6-1 6.1 Organization, Review, Investigation and Audit 6-1 6.2 Plant Operating Procedures 6-14 6.3 Actions to be taken in the Event of A Reportable Occurrence in Plant Operation 6-16 6.4 Action to be taken in the Event a Safety Limit is Exceeded 6-16 6.5 Plant Operating Records 6-16 l

6.6 Reporting Requirements 6-18 6.7 Environmental Qualification 6-22 6.8 Offsite Dose Calculation Manual (ODCM) 6-22 6.9 Process Control Program (PCP) 6-24 6.10 Major Changes to Radioactive Waste Treatment Systems (Liquid, Caseous, Solid) 6-25 vi 3959a 3843A

DRESDEN II DPR-19 Amendment No. $f, ps, 94, g$, 86 i

List of Tables

.P.,ggg, Table 3.1.1 Reactor Protection System (Scram) 3/4.1 - 5 Instrumentation Requirements Table 4.1.1 Scram Instrumentation Functional Tests 3/4.1 - 8 Table 4.1.2 Scram Instrumentation Calibration 3/4.1 -10 i

Table 3.2.1 Instrumentation that Initiates Primary Containment Isolation Functions 3/4.2 - 8 Table 3.2.2 Instrumentation that Initiates or Controls the Core and Containment Cooling System 3/4.2 -10 Table 3.2.3 Instrumentation that Initiates Rod Block 3/4.2 -12 Table 3.2.4 Radioactive Liquid Effluent Monitoring Instrumentation 3/4.2 -14 Table 3.2.5 Radioactive Gaseous Effluent Monitoring Instrumentation 3/4.2 -15 Table 4.2.1 Minimum Test and Calibration Frequency for Core and Containment Cooling Systems Instrumentation, Rod Blocks, and Isolations 3/4.2 -17 Table 4.2.2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 3/4.2 -20

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Table 4.2.3 Radioactive Caseous Effluent Monitoring Instrumentation Surveillance Requirements 3/4.2 -22 Table 4.6.2 Neutron Flux and Sample Withdrawal B 3/4.6-26 Table 3.7.1 Primary Containment Isolation 3/4.7 -31 Table 4.8.1 Radioactive caseous Waste Sampling and Analysis Program 3/4.8-22 Table 4.8.2 Maximum Permissible Concentration of Dissolved 3

or Entrained Noble Cases Released From the Site to Unrestricted Areas in Liquid Waste 3/4.8-24 Table 4.8.3 Radioactive Liquid Waste Sampling and Analysis Program 3/4.8-25

, Table 4.8.4 Radiological Environmental Monitoring Program 3/4.8-27 Table 4.8.5 Reporting Levels for Radioactivity concentrations in Environmental Samples 3/4.8-28 Table 4.8.6 Practical Lower Limits of Detection (LLD) for Standard Radiological Environmental Monitoring Program 3/4.8-29 Table 4.11-1 Surveillance Requirements for High Energy Piping Outside Containment 3/4.11-3 Table 3.12-1 Fire Detection Instruments B 3/4.12-17 Table 3.12-2 Sprinkler Systems B 3/4.12-18 Table 3.12-3 CO2 Systems B 3/4.12-19 Table 3.12-4 Fire Mose Stations B 3/4.12-20 & 21 Table 6.1.1 Minimum Shift Manning Chart 6-4 Table 6.6.1 Special Reports 6-23 v11 i

3959a 3843A

DRESDEN II DPR-19 Amendment ND. S(, $$, pg,86 W

List of Flaures Paae Figure 2.1-3 APRM Bias Scram R91stionship to Normal Operating Conditions B 1/2.1-17 Figure 4.1.1 Graphical Aid in the Selection of an Adequate Interval Between Tests B 3/4.1-18 Figure 4.2.2 Test Interval vs. System Unavailability B 3/4.2-34 Figure 3.4.1 Standby Liquid control Solution Requirements 3/4.4-4 Figure 3.4.2 Sodium Penta) orate Solution Temperature Requirements 3/4.4-5 Figure 3.5-1 Maximum Average Planar LHCR 3/4.5-17 (consisting of eight fuel type curves) thru 24 Figure 3.5-2 Core Flow %

3/4.5-27 & 28 Figure 3.6.1 Minimum Temperature Requirements per Appendix G of 10 CFR 50 3/4.6-20 Figure 4.6.1 Minimum Reactor Pressurization Temperature B 3/4.6-25 Figure 4.6.2 Chloride Stress Corrosion Test Results at 500*F B 3/4.6-27 Figure 4.8.1 Owner Controlled / Unrestricted Area Boundary B 3/4.8-38 Figure 4.8.2 Detail of Central Complex B 3/4.8-39 Figure 6.1-1 Corporate and Station Organization 6-3 g.

g vill 3918a 8401D

DRESDEN II DPR-19 Amendmnt No. [, 86 3.12 LIMITING CONDITIONS FOR OPERATION 4.12 SURVEILLANCE REQUIREMENTS (Cont'd.)

(Cont'd.)

b.

Restore the in-operable instru-ment (s) to operable status within 14 days, or prepare and submit a report to the Commission pursuant to Speci-l fication 6.6.B within the next 30 days outlining the cause of the mal-function, action taken and the plans for restoring the instrument (s) to operable status, c.

The provisions of Specification 3.0.A. are not applicable.

B.

Fire Suppression Water System B.

Fire Suppression Water System 1.

The Fire Suppression 1.

The Fire Suppression Water System shall be Water System shall be operable at all times demonstrated operable:

with:

a.

A flow path a.

At least once per capable of taking 31 days by suction from the verifying valve 2/3 Intake Canal positions, for Unit 2/3 Fire Pump.

j b.

A flow path b.

At least once per 7

i capable of taking,

12 months by suction from the cycling each Unit 1 Intake testable valve Canal for Unit 1 in the flow path fire pump.

through one complete cycle.

3/4.12-2 l

3696a 3124A

DRESDEN II DPR-19 Amendment No. pf, 86 3.12 LIMITING CONDITIONS FOR OPERATION 4.12 SURVEILLANCE REOUIREMENTS (Cont'd.)

(Cont'd.)

report to the Commission pursuant to l

Specification 6.6.B within the next 30 days outlining the plans, l

action taken 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 6.6.B outlining the actions taken and the plans and schedule for re-storing the system to operable status.

i 4.

If the requirements of l

3.12.B.3.a cannot be met, an orderly shutdown shall be initiated, and the reactor shall be in cold shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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5 C.

Sprinkler Systems C.

Sprinkler Systems 1.

The sprinkler systems 1.

At least once per 31 given in Table 3.12-2 days by verifying that shall be operable at each valve, manual, all times when power-operated, or equipment in the area automatic, in the flow 3/4.12-5 3696a 3124A

DRESDEN II DpR-19 Amend;cnt No. p2, 86 3.12 LIMITING CONDITIONS FOR OPERATION 4.12 SURVEILLANCE REOUIREMENTS (Cont'd.)

(Cont'd.)

that is sprinkler path is in its correct protected is required position.

to be operable.

2.

With a sprinkler 2.

At least once per 12 system inoperable, months by cycling each establish fire testable valve in the inspections with flow path through at backup fire supression least one complete equipment within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

cycle of full travel, a.

In the Unit 2/3 turbine mezzanine 538' elevation area or Unit 2 hydrogen seal oil area, a continuous fire watch is to be established, b.

In all other areas given in Table 3.12-2 perform surveillance hourly.

3.

Restore the system to 3.

At least once per operable status within operating cycle:

14 days, or prepare and submit a report to a.

A system functional the commission pursuant test shall be to Specification performed which l

6.6.B within the includes simulated next 30 days outlining automatic actuation the cause of of the system and inoperability, action verifying that the taken and the plans automatic valves in for restoring the

,the flow path pystem to operable actuate to their status.}

correct positions.

I-b.

The sprinkler headers shall be inspected to verify their integrity.

3/4.12-6 3696a 3124A

DRESDEN II DPR-19 Am:ndm2nt ND. Pf, 86 i

3.12 LIMITING CONDITIONS FOR OPERATION 4.12 SURVEILLANCE REQUIREMENTS (Cont'd.)

(Cont'd.)

unprotected areas within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and perform inspection at least hourly.

5.

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

Specification 6.6.B.

within the next 30 days outlining the cause of inoperability, action taken and the plans and schedule for restoring the system to operable status.

6.

The provisions of Specification 3.0.A.

are not applicable.

E.

Fire Hose Stations E.

Fire Hose Stations 1.

The Fire Hose 1.

At least once per 31 Stations given in days, a visual Table 3.12-4 shall inspection of each fire be operable at all hose station shall be times when the made to assure all equipment in the equipment is available i

area is required to at the station.

be operable.

2.

With a hose station 2.

At least once per inoperable route an operating cycle, the additional equivalent hose will be removed capacity hose to the for inspection and unprotected area from repacked. Degraded g.

g an operable hose gaskets in the station within I hour.

couplings will be replaced.

3.

When a hose station 3.

At least once per 3 becomes inoperable, years, each hose restore to operable station valve will be 3/4.12-8 3696a 3124A

DRESDEN Il DPR-19 Amendssnt No. $d, 86 3.12 LIMITING CONDITIONS FOR OPFR& TION 4.12 SURVEILLANCE REQUIREMENTS (Cont'd.)

^

(Cont'd.)

status within 14 days partially opened to or report to the verify valve Commission pursuant operability and no to specification blockage.

l 6.6.B within the next 30 days outlining the cause of inoperability, action taken and plans for restoring the hose station to operability.

4.

The provisions of 4.

At least once per 3 Specification 3.0.A years a hydrostatic are not applicable.

test will be conducted on each hose at a pressure at least 50 psig above line pressure at that station.

F.

Penetration Fire Barriers F.

Penetration Fire Barriers 1.

All penetration fire 1.

Each of the required barriers (including penetration fire fire doors and fire barriers shall be dampers) protecting verified to be intact safety related areas by a visual shall be intact, inspection:

except as stated in specification a.

At least once per 3.12.F.2 below.

18 months, and b.

Prior to declaring a penetration fire barrier intact following repairs or maintenance.

I 6

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2.

With one or more of the required penetration fire barriers not in-tact, establish a con-tinuous fire watch on at least one side of the affected penetra-tion within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months when 3/4.12-9 3696a 3124A

DRESDEN II DPR-19 Amendment Ns. $(, S6 3.12 LIMITING CONDITIONS FOR OPERATION 4.12 SURVEILLANCE REQUIREMENTS (Cont'd.)

(Cont'd.)

the area on either side of the affected pene-tration contains equip-ment required to be operable.

3.

The provisions of Specification 3.0.A are not applicable.

4.

Restore the non-fune-tional fire barrier penetrations to oper-able status w} thin 7 days or prep'are and submit a report to the Commission pursuant to l

Specification 6.6.B within the next 30 days outlining the cause of inoperability, action taken and the plans and schedule for restoring the penetection fire barriers to operable status.

G.

See 3.12.B.

G.

Fire Pump Diesel Engine 1.

The fire pump diesel engine shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying:

1) The fuel storage day tank contains at least 150 gallons of fuel, and 3/4.12-10 l

3696a l

3124A

l DRESDEN II DPR-19 Amendment No. P2, 86

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6.0 ADMINISTRATIVE CONTROLS 6.1 Organization. Review. Investigation and Audit A.

The Station Superintendent shall have overall full-time i

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 l

experience requirements for plant manager.

B.

The organization chart of the corporate management which relates to the operatior of this station and the normal functional organization chart for operation of the station are shown in Figure 6.1.1.

C.

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

The Operating Ar.sistant Superintendent Operating Engineer, Shift Engineers, and Shift Foreman shall have a Senior Operating License. The Fuel Handling Foreman has a 1

limited Senior Operating License. The Division Vice President Nuclear Stations on the corporate level has responsibility for the Fire Protection Program. An Operating Engineer at the station will be responsible for implementation of the Fire Protection Program. A fire brigade of at least 5 members shall be maintained on-site at all times. This excludes the j

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

D.

Qualifications of the station management and operating staff shall meet minimum acceptable levels as described in ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel," dated March 8, 1971, with the exception of the Radiological-Chemical Supervisor who shall meet or exceed the qualifications of Radiation Protection Manager of Regulatory Guide 1.8, September, 1975, and the Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific j.

.or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents. The individual filling the position of Administrative and Support Services Assistant Superintendent shall meet the minimum acceptable level for " Technical Manager" as described in 4.2.4 of ANSI N18.1 - 1971.

-l 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.

6-1 3699a 3124A

DRESDEN 11 DPR-19 Amand: ant No. P2, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

A training program for the fire brigade shall be maintained under the direction of the Operating scsineer and shall meet or exceed the requirements of Saction 27 of the NFPA Code - 1975, except for fire brigade training sessions which shall be held at least quarterly.

F.

Retraining shall be conducted at intervals not exceeding two years.

G.

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

1.

The Supervisor of the Offsite Review and Investigative Function shall be appointed by the Vice President-Nuclear l

Operations.

The Audit Function shall be the responsibility of the Manager of Quality Assurance and shall be independent of operations.

Offsite Review and Investiaative Function a.

The Supervisor of the Offsite Review and Investigative Function shall:

(i) provide directions for the review and investigative function and appoint a senior participant to provide appropriate direction, (ii) select each participant for this function, (iii) select a complement of more than one participant who collectively possess background and qualifications in the subject matter under review to provide compre-hensive interdisciplinary review coverage under this function, (iv) independently review and approve the findings and recommendations developed by personnel performing the review and investigative function, (v) approve and report in a timely manner all findings of noncompliance with NRC requirements and provide recommendations,to,the, Station Superintendent, Division

,,Vice President-Nuclear' Stations, Manager of Quality Assurance, and the Vice President-Nuclear Operations.

3 During periods when the Supervisor of the 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.

6-2 3699a 3124A I

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CHAIRIIAN AND i

FRE$iDENT E

I EXECUTIVE VICE PRESIDENT (CONSTRtPCTION, FRJDUCTICII AND ENCINEERINC) i I

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VICE PRESIDENT VICE FRESIDENT (ENCINEERINC) d (NUCLEAR OPERATIONS)

STAFF SerIDTEE RELATIONS

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MANAGER DIVISION ASSISTAIIT ASSISTANT MANAGER STATION VICE PRESIDENT VICE PRESIDENT g

CONSTRUCTICII ASID GENERAL IICR.

VICE PRESIDENT e)ALITY l

ASSURANCE NUCLEAR STATIONS l

I FONER SUFFLT

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SYSTWI QUALITY NUCLEAR FUEL PROGUCTICII STATION IINCLEAR DIRECTOR MANACER OF ASSUR*NCE FR0buCTICII l SERVICES MAaIACER SERVICES TRAINIIIC EIICINEERIIIC IIUCl. EAR IEUC1. EAR Is m r88 (CNENISTRY &

MANAGER MANACER 81A80ACER LICENSIIIC SAFETT

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MAINTENAsICE Rae WASTE SERVICES, (NUCLEAR REAC10R

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ASSURAIBCE

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INC IIAI ARMIIISTRATOR SUFFORT SEIIVICES l

ASSISTAf1T SOFERIIITEIIDENT SUPERINTENDENT l

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TRA!!!IIC OFFICE SUPERVISOR ENCIIIEERS ELECTRICIAN INSTRISSIIT SECNANIC

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REVIEW FUEL Q.C.

OPERAggIIe BIASTER IIASTER IIASTER j

SUPERVISOR SUPERVISOR

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PROTEt.TIcII 1

TECR STAFF RAD-CIMBI SHIFT INSFECTOR l

SUPERVISOR

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CorForate and Station Ortenisation 6-3 00.

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DRESDEN II DPR-19 Amendment No. N, 86 TABLE 6.1.1 MINIMUM SHIFT MANNING CHART (1)

CONDITION OF NUMBER OF MEN IN EACH POSITION UNITS STA or NON-RAD WITH FUEL FIRST UNIT SECOND UNIT THIRD UNIT SR0(2)

R0(3) SCRE LIC.

MEN Cold Shutdown Cold Shutdown Cold shutdown 1

1 0

5 1

ONE Above Cold Shutdown Cold Shutdown Cold Shutdown 2

2 1

5 1

Cold Shutdown Cold Shutdown Cold Shutdown 1

2 0

5 1

f TWO Above Cold Shutdown Cold Shutdown Cold Shutdown 2

3 1

5 1

f Above Above Cold Shutdown Cold Shutdown Cold Shutdown 2

3 1

5 1

i f

Cold Shutdown Cold Shutdown Cold shutdown 1

3 0

5 1

THREE Above I

Cold Shutdown Cold Shutdown Cold Shutdown 2

4 1

5 1

l Above Above Cold Shutdown Cold Shutdown Cold Shutdown 2

4 1

5 1

l Above Above Above i

Cold Shutdown Cold Shutdown Cold Shutdown 2

4 1

5 1

SRO

- Senior Reactor Operator. At least one SRO must remain in the Control Room at all times when one or more units is above cold shutdown. This person may, however, leave the Control Rocrn for periods not to exceed 10 minutes, provided another SRO acts as relief operator. The SCRE or shift supervisor can fulfill this requirement.

RO'

- Reactor Operator (For each reactor containing fuel, one RO will be in the Control Room at all times.)

STA

- Shift Technical Advisor.

SCRE

- Station Control Rom Engineer (STA with Senior Reactor Operator's License).

NON-LIC.

- Equipment Operators and Equipment Attendants.

RAD MEN

- Radiation Protection Men.

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i NOTES: (1) + Shift crew conposition mgy be less than the minimum requirements for a perlogi of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accomodate unexpected absence of on-duty shift crew menbers provided inmediate action is taken to restore the shift crew conposition to within the minimum requirements.

(2) - Does not include the licensed Senior Reactor Operator or Senior Reactor Operator limited to fuel handling, supervising CORE OPERATIONS.

(3) - Shall not operate units on which they are not Ilcensed.

ADDITIONAL REQUIREMENTS l

A.

SRO can be RO at controls.

I 8.

SRO in Control Roten cannot provide relief to SRO/R0 at controls.

C.

SRO in Control Room must be in sight of or audible range of operator at all times or be in audible range of annunciators.

6-4 3699a 3124A

DRESDEN II DPR-19 Amind2snt No. $2, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

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 pro-cedures, equipment or systems as described in the safety analysis report and 2) tests or experi-ments completed under the provision of 10 CFR Section 50.59 to verify that such actions did not constitute unreviewed safety questions.

Pro-posed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of Quality Assurance.

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

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

(4) Proposed changes in Technical Specifications or NRC operating licenses.

(5) Noncompliance with NRC requirements, or of inter-nal 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 requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notifi-cation to the Commission.

I

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Allrecogni*zedindicationsofanunanticipated (8) 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 changes.

6-5 l

3699a 3124A

DRESDEN II DPR-19 Amendzant No. Sf, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station Superintendent, Division Vice President - Nuclear Stations and l

Manager of Quality Assurance.

b.

Audit Function The Audit Function shall be the responsibility of the Manager of Quality Assurance independent of the Production Department. Such responsibility is delegated to the Director of Quality Assurance for Operating and to the 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 two years or less as designated below.

(1) Audit of the.Conformance of facility operation to provisions contained within the Technical Speci-fications 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 six months.

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

t (5) Audit of the Facility Emergency Plan and implementing procedures at least once per 12 l

months.

6-6 3699a 3124A

DRESDEN II DPR-19 AmendmentNo.pf,pd,86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(6) Audit of the Facility Security Plan and implementing procedures at least once per 12 months.

(7) Audit onsite and offsite reviews.

(8) Audit of Facility Fire protection Program and implementing procedures at least once per 24 months.

(9)

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

(10) The ODCM and implementing procedures at least

.s once per 24 months.

(11) The PCP and implementing procedures for solidifi-cation of radioactive waste at least once per 24 months.

(12)

Report all findings of noncompliance with NRC requirements and recommendations and results of each audit to the Station Superintendent, the Division Vice President-Nuclear Stations, Manager l

of Quality Assurance, the General Superintendent of Production Eystems Analysis, and to the Vice President-Nuclear Operations, c.

Authority The Manager of Quality Assurance reports to the Chair-man and President. The Supervisor of the Offsite Review and Investigative Function reports to the Manager of Nuclear Safety who reports to the Chairman and President. Either the Manager of Quality Assurance or the Supervisor of the Offsite Review and Investigative Function has the authority to order unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions.

d.

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

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DRESDEN II DPR-19 Amendmant Ns. Pf, pd, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(2) Copies of documentation, reports, and l

correspondence shall be kept on file at the station.

l e.

Procedures 1

i Written administrative procedures shall be prepared and maintained for the off-site reviews and i

investigative functions described in Specifications 6.1.C.1.a.

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

(6)

Determining satisfactory cocpletion of action required based on approved findings and recommendations reported by personnel performing the review and n

investigative function.

1 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 i

in one or more of the following disciplines as appropriate for the subject or subjects bqing reviewed and investigated.

t t

(

(a) nuclear power plant technology (b) reactor operations (c) utility operations (d) power plant design (e) reactor engineering (f) radiological safety 6-8 l

l 0146W 1

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DRESDEN II DPR-19 Am3ndm2nt No. P2, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(g) reactor safety analysis (h) instrumentation and control (1) metallurgy (j) any other appropriate disciplines required by unique characteristics of the facility.

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

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

(b) Reactor Operations Engineering graduate or equivalent with 5 years experience in nuclear power plant oper9tions.

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

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

(e) Reactor Enaineering Engineering graduate or equivalent.

In addition, at least 5 years of emperience in nuclear plant engineering, operation, and/or i

l'

graduate work in nuclear engineering or equivalent in reactor physics is required.

(f) Radioloalcal Safety Engineering graduate or equivalent with at least 5 years of experience in radiation control and safety.

6-9 0146W

DRESDEN II DPR-19 Amendment No Sf, p3, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

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

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

(i) Metalluray 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 Oncite Review and Investigative Function shall be

pervised by the Station Superintendent, s.

Onsite Review and Investiaative Function The Station Superintendent shall:

(i) 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 direction; (ii) approve participants for this function; (iii) 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 inter-disciplinary review 5

coverage under this function; (iv) independently review and approve the: findings and recommendations developed by personnel performing the Review and Investigative Function; (v) report all findings of noncompliance with NRC requirements, and provide recommendations to the Division Vice President-Nuclear l

Stations and the Supervisor of the Offsite Review and Investigative Function; and (vi) 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.

0146W

DRESDEN II DPR-19.

Amindsent No. Pf, p3, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

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

(1)

Review of:

1) procedures required by Specifica-tion 6.2 and changes thereto, 2) any other pro-posed procedures or changes thereto as determined by the Plant Superintendent to affect nuclear safety.

(2) Review of all croposed tests and experiments that affect nue) ar safety.

(3)

Review of all proposed changes to the Technical

-specificaticas.

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

(5)

Investigation of all noncompliance with NRC requirements and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Division Vice l

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

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

(7). Performance of special reviews and investigations and reports thereon as requested by the l

Supervisor of the Offsite Review and Investigative Function.

(8) Review the Station Security Plan and shall submit l

recommended changes to the Division Vice l

President-Nuclear Stations.

I (9) Review the Emergency Plan and station implementing procedures and shall submit l

recommended changes to the Division Vice President-Nuclear Stations.

(10)

Review of reportable events and actions taken to l

prevent recurrence.

t 6-11 0146W

DRESDEN II DPR-19 AmendAsnt No, pd, p$, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(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 chanses 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 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, 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 the Division Vice President-Nuclear l

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 the Division Vice President-Nuclear Stations, l

the Supervisor of the Offsite Review and Investigative Function, the Station j

Su'perintendent and the Manager of Quality Assurance.

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

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DRESDEN II DPR-19 Am:ndmint No. f/, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

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.

(3) Review and approval.

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

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

(6) Assignment of responsibilities, e.

Personnel (1) The personnel performing the Onsite Review and Investigative Function, in addition to the Station Superintendent, shall consist of persons having expertise in:

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

(2)

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

H.

1.

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

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DRESDEN II DPR-19 Amendment No. %, f3, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

2.

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

6.2 Plant Operatinz 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 l

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 implementing procedures.

i 11.

g Fire Protection-Program implementation.

12.

ODCM implementation.

13.

PCP implementation.

14.

Working hours of the Shift Engineer, Station Control Room Engineer, Shif t Foreman, and Nuclear Station Operator job l

classifications such that the heavy use of overtime is not l

routinely required.

6-14 l

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DRESDEN II DPR-19 Amindu nt No. %, %, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

8.

Radiation contec1 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.

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, fuel handling, or instrument maintenance, 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 Radiological Chemical Supervisor. At least one person approving each of the above procedures shall hold a valid senior operator's license.

In addition, these procedures and changes thereto must have 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 Procedure" utilized for safety related work shall be so approved only if procedures referenced in the

" Maintenance / Modification Procedure" have been approved as required by 6.2.A.

procedures which do not fall within the 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 al,tered.

2.

The change is approved by two members of the plant a

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

i 3.

The change is documented, reviewed by the Onsite Review i

and Investigative Function and approved by the Station Superintendent within 14 days of impicmentation.

i l

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DRESDEN II DPR-19 Amendment No. M, %, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

E.

Drills of the emergency procedures described in Specification 6.2.A.4 shall be conducted at the frequency specified in the Generating Station Emergency Plan. These drills will be planned so that during the course of the year, comununication links are tested and outside agencies are contacted.

6.3 Action to be Taken in the Event of a Reportable Event in Plant Operation Any reportable event shall be promptly reported to the Division l

Vice President-Nuclear Stations or his designated alternate. The incident shall be promptly reviewed pursuant to Specification 6.1.G.2.a(5) and a separate report for each reportable event shall l

be prepared in accordance with the requirements of Specification 6.6.B.

6.4 Action to be Taken in the Event a Safety Limit is Exceeded If a safety limit is exceeded, the reactor shall be shut down issnediately and reactor operation shall not be resumed until authorized by the NRC.

The conditions of shutdown shall be promptly reported to the Division Vice President-Nuclear Stations l

or his designated alternate. The incident shall be reviewed pursuant to Specification 6.1.G.I.a and 6.1.G.2.a and a separate report for each event shall be prepared in accordance with Specification 6.6.B.

l 6.5 Plant Operating Records A.

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

1.

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

2.

Records of principal maintenance activities, including inspection and repair, regard 1N; principal items of A

4 equipmentpertainingto.nuc{earsafety.

)

i 3.

Records and reports of reportabic and safety limit events.

l 4.

Records and periodic checks, inspection and/or calibrations performed to verify the Surveillance Requirements (See Section 4 of these Specifications) are beir.g met. All equipment falling to meet surveillanca requirements and the corrective action taken shall be recorded.

6-16 0146W

DRESDEN II DPR-19 Am2ndmint No. 94 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

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.

10.

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

B.

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

1.

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

2.

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

3.

Records of new and spent fuel inventory and assembly histories.

4.

(Deleted) 5.

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

6.

Records of plant radiation and contamination surveys.

i 7.

Records of off-site environmental monitoring surveys.

8.

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

9.

ReIords of radioactivity in 11guld and gaseo'us wastes released to the environment.

i l

10.

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.

11.

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

i

l 6-17 l

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DRESDEN II DpR-19 Am:nd:snt No. $d, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

12. Inservice inspections of the reactor coolant system.

13. Minutes of meetings and results of reviews performed by the off-site and on-site review functions.

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

6.6 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Regional Administrator of the appropriate Regional Office of the NRC 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 planr.ed 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 FSAR 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 i

based on other commitments shall be included in this report.

Startup reports shall be submitted within (1) 90 days 7

j following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup 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 i

reports shall be submitted at least every three months until all three events have been completed.

i 6-18 l

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DRESDEN II DPR-19 d

Amendaent No. $, P$, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

2.

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

e.g.,

reactor operations and surveillance, inservice laspection, routine maintenance, special maintenaoce (describe maintenance),

waste processing, and refueli?a. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than :10% 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.

.g 3.

Monthlv Operatina Report Routine reports of operating statistics and shutdown experiences shall be submitted on a monthly basis to the Director, Office of Resource Management US Nuclear l

Regulatory Commission, Washington, DC 20555, with a copy to the appropriate Regional Administrator, to arrive no l

later than the 15th of each month following the calendar month covered by the report.

B.

Reportable Events Reportable events will be submitted as required by 10CFR 50.73.

i C.

Unique Reportina Requirements 1.

Radioactive Effluent Release Report (Semi-Annual)

A 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.

Note:

This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

6-19 0146W

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DRESDEN II DPR-19 Amendment No. p2, 90, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

2.

Environmental Radioactivity Data'(Annual Report)

Standard Radiological Monitoring Program a.

(1) Non-Routine Report (a) 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 4.8-1 and if the radioactivity is attributable to plant operation, a written report shall be submitted to the Regional Administrator 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. When more than one of the radionuclides in Table 4.8-1 are detected in the medium, the reporting level shall have been exceeded if IC /(RL){ is equal to or greater than 1 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 4.8-1 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, Appandix I.

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

(2) Annual Operating Report An annual report containing the data taken in the standard radiological monitoring program (Table 4.8-1) shall be submitted by March 31 of the next year.

The content of the report shall include:

6-20 l

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DRESDEN II DPR-19 Amendmsnt No. %, %, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(a) Results of environmental sampling summarized on a quarterly basis following 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.nall 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 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 ODCM.

(c) Results of the census to determine the locations of animals producing milk for human consumption, and the pasture season feeding practices at dairies in the monitoring program.

(d) The reason for the omission if the nearest dairy to the station is not in the monitoring program.

(Table 4.8-5)

(e) An annual summary of meteorological conditions concurrent with the releases of gaseous effluents in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.

~

(f) The results of the interlaboratory comparison program described in section.3.8.E.7.

e (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.

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DRESDEN II DPR-19 Am2ndment No. yd, $0, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

3.

Special Reports Special reports shall be submitted as indicated in Table 6.6.1.

6.7 Environmental Qualification A.

By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588

" Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment" December 1979. Copies of these documents are attached to Order for Modification of License DPR-19 dated October 24, 1980.

B.

By no later than December 1, 1980, complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.

6.8 Offsite Dose Calculation Manual (ODCM)

A.

The ODCM shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCO's contained in these Technical Specifications. Methodologies and calculational procedures acceptable to the Commission are contained in NUREG-0133.

4' t:

The ODCM shall be submitted to the Commission at the time of ;

proposed Radiological Effluent Technical Specifications and shall be subject to review and approval by the Commission prior to implementation.

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DRESDEN II DPR-19 Amindasnt No. P@, P5, 86 TABLE 6.6.1 SPECIAL REPORTS SPECIFICATION

&REA REFERENCE SUBMITTAL DATE a.

Response time of safety related instruments (2) 1.0.E (Dres, 1)

Annual Report b.

Main steam isolation valve and feedwater power operated isolation valves closure times (2) 3.7.B.1.c (Dres. 1) Annual Report Primary Coolant leakage to Drywell (4) 3.6.D Bases 5 years (1) c.

d.

In-Service Inspection Evaluation (4) 3.6.F Bases 5 years (1) 4 e.

Evaluation of Economic Generation 3.3.C Bases Upon completion of Control System (ECCS) operation (4) initial testing f.

Failed Fuel Detection (4) 3.2 Bases 5 years (1) g.

Main Steam Line Leakage to Steam-Tunnel (4) 3.6.D Bases 5 years (1) h.

In-service Inspection Development (4) 3.6.F Bases 5 years (1) 1.

In-Service Inspection of Sensitized Stainless Steel Components (3) 4.6.F 4 years (1)

j. Secondary Containment Leak Rate Test (4) 3.7.C.1 within 90 days after completion of each test k.

High off-gas discharge rate (2) 3.8.A.4 (Dresden 1) within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of occurrence 1,.

Radioactive source Leak Test}ng.(5).

3.8.F Annual Report NOTES:

1.

The report shall be submitted within the period of time listed based on the commercial service date as the starting point.

2.

Dresden 1 only 3.

Dresden 2 only 4.

Dresden 2 and 3 only.

5.

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

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DRESDEN II DPR-19 Amendment No. Pi, $$, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

B.

Licensee initiated changes to the ODCM may be made provided the change:

1.

Shall be submitted to the Commission by inclusion in the Monthly Operating Report pursuant to Specification 6.6.A.3.

within 90 days of the date the change (s) was made effective and shall contain:

Sufficiently detailed information to support the a.

change. Information submitted should consist of a package of those pages of the ODCM to be changed together with appropriate analyses or evaluations justifying the change (s);

b.

A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and Documentation of the fact that the change has been c.

reviewed and found acceptable by the Onsite Review function.

2.

Shall become effective upon review and acceptance by the Onsite Review function.

6.9 Process Control Program (PCP)

A.

The PCP shall contain the sampling, analysis, and formulation determination by which solidification of radioactive wastes from 11guld systems is assured.

B.

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

C.

Licensee initiated changes may be made to the PCP provided the change:

4 1.

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

Sufficiently detailed information to support the change; a.

b.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and 6-24 0146W

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l DRESDEN II DPR-19

)

Amendment No. p4!, P3, 86 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

Documentation that the change has been reviewed and found c.

acceptable by the Onsite Review Function.

l 2.

Shall become effective upon review and acceptance b'y the Onsite Review Function.

l 6.10 Major Changes to Radioactive Waste Treatment Systems (Liquid, Gaseous, Solid) (See note below)

A.

Licensee initiated major changes to the radioactive waste systems may be made provided:

1.

The change is reported in the Monthly Operating Report for the period in which the evaluation was reviewed by the Onsite l

Revle.w Function. The discussion of each change shall contain:

a.

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

Sufficient detailed information to support the reason for the change; A detailed description of the equipment, components, and c.

p.*ocess involved and the interfaces with other plant systems; d.

An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments; e.

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

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

Documentation of the fact that the change was reviewed and found acceptable by the Onsite Review Function.

l 2.

The change shall become effective upon review and acceptance by the Onsite Review Function.

l Note:

Licensee may choose to submit this information as part of the annual FSAR update.

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NUCLEAR REGULATORY COMMISSION 5

j WASHINGTON, D. C. 20555

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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE t

Amendment No. 79 License No. DPR-25 1.

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

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated February 17, 1983, as supplemented by letters dated April 27 and October 24, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

_?.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility Operating License No. DPD-?5 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 79, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR GULATORY COMMISSION b'

T/

John A. Zwolinski, Chief Operating Peactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: March 20, 1985 9

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ATTACHMENT TO LICENSE AMENDMENT NO. 79 FACILITY OPERATING LICENSE DPR-25 DOCKET NO. 50-249 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

.s REMOVE INSERT vi vi*

vii vii*

viii viii*

3/4.12-2 3/4.12-2 3/4.12-5 3/4.12-5 3/4.12-6 3/4.12-6 3/4.12-8 through 3/4.12-10 3/4.12-8 through 3/4.12-10 6-1 through 6-29 6-1 through 6-25*

i

Please note that these pages supersede their counterparts issued by previous amendments, including Amendment 77 (Radiological Effluent Technical Specifi-cations) which, although issued November 16, 1984, became effective on March 15, 1985.

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DRESDEN III DPR-25 AmendaOnt Co }$, }4, 79 (Table of Contents. Cont'd.)

l l

f_818 4.9 Auxiliary Electrical Systems 3/4.9 - 1 4.9.A Station Batteries 3/4.9 - 1 4.9.B (N/A) 4.9.C Diesel Fuel 3/4.9 - 4 4.9.D Diesel Generator Operability 3/4.9 - 4 4.10 Refuelins 3/4.10- 1 4.10.A Refueling Interlocks 3/4.10- 1 4.10.B Core Monitoring 3/4.10- 1 4.10.C Fuel Storage Pool Water Level 3/4.10- 2 4.10.D Control Rod Drive and Control Rod Drive Maintenance 3/4.10- 3 4.10.E Extended Core Maintenance 3/4.10- 4 4.10.F Spent Fuel Cask Handling 3/4.10- 5 4.11 High Energy Piping Integrity 3/4.11-1 4.12 Fire Protection Systems 3/4.12-1 4.12.A Fire Detection Instrumentation 3/4.12-1 4.12.B Fire Suppression Water System 3/4.12-2 4.12.C Sprinkler Systems 3/4.12-5 4.12.D CO2 System 3/4.12-7 4.12.E Fire Hose Stations 3/4.12-8 4.12.F Penetration Fire Barriers 3/4.12-9 4.12.G Fire Pump Diesel Engine 3/4.12-10 4.12.H Halon System 3/4.12-13 5.0 Design Features 5-1 5.1 Site 5-1 5.2 Reactor 5-1 5.3 Reactoc Vessel 5-1 5.4 Containment 5-1 5.5 Fuel Storage 5-1 5.6 Seismic Design 5-2 6.0 Administrative Controls 6-1 6.1 Organization, Review, Investigation and Audit 6-1 6.2 Plant Operating Procedures 6-14 6.3 Actions to be taken in the Event of A Reportable Occurrence in Plant Operation 6-16 6.4 Action to be taken in the Event a Safety Limit is Exceeded 6-16 6.5 Plant Operating Records 6-16 l

6.6 Reporting Requirements 6-18 6.7 Environmental Qualification 6-22 6.8 Offsite Dose Calculation Manual (ODCM) 6-22 6.9 Process Control Program (PCP) 6-24 6.10 Major Changes to Radioactive Waste Treatment Systems (Liquid, Gaseous, Solid) 6-25 Vi 3958a

)

0009A

DRESDEN III DPR-25 AmendmentNo.JS,%,p,79 List of Tables f.81*

Table 3.1.1 Reactor Protection System (Scram) 3/4.1 - 5 Instrumentation Requirements Table 4.1.1 Scram Instrumentation Functional Tests 3/4.1 - 8 Table 4.1.2 Scram Instrumentation Calibration 3/4.1 -10 Table 3.2.1 Instrumentation that Initiates

~

Primary Containment Isolation Functions 3/4.2 - 8 Table 3.2.2 Instrumentation that Initiates or Controls the Core and Containment Cooling System 3/4.2 -10 Table 3.2.3 Instrumentation that Initiates Rod Block 3/4.2 -12 Table 3.2.4 Radioactive Liquid Effluent Monitoring Instrumentation 3/4.2 -14 Table 3.2.5 Radioactive Gaseous Effluent Monitoring Instrumentation 3/4.2 -15 Table 4.2.1 Minimum Test and Calibration Frequency for Core and Containment Cooling Systems Instrumentation, Rod Blocks, and Isolations 3/4.2 -17 Table 4.2.2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 3/4.2 -20 Table 4.2.3 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 3/4.2 -22 Table 4.6.2 Neutron Flux and Sample Withdrawal B 3/4.6 -26 Table 3.7.1 Primary Containment Isolation 3/4.7 -31 Table 4.8.1 Radioactive Gaseous Waste Sampling and Analysis Program 3/4.8 -22 Table 4.8.2 Maximum Permissible Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste 3/4.8 -24

,Table 4.8.3 Radioactive Liquid Waste Sampling and Analysis Program 3/4.8 -25 Table 4.8.4 Radiological Environmental Monitoring Program 3/4.8 -27 Table 4.8.5 Reporting Levels for Radioactivity Concentrations in Environmental Samples 3/4.8 -28 Table 4.8.6 Practical Lower Limits of Detection (LLD) for Standard Radiological Environmental Monitoring Program 3/4.8 -29 Table 4.11-1 Surveillance Requirements for High Energy Piping Outside containment 3/4.11-3 Table 3.12-1 Fire Detection Instruments B 3/4.12-17 Table 3.12-2 Sprinkler Systems B 3/4.12-18 Table 3.12-3 CO2 Systems B 3/4.12-19 Table 3.12-4 Fire Hose Stations B 3/4.12-20 & 21 Table 6.1.1 Minimum Shift Manning Chart 6

-4 Table 6.6.1 Special Reports 6

-23 vii 3958a 0009A

DRESDEN III DPR-25 Amendment No. Jd, 78, J4, 79 j

List of Fimures EAL*.

Figure 2.1-3 APRM Bias Scram Relationship to Normal Operating Conditions B 1/2.1-17 Figure 4.1.1 Graphical Aid in the Selection of an Adequate Interval Between Tests B 3/4.1-18 Figure 4.2.2 Test Interval vs. System Unavailability B 3/4.2-33 Figure 3.4.1 Stendby Liquid Control Solution Requirements 3/4.4-4 Figure 3.4.2 Sodium Pentaborate Solution Temperature Requirements 3/4.4-5 Figure 3.5-1 Bundle Average Exposure (NWD/NT)

(Sheet 1 of 5) 3/4.5-17 Figure 3.5-1 Planar Average Exposure (NWD/T)

(Sheet 2 of 5) 3/4.5-18 Figure 3.5-1 Planar Average Exposure (NWD/T)

(Sheet 3 of 5) 3/4.5-19 Figure 3.5-1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

(Sheet 4 of 5) 3/4.5-20 Figure 3.5-1 Planar Average Exposure (NWD/ST)

(Sheet 5 of 5) 3/4.5-21 Figure 3.5-2 Core Flow %

3/4.5-25 & 26 Figure 3.6.1 Minimum Temperature Requirements per Appendix G of 10 CFR 50 3/4.6-20 Figure 4.6.1 Minimum Reactor Pressurization Temperature B 3/4.6-25 Figure 4.6.2 Chloride Stress Corrosion Test Results at 500*F B 3/4.6-27 Figure 4.8-1 Owner Controlled / Unrestricted Area Boundary B 3/4.8-38 Figure 4.8-2 Detail of Central Complex B 3/4.8-39 Figure 6.1-1 Corporate and Station Organization 6

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viii 3958a 0009A

DRESDEN III DPR-25 Amendment N3. pf, 79 3.12 LIMITING CONDITIONS FOR OPERATION 4.12 SURVEILLANCE REQUIREMENTS (Cont'd.)

(Cont'd.)

b.

Restore the in-operable instru-ment (s) to operable status within 14 days, or prepare and submit a report to the Commission pursuant to Speci-l fication 6.6.B within the next 30 days outlining the cause of the mal-function, action taken and the plans for restoring the instrument (s) to operable status.

c.

The provisions of Specification 3.0.A. are not applicable.

B.

Fire Suppression Water System B.

Fire Suppression Water System 1.

The Fire Suppression 1.

The Fire Suppression Water System shall be Water System shall be operable at all times demonstrated operable:

with:

a.

A flow path a.

At least once per capable of taking 31 days by suction from the verifying valve 2/3 Intake Canal positions.

for Unit 2/3 Fire

Pump, b.

A flow path b.

At least once per capable of taking 12 months by suction from the cycling each Unit 1 Intake testable valve Canal for Unit 1 in the flow path fire pump.

through one complete cycle.

3/4.12-2 (wp3902a)

DRESDEN III DPR-23 AmendI:nt No. 76, yg j

3.12 LIMITING CONDITIONS FOR O?ERATION 4.12 SURVEILLANCE REQUIREMENTS (Cont'd.)

(Cont'd.)

report to the Commission pursuant to l

Specification 6.6.B within the next 30 days outlining the plans, l

action taken and procedures to be used to provide for the loss of redundancy in this system.

3.

With no Fire Suppression Wa.ter 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 6.6.B outlining the actions taken and the plans and schedule for restoring the system to operable status.

4.

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

C.

Sprinkler Systems C.

Sprinkler Systems 1.

The sprinkler systems 1.

At least once per 31 given in Table 3.12-2 days by verifying that shall be operable at each valve, manual, all times when power-operated, or equipment in the area automatic, in the flow 3/4.12-5 (wp3902a) 3

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DRESDEN III DPR-25 Amendment Ns. ps, 79 3.12 LIMITING CONDITIONS FOR OPERATION 4.12 SURVEILLANCE REOUIREMENTS (Cont'd.)

(Cont'd.)

that is sprinkler path is in its correct protected is required position.

to be operable.

2.

With a sprinkler

2. - At least once per 12 system inoperable, months by cycling each establish fire testable valve in the inspections with flow path through at backup fire supression least one cceplete equipment within I hour.

cycle of full travel.

a.

In the Unit 2/3 turbine mezzanine 538' elevation aren or' Unit 3 hydrogen seal oil area, a continuous fire watch is to be established.

b.

In all other areas given in Table 3.12-2 perform surveillance hourly.

3.

Restore the system to 3.

At least once per 2

operable status within operating cycle:

14 days, or prepare and submit a report to a.

A system functional the Commission pursuant test shall be to specification performed which l

'6.6.B within the includes simulated next 30 days outlining automatic actuation the cause of of the system and inoperability, action verifying that the taken and the plans automatic valves in for restoring the the flow path system to operable actuate to their status.

correct positions.

b.

The sprinkler headers shall be inspected to verify their integrity.

3/4.12-6 (wp3902a)

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DRESDEN III DPR-25 Amendment No. 74, 79 f

3.12 LIMITING CONDITIONS FOR OPERATION 4.12 SURVEILLANCE REQUIREMENTS (Cont'd.)

(Cont'd.)

unprotected areas within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and perform inspection at least hourly.

5.

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

Specification 6.6.B within the next 30 days outlining the cause of inoperability, action taken and the plans and schedule for restoring the system to operable status.

6.

The provisions of Specification 3.0.A.

are not applicable.

E.

Fire Hose Stations E.

Fire Hose Stations 1.

The Fire Hose 1.

At least once per 31 Stations given in days, a visual Table 3.12-4 shall inspection of each fire be operable at all hose station shall be times when the made to assure all equipment in the equipment is available area is required to at the statie.

be operable.

2.

With a hose station 2.

At least once per inoperable route an operating cycle, the additional equivalent hose will be removed capacity hose to the for inspection and unprotected area from repacked. Degraded an operable hose gaskets in the station within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

couplings will be replaced.

3.

When a hose station 3.

At least once per 3 becomes inoperable, years, each hose restore to operable station valve will be 3/4.12-8 4

(wp3902a)

DRESDEN III DPR-25 Amendment No. Jd, 79 3.12 LIMITING CONDITIONS FOR OPERATION 4.12 SURVEILLANCE REOUIREMENTS (Cont'd.)

(Cont'd.)

. status within 14 days partially opened to or report to the verify valve Commission pursuant operability and no to specification blockage.

l 6.6.B within the next 30 days outlining the cause of inopera-l bility, action taken and plans for restoring the hose station to operability.

4.

The provisions of 4.

At least once per 3 Specification 3.0.A years a hydrostatic are not applicable.

test will be conducted on each hose at a pressure at least 50 psig above line pressure at that station.

F.

Penetration Fire Barriers F.

Penetration Fire Barriers 1.

All penetration fire 1.

Each of the required barriers (including penetration fire fire doors and fire barriers shall be dampers) protecting verified to be intact safety related areas by a visual shall be intact, inspection:

except as stated in specification a.

At least once per 3.12.F.2 below.

18 months, and b.

Prior to declaring a penetration fire barrier intact following repairs or maintenance.

2. -With one or more of the required penetration fire barriers not in-tact, establish a con-tinuous fire watch on at least one side of the affected penetra-tion within I hour when 3/4.12-9 (wp3902a)

r DRESDEN III DPR-25 Amendment No. 7

79

/

3.12 LIMITING CONDITIONS FOR OPERATION 4.12 SURVEILLANCE REOUIREMENTS (Cont'd.)

'(Cont'd.)

the area on either side of the affected pene-tration contains equip-ment required to be operable.

3.

The provisions of Specification 3.0.A are not applicable.

4.

Restore the non-func-tional fire barrier penetrations to oper-able status within 7 days or prepare and submit a report to the Commission pursuant to l

Specification 6.6.B.

within the next 30 days outlining the cause of inoperability, action taken and the plans and schedule for restoring the penetration fire barriers to operable status.

G.

See 3.12.B.

G.

Fire Pump Diesel Engine 1.

The fire pump diesel engine shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying:

1) The fuel storage day tank contains at least 150 gallons of fuel, and 3/4.12-10 (wp3902a)

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DRESDEN III DPR-25 Amendment No. Jd, 79 6.0 ADMINISTRATIVE CONTROLS 6.1 Oraanization. Review. Investiaation 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 l

experience requirements for plant manager.

B.

The organization chart of the corporate management which relates tc the operation of this station and the normal functional organization chart for operation of the station are shown in Figure 6.1.1.

C.

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

The Operating Assistant Superintendent. Operating Engineer, Shift Engineers, and Shift Foreman shall have a Senior Operating License. The Fuel Handling Foreman has a limited Senior Operating License. The Division Vice President Nuclear Stations on the corporate level has responsibility for the Fire Protection Program. An Operating Engineer at the station will be responsible for implementation of the Fire Protection Program. 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 essential functions during a fire emergency.

D.

Qualifications of the station management and operating staff shall meet minimum acceptable levels as described in ANSI N18.1, " Selection and Training of Wuclear Power Plant Personnel " dated March 8, 1971, with the exception of the Radiological-Chemical Supervisor who shall meet or exceed the qualifications of Radiation Protection Manager of Regulatory Guide 1.8, September, 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for trans-lents and accidents. The individual filling the position of Administrative and Support Services Assistant Superintendent

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

E.

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

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DRESDEN II' DPR-25 Amendment No. 78, 79 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

A training program for the fire brigade shall be maintained under the direction of the Operating Engineer and shall meet or exceed the requirements of Section 27 of the NFPA Code -

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

F.

Retraining shall be conducted at intervals not exceeding two i

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 sad Investigative i

Function shall be appointed by the Vice President-Nuclear Operations. The Audit Function shall be the responsibi-lity of the Manager of Quality Assurance and shall be independent of operations.

a.

Offsite Review and Investiaative Function The Supervisor of the Offsite Review and Investigative Function shall:

(i) provide directions for the review and investigative function and appoint a senior participant to provide appropriate direction, (ii) select each participant for this function, (iii) select a complement of more than one participant who collectively possess background and qualifications in the subject matter under review to provide compre-hensive interdisciplinary review coverage under this function (iv) independently review and approve the findings and recommendations developed by personnel performing the review and investigative function, (v) approve and report in a timely manner all findings of noncompliance with NRC requirements and provide recommendations to the Station Superintendent.

Division Vice President-Nuclear Stations, Manager of 4

Quality Assurance, and the Vice President-Nuclear Operations". During periods when the Supervisce of the 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 cf the Offsite Review and Investigative Function.

6-2 l

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Corporate and Station Organisation 6-3 I

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DRESDEN III DPR-25 Am:ndmentNo.[,79 TABLE 6.1.1 MINIPUM SHIFT MANNING CHART (1) i CONDITION OF NUMBER OF EN IN EACH POSITION iMITS STA or NON-RAD WITH FUEL FIRST UNIT SECOND UNIT THIRD LMIT SR0(2)

R0(3) SCRE LIC.

EN Cold Shutdown Cold Shutdown Cold Shutdown 1

1 0

5 1

ONE Above Cold Shutdown Cold Shutdown Cold Shutdown 2

2 1

5 1

Cold Shutdown Cold Shutdown Cold Shutdown 1

2 0

5 1

TWO Above Cold Shutdown Cold Shutdown Cold Shutdown 2

3 1

5 I

Above Above Cold Shutdown Cold Shutdown Cold Shutdown 2

3 1

5 1

Cold Shutdown Cold Shutdown Cold Shutdown 1

3 0

5 1

THREE Above Cold Shutdown Cold Shutdown Cold Shutdown 2

4 1

5 1

Above Above Cold Shutdown Cold Shutdown Cold Shutdown 2

4 1

5 1

Above Above Above Cold Shutdown Cold Shutdown Cold Shutdown 2

4 1

5 1

SRO

- Senior Reactor Operator. At least one SRO must remain in the Control Room at all times when one or more units is above cold shutdown. This person may, however, leave the Control Rom for periods not to exceed 10 minutes, provided another SRO acts as relief operator. The SCRE or shift supervisor can fulfill this requirement.

RO

- Reactor Operator (For each reactor containing fuel, one RO will be in the Control Rom at all times.)

STA

- Shift Technical Advisor.

SCRE

- Station Control Room Engineer (STA with Senior Reactor Operator's License).

NON-LIC.

- Equipment Operators and Equipment Attendants.

RAD MEN

- Radiation Protection Men.

NOTES: (1) - Shift crew conposition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accamodate unexpected absence of on-duty shift crew menbers provided inmediate action is taken to restore the shift crew conposition to within the mininun requirements.

(2) - Does not include the itcensed Senior Reactor Operator or Senior Reactor Operator 11mited to fuel handling, supervising CDRE OPERATIONS.

(3) - Shall not operate units on which they are not Ilcensed.

A00!TIONAL REQUIREMENTS A.

SRO can be 90 at controls.

B.

SRO in Control Room cannot provide relief to SRO/R0 at controls.

C.

SRO in Control Roten nust be in sight of or audible range of operator at all times or be in audible range of annunciators.

6-4 0141W 0014n

DRESDEN III DPR-25 Amendment No. )$, 79 6.0

[?51NISTRATIVE CONTROLS (Cont'd.)

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 pro-cedures, equipment or systems as described in the safety analysis report and 2) tests or experi-ments completed under the provision of 10 CFR Section 50.59 to verify that such actions did not constitute unreviewed safety questions. Pro-posed 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 Section 50.59 10 CFR.

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

(4) Proposed changes in Technical Specifications or NRC operating licenses.

(5) Noncompliance with NRC requirements, or of inter-nel 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 requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification" to the Commission.

(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 changes.

6-5 l

t DRESDEN III DPR-25 Amendment No. pf, 79 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station Superintendent, Division Vice President-Nuclear Stations and l

Manager of Quality Assurance.

b.

Audit Function The Audit Function shall be the responsibility of the Manager of Quality Assurance independent of the Production Department. Such responsibility is delegated to the Director of Quality Assurance for Operating and to the 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 two years or less as designated below.

(1) Audit of the Conformance of facility operation to pros 1sions contained within the Technical Speci-fications 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 six 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 12 months.

l 6-6 0141W 0014n

?

DRESDEN III DPR-25 Amendment No. p,) f, 79 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(6) Audit of the Facility Security Plan and implementing procedures at least once per 12 e

months.

(7) Audit onsite and offsite reviews.

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

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

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

(11)- The PCP and implementing procedures for solidifi-cation of radioactive waste at least once per 24 months.

(12) Report all findings of noncompliance *fith NRC requirements and recommendations and results of each audit to the Station Superintendent, the Division Vice President-Nuclear Stations, Manager of Quality Assurance, the General Superintendent of Production Systems Analysis, and to the Vice l

President-Nuclear Operations.

I c.

Authority The Manager of Quality Assurance reports to the Chairman and President. The Supervisor of the Offsite Review and Investigative Function reports to the Manager of Nuclear Safety who reports to the Chairman and President. Rither the Manager of Quality Assurance or the Supervisor of the Offsite Review and Investigative Function has the authority to order unit shutdown or request any other action which he deems necestsey to avoid unsafe plant conditions.

d.

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

6-7 l

__~

DRESDEN III DJR-25 Amendment No. )$, K, 79

}

i 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(2) Copies of documentation, reports, and j

correspondence shall be kept on file at the station.

l e.

Procedures Written administrative procedures shall be prepared I

and maintained for the off-site reviews and

+

investigative functions described in Specifications 6.1.G.1.a.

These procedures shall cover the following:

(1)

Content and method of submission of presentations to the Supervisor of the Offsite Review and Investigative Function.

(2) Use of committees and consultants.

l (3) Review and approval.

(4) Detailed listing of items to be reviewed.

^

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

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

i 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 onb 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 6-8 0141W l

0014n

DRESDEN III DPR-25 Amends.ent No. J/s, 79 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(g) reactor safety analysis (h) instrumentation and control (i) 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 Technolony Engineering graduate or equivalent with 5 years experience in the nuclear power field design and/cr 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 Desian Engineering graduate or equivalent with at least 5 years of experience in power plant design and/or operation.

(e) Reactor Enaineerina Engineering graduate or equivalent.

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

(f) Radis19mical safetr Engineering graduate or equivalent with at least 5 years of experience in radiation control and safety.

6-9 0141W 0014n

DRESDEN III DPR-25 Amendment No. Jd, J1, 79 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

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

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

(i) Metallurav 4

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.

Onsite Review and Investiaative Function a.

The Station Superintendent shall:

(i) provide direction for the Review and Investigctive Function and appoint the Technical Staff Supervisor, or other comparably qualified individual as a senior participant to provide appropriate direction; (ii) approve participants for this function; (iii) 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 inter-disciplinary review coverage under this function; (iv) independcatly review and approve the findings and recommendations developed by personnel performing the Review and Investigative Function; (v) report all findings of noncompliance with NRC requiremants, and provide recommendations to the Divisica Vice Prssident-Nuclear Stations and the Supervisor of the Offsite Review and Investigative Function; and (vi) submit to the Offsite Review and Investigative Function for concurrence in a timely manner, those items described in Specification 6.1.C.1.a which have been approved by the Onsite Review and Investigative Function.

6-10 l

DRESDEN III DPR-25 Amendment No. ?$, 34, 79 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

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

(1) Review of:

1) procedures required by Specifica-tion 6.2 and changes thereto, 2) any other pro-posed 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 the Division Vice President-Nuclear Stations and to the Supervisor of the Offsite Review and Investigative Function.

(6) Review of facility operations to datect 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 the Station Security Plan and shall submit recommended changes to the Division Vice President-Nuclear Stations.

~

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

l (10) Review of reportable events and actions taken to l

prevent recurrence.

6-11 l

DRESDEN III DPR-25 Amendment No. 7j$. ??, 79 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

l (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 Offsite Review and Investigative Function.

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

b.

Authority The Technical Staff Supervisor is responsible to the Station Superintendent and shall make recommendations in a timely manner in all areas of review, investigation, and quality control phases of plant maintenance, operation and administrative procedures relating to facility cperations 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 recommenda-tions or select a course of action that is more conservative regarding safe operation of the facility. All such disagreements shall be reported immediately to the Division Vice President-Nuclear i

Stations and the Supervisor of the Offsite Review and i

Investigative Function.

c.

Records (1) Reports, reviews, investigations, and recommendations shall be documented with copies to the Division Vice President-Nuclear Stations.

l 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.

6-12 l

I

~ --

i DRESDEN 111 DPR-25 Amendment No. J6, 79 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

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 l

the Offsite Review and Investigative Function.

(2) Use of committees.

(3) Review and approval.

(4) Detailed listing of items to be reviewed.

(5) Procedures for administration of the quality 1

control activities.

1 (6) Assignment of responsibilities.

e.

Personnel (1) The personnel performing the Onsite Review and Investigative Function, in 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 safety and chemistry (e) instrumentation and control (f) mechanical and electric systems.

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

H.

1.

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

6-13 l

i DRESDEN III DPR-25 Amendment No. 16, 11, 7 9 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

2.

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

6.2 Plant Operating Procoduces 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.

Refuelinkoperations.

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 implementing procedures, 11.

Fire protection Program implementation.

12.

ODCM implementation.

13.

PCP implementation.

14.

Working hours of the Shift Engineer, Station Control Room Engineer, Shif t Foreman, Nuclear Station Operator job classifications such that the heavy use of overtime is not routinely required.

6-14 l

DRESDEN III DPR-25 Amendment No. }$, J7, 79 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

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.

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 sud the Technical Staff Supervisor in the areas of operation, fuel handling, or instrument maintenance, and by the Maintenance Assistant Superintendent and Technical Staff Supervisor in the areas

.s 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 R6diological Chemical Supervisor. At least one person approving each of the t

above procedures shall hold a valid senior operator's 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 procedure" utilized for safety related work shall be so approved only if procedures referenced in the

" Maintenance / Modification procedure" have been approved as required by 6.2.A.

Procedures which do not fall within the 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.

6-15 l

i DRESDEN III DPR-25 Amendment No. )6, ?7, 79 6.0 ADMINISTRATIVE CONTPOLS (Cont'd.)

E.

Drills 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.

6.3 Action to be Taken in the Event of a Reportable Event in Plant Operation Any reportable event shall be promptly reported to the Division l

Vice President-Nuclear Stations or his designated alternate.

The incident shall be promptly reviewed pursuant to Specification 6.1.G.2.a(5) and a separate report for each reportable event shall l

be prepared in accordance with the requirements of Specification 6.6.B.

6.4 Action to be Taken in the Event a Safety Limit is Exceeded If a safety limit is exceeded, the reactor shall be shut down immediately and reactor operation shall not be resumed until authorized by the NRC. The conditions of shutdown shall be promptly reported to the Division Vice President-Nuclear Stations or his designated alternate. The incident shall be reviewed pursuant to Specification 6.1.C.1.a and 6.1.C.2.a and a separate report for each event shall be prepared in accordance with Specification 6.6.B.

l' 6.5 Plant Operating Records A.

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

1.

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

2.

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

3.

Records and reports of reportable and safety limit events.

l 4.

Records and periodic checks, inspection and/or calibrations performed to verify the Surveillance Requirements (See Section 4 of these Specifications) are being met. All equipment failing to meet surveillance requirements and the corrective action taken shall be recorded.

6-16 I

DRESDEN III DPR-25 Amendment No. %, 79 i

6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

5.

Records of changes made tc

'e 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.

10.

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

B.

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

1.

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

2.

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

3.

Records of new and spent fuel inventory and assembly histories.

4.

(Deleted) 5.

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

6.

Records of plant radiation and contamination surveys.

7.

Records of off-site environmental monitoring surveys.

8.

Records of radiation exposure for all plant personnel, including all contractors and visitors to the plant in accordance with 10 CFR 20, 9.

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

10.

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.

11.

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

6-17 l

DRESDEN III DPR-25 Amendment No. }$, 79

?

1 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

12.

Inservice inspections of the reactor coolant system.

13.

Minutes of meetings and results of reviews performed by the off-site and on-site review functions.

i 14.

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

6.6 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10 Code of Federal Regulations, the following identified reports shall be submitted to the Regional Administrat'or of the appropriate Regional Office of the NRC 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 4

hydraulic performance of the plant. The report shall address each of the tests identified in the FSAR 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 commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., init~1al criticality, completion of startup test program, and resumption or comunencement of commercial power operation),

4 supplementary reports shall be submitted at least every three months until all three events have been completed.

6-18 l

e DRESDEN III DPR-25 Amendment No. Jf, J7, 79 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

i 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 arem/yr and their associated man rem exposure according to work and job functions, (See note); e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or' film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

3.

Monthly Operatina Report Routine reports of operating statistics ar.d shutdown experiences shall be sul.altted on a monthly basis to the Director, Office of Resource Management, US Nuclear l

Regulatory Commission, Washington, DC 20555, with a copy to the appropriate Regional Administrator, to arrive no l

later than the 15th of each month following the calendar month covered by the report.

B.

Reportable Events Reportable events will be submitted as required by 10CFR 50.73.

C.

Unique Reportina Recuirements 1.

Radioactive Effluent Release Report (Semi-Annual) i A 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.

Note: This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

6-19

_y,.

_y_.-

_y__

___,-.-.,-,,,.m._.

..,m__

.-.-,..m

.._,.,,w

DRESDEN III DPR-25 Amendment No. Jd, 77, 79 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

2.

Environmental Radioactivity Data (Annual Report)

Standard Radiological Monitoring program a.

(1) Non-Routine Report (a) 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 4.8-1 and if the radioactivity is attributable to plant operation, a written report shall be submitted to the Regional

, Administrator of the NRC Regional office, with a copy to the Director, Office of Nuclear Reactor Regulation, within 30 days from the i

end of the quarter. When more than one of the radionuclides in Table 4.8-1 are detected in the medium, the reporting level shall have been exceeded if IC /(RL){ is equal to or greater than 1 i

where C is the concentration of the ith radionuclide in the medium and RL is the reporting level of radionuclide i.

(b) If radionuclides other than those in Table 4.8-1 are detected and are due to plant effluents, a reporting level is exceeded if i

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

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

(2) Annual Operating Report An annual report containing the data taken in the standard radiological monitoring program (Table 4.8-1) shall be submitted by March 31 of the next year. The content of the report shall include:

}

I 6-20 I

j 0141W 0014n

i DRESDEN III DpR-25 Amendment No. ?$, 7d, 79 j

6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

(a) Results of environmental sampling summarized on a quarterly basis following 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

.s provided.

(b) An assessment of the monitoring results and radiation dose via the principal pathways of exposure resulting from 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 ODCM.

(c) Results of the census to determine the locations of animals producing milk for human consumption, and the pasture season feeding practices at dairies in the monitoring program.

(d) The reason for the omission if the nearest dairy to the station is not in the monitoring program.

(Table 4.8-5)

(e) An annual summary of meteorological conditions concurrent with the releases of gaseous effluents in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.

(f) The results of the interlaboratory comparison program described in section 3.8.E.7.

(g) The results of.he 40 CFR 190 uranium fuel cycle dose an.lfsis for each calendar year.

(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.

l 6-21

DRESDEN III DPR-25 4

Amendment No. 7$, 77, 79

/

6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

3.

Special Reports Special reports shall be submitted as indicated in Table 6.6.1.

i 6.7 Environmental Qualification A.

By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588 3

" Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment" December 1979. Copies of these documents are attached to order for Modification of License DPR-25 dated October 24, 1980.

B.

By no later than December 1, 1980, complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all 4

safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.

6.8 Offsite Dose Calculation Manual (ODCN)

A.

The ODCM shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCO's contained in these Technical Specifications. Methodologies and calculational procedures acceptable to the Commission are contained in NUREG-0133.

The ODCM shall be submitted to the Commission at the time of proposed Radiological Effluent Technical Specifications and shall be subject to review and approval by the Commission prior to implementation.

i l

6-22

DRESDEN III DPR-25 Amendment No. J 7f. 79 j

TABLE 6.6.1 SPECIAL REPORTS SPECIFICATION AREA REFERENCE SUBMITTAL DATE a.

Response time of safety related instruments (2) 1.0.E (Dres. 1)

Annual Report b.

Main steam isolation valve and feedwater power operated isolation valves closure times (2) 3.7.B.l.c (Dres. 1) Annual Report c.

Primary Coolant leakage to Drywell (4) 3.6.D Bases 5 years (1) d.

In-Service Inspection Evaluation (4) 3.6.F Bases 5 years (1) e.

Evaluation of Economic Generation 3.3.G Bases Upon completion of Control System (EGCS) operation (4) initial testing f.

Failed Fuel Detection (4) 3.2 Bases 5 years (1) g.

Main Steam Line Leakage to Steam Tunnel (4) 3.6.D Bases 5 years (1) h.

In-service Inspection Development (4) 3.6.F Bases 5 years (1) 1.

In-Service Inspection of Sensitized Stainless Steel Components (3) 4.6.F 4 years (1)

j. Secondary Containment Leak Rate Test (4) 3.7.C.1 within 90 days after completion of each test High off-gas discharge rate (2) 3.8.A.4 (Dresden 1) within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months k.

of oceptrence l.

Radioactive Source Leak Testing (5) 3.8.F Annual Report NOTES:

1.

The report shall be submitted within the period of time listed based on the commercial service date as the starting point.

2.

Dresden 1 only 3.

Dresden 2 only 4.

Dresden 2 and 3 only.

5.

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

6-23

w DRESDEN III DPR-25 Amendment No. pd, p1, 79 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

B.

Licensee initiated changes to the ODCM may be made provided the change:

1.

Shall be submitted to the Commission by inclusion in the Monthly Operating Report pursuant to Specification 6.6.A.3.

within 90 days of the date the change (s) was made effective and shall contain:

a.

Sufficiently detailed information to support the change. Information submitted should consist of a package of those pages of the ODCM to be changed together with appropriate analyses or evaluations justifying the change (s);

b.

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

Documentation of the fact that the change has been reviewed and found acceptable by the Onsite Review function.

2.

Shall become effective upon review and acceptance by the Onsite Review function.

6.9 Process Control Program (PCP)

A.

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

B.

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

C.

Licensee initiated changes may be made to the PCP provided the change:

1.

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

a.

Sufficiently detailed information to support the change; l

b.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and 6-24 l

w DRESDEN III DPR-25 Amendment No. Jd, 7/1, 79 5.0 ADMINISTRATIVE CONTROLS (Cont'd.)

Documentation that the change has been reviewed and found c.

acceptable by the Onsite Review Function.

l 2.

Shall become effective upon review and acceptance by the Onsite Review Function.

l 6.10 Major Changes to Radioactive Waste Treatment Systems (Liquid, Gaseous, Solid) (see note below)

Licensee initiated major changes to the radioactive waste systems A.

may be made provided:

1.

The change is reported in the Monthly Operating Report for the period in which the evaluation was reviewed by the Onsite l

Review Function. The discussion of each change shall contain:

A summary of the evaluation that led to the determination a.

that the change could be made in accordance with 10 CFR 50.59; b.

Sufficient detailed information to support the reason for the change; A detailed description of the equipment, components, and c.

process involved and the interfaces with other plant systems; d.

An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments; e.

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

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

Documentation of the fact that the change was reviewed and found acceptable by the Onsite Review Function.

l 2.

The change shall become effective upon review and acceptance by the Onsite Review Function.

l Note:

Licensee may choose to submit this information as part of the annual FSAR update.

0141W 0014n

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ML20112G216

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Attachment:

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