ML20205Q918

Amends 103 & 93 to Licenses DPR-39 & DPR-48,respectively, Modifying Tech Specs to Eliminate Requirements to Shut Down When Coolant Iodine Exceeds 1 Uci/G Dose Equivalent I-131 for 800 H in 12-month Period

ML20205Q918
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	03/26/1987
From:	Varga S Office of Nuclear Reactor Regulation
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ML20205Q881	List: ML20205Q877 ML20205Q918 ML20205Q956
References
NUDOCS 8704060124
Download: ML20205Q918 (27)

Text

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• ,,a bs A ,\ UNITED STATES

[T ,p, NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20S55 5 j

%,e..../

COWONWEALTH EDISON COMPANY l

DOCKET N0. 50-295 1 7 ION NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.103 License No. DPR-39

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

A. The application for amendment by Comonwealth Edison Company (the licensee) dated October 15, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission'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 2.C.(2) of Facility Operating License No. DPR-39 is hereby amended to read as follows:

8704060124 870326 fDR ADOCK 05000295 PDR 1

a (2) Technical Scecificatinns The Technical Specifications contained in Appendices A and R, as revised through Amendment No.103, are hereby incorporated in the license. The licensee shall operate the fecility in accordance with the Technical-Specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION yf C.Mu I&u teven A. Varga, 0 rector h'PWPPro.iectDirectorate#3

()

Division of PWR Licensing-A, NRR

Attachment:

Changes to the Technical Specifications Date of Issuance: March 26, 1987

. .p ua, 8 UNITED STATES

[ ', ( '[ gg NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 E .j N

%s.....J COMMONWEALTH EDIS0t! COMPANY DOCKET NO. 50-304 ZION NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 f.icense No. DPR-48

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

A. The application for amendment by Commonwealth Edison Company (the licensee) dated October 15, 1986, 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 Conmission'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; 7

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 2.C.(2) of Facility Operating License No. DPR-48 is hereby amended to read as follows:

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(?) Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No. 93 , 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 s f9 hk 2 ytev'nA.Varaa,Di ctor 4

PWR Project Directorate #3 -

Division of PWR Licensing-A, NRR

Attachment:

Changes to the Technical

., Specifications Date of Issuance: March 26, 1987 4

4 1

l O UNITED STATES

'g y/ g NUCLEAR REGULATORY COMMISSION

' , 5 , g( j

. j WASHINGTON, D. C. 20555 4,o$

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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.103 FACILITY OPERATING LICENSE H0. DPR-39 AMENDMENT NO. 93 FACILITY OPERATING LICENSE NO. DPR-48 DOCKET NOS. 50-P95 AND 50-304 Revise Appendix A as follows:

Remove Pages Insert Paces xi xi 123 123 124 124 124a 124a 125 125 295 AA7 295 AA7 300 300 301 301 302 302 303 303 305 305 306 306 307 307 j

308 308 309 309 310 310 311 311 314 314 316 316 317 317 323 323 324 324

t I

Table . Pigg 4.17-1 Charcoal Filters 2 94 i 4.17-2 NEPA Filters 285 i

j 4.19-1 Failed Fuel Monitoring Instruments 235 I

! 4.21-1 Fire Protection Instruments * '

295p 4.21-2 Fire Suppression Water System 295r l 4.21-3 Sprinkler Systems 295s 4.21-4 CO2 Systems 295t

) 4.21-5 Fire Nose Stations ...-

295u

.. g l 6. 6-1 Special Reports 323 l 6.8-1 Boundary Doors for Flooding Protection 328 4

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List of Tables (Continued) ,

x1 Amendment Nos. 103, 93 TSC 84-03(4) 13140/10150

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. s LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS i REACTOR COOLANT SYSTEM 3.3.6 SPECIFIC ACTIVITY 4.3.6 The specific activity of the reactor coolant y shall be sampled and analyzed in accordance i The specific activity of the reactor coolant with Table 4.3.6-1.

l shall be limited to:

a. Less than or equal to 1.0 microcurie per 3

gram DOSE EQUIVALENT 1-131, and

b. Less than or equal to 100/E microcuries per gram. .

APPLICABILITY: Modes 1, 2, 3, 4, 5 and 7, 1 ACTION: Modes 1, 2, 3* and 7*:

a. With the specific activity of the reactor coolant greater than 1.0 microcurie per gram DOSE EQUIVALENT l-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line shown on Figure 3.3.6-1, be in at least NOT SHUT 00WN with Tavg less than 500*F within six hours.

b. With the specific activity of the reactor coolant greater than 100/E micropuries per ,

gram, be in at least NOT SHUTDOWN with '

Tavg less than 500*F.within six hours.

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• With Tavg greater than or equal to 500*F.

18120/10130 123 Amendment Nos. 103, 93

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.1 LINITING CONDITION FOR OPERAT10N SURVEILLANCE REQUIREMENTS i 1

ACTION: 4.3.6 Modes 1, 2, 3, 4, 5 and 7:  ?

a. With the specific activity of the reactor coolant greater than 1.0 microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microcuries per gram, perform the sampling and analysis requirements of item 44) of Table 4.3.6-1 untti the specific activity of the primary coolant is restored to within its limits.

b. A SPECIAL REPORT shall be prepared and submitted to the Commission as part of the Annual Report when Specification 3.3.6 has -

been exceeded. This report shall include

- the following information:

1. Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded;

2. Results of the last isotopic analysis for radiolodine performed prior to exceeding the limit, results of analysis while the limit was exceeded, and the ,

results of one analysis after the radioiedine activity was reduced to less than the limit. Each result should include date and time of sampling and the radiolodine concentrations;

3. Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

• prior to the first sample in which the limit was exceeded; 10120/10130 124

i l LIM 111NG CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS i 3.3.6 4. Graph of the 1-131 concentration and one 4.3.6

other radiolodine isotope concentration, l in microcuries per gram, as a function of time for the duration of the specific activity above the steady-state level; j 5. The time' duration when the specific

activity of the primary coolant exceeded 4

the radiciodine limit.

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10120/10130 124a Anendment Nos.103, 93 1

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j Beses: SPECIFIC ACTIVITY i

l 3.3.6 The limitations on the specific activity of the

] & primary coolant ensure that.the resulting 2-hour j 4.3.6 doses at the site boundary will not exceed an

! appropriately small fraction of 10CFR100 limits following a steam generator tube rupture

] accident in conjunction with an assumed steady

' state primary-to-secondary steam generator -

! leakage rate of 1.0 GPM. The values for the limits on specific activity represent limits

based upon a parametric evaluation by the NRC of i typical site locations. These values are conservative to that specific site parameters of the Zion site, such as site boundary location and meteorological conditions, were not 1 considered in this evaluation.

to less than 500*F prevents the ReducingTaltivityshouldasteamgenerator release of a i tube rupture since the saturation pressure of l

the primary coolant is below the lift pressure of the atmospheric steam relief valves. The

}

surveillance requirements provide adequate j ' assurance that excessive specific activity

levels in the primary coolant will be detected

in sufficient time to take corrective action.

Information obtained on todine spiking will be i used to assess the parameters associated with j spiking phenomena.

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Amendment Nos. 103, 93 j 10120/10130 125

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I LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMr.NT 4022. Shock Suppressors (Continued) 4.22. Shock Suppressors (Continued)

3. Snubber Service Life Monitoring 3. Snubber Service Life Monitorine ,,,

! A record of the service -life ofEddh' mechanical and hydraulic stiiubbe'6 t'he date at

! which designated service life commences and the installation and maintenance" records' on which the designated service life is based shall be maintained as required by Specification 6.5.2.0.

Concurrent with the first inservice visual inspection and at least once per 18 months

thereaf ter, the ins..llation and maintenance j-records for each snubber shall be. reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to

the next scheduled snubber service life

review. If the indicated service life will be i exceeded prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be

replaced or reconditioned so as to extend its service life beyond the date of the next

! scheduled service life review. This .

reevaluation, replacement or reconditioning shall be indicated in the records.

Amendment Nos. 103, 93 10140/10150 295AA7 TSC 84-03(4) i .. .

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6.0 ADNINISTRATIVE CONTROLS 4. Qualifications of the Station management and operating staff shall meet minimum 6.1. Organization, Review Investigation, and Audit acceptable levels as described in ANSI N18.1

" Selection and Training of Nuclear Power

1. The Station Manager shall have overall Plant Personnel," dated March 8,1g71 with full-time responsibility for safe operations the exception of the Radiation-Chemistry l of the facility. During periods when the Supervisor or Lead Health Physicist, who '

l Station Manager is unavailable, he shall shall meet or exceed the qualifications of l designate this responsibility to an Radiation Protection Manager of Regulatory

established alternate who satisfies the ANSI Guide 1.8 September,1g75. The Shift i

N18.1 experience requirements for plant Control Room Engineer shall have c manager. bachelor's degree or equivalent 16 a scientific or engineering discip'd.e with ,

2. The organization chart of the corporate specific training in plant Jestt... i.nd j management which relates to the operation of response and analysis of the plant for i

this station and the noriani functional transients, and accidents. The udividuci organization chart for operation of the filling the position of Services i

station is shown in Figures 1-6 of the Superintendent shall meet the minimum j Commonwealth Edison Quality Assurance Manual. acceptable level for " Technical Manager" as

{ described in 4.2.4 of ANSI N18.1, 1g71.

j 3. The shift manning for the station shall be as { .

shown in Figure 6.1-1. The Assistant 5. Retraining and replacement training of i Superintendent Operating, Operating Engineer, Station personnel shall be in accordance l Shift Engineers, and Shift Foreann shall have with ANSI N18.1, " Selection and Training of l a Senior Reactor Operators License. The Fuel Nuclear Power Plant Personnel," dated March Mandling Foreman shall have a Senior Reactor 8, 1g71. A training program for the Fire Operator or Limited Senior Reactor Operators Brigade shall be maintained under the License. The Assistant Vice President and direction of the Station Fire Marshall and General Manager Nuclear Stations on the shall meet or exceed the requirements of

! corporate level has responsibility for the Section 27 of the NFPA Code - 1g75 except j Fire Protection Program. An Operating that Fire Brigade training will be conducted j Engineer at the station will be responsible quarterly.

, for implementation of the Fire Protection Program. A Fire Brigrade of at least 5 6. Retraining shall be conducted at intervals members shall be maintained onsite at all not exceeding two years.

times. The Fire trigade shall not include the minimum shift crew necessary for safe shutdowa 1. The Review and Investigative function and of the plant (4 members) or any personnel the Audit Function of activities affecting {

required for other essential functions during quality during facility operations shall be >

a fire emergency. constituted and'have the responsibilities j -

and authorities outlined below.

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10140/10150 300 TSC 84-03(4)

I hendment hs. M3, %

6.1.7. (Continued)

Offsite Review and Investinative Function this responsibility to an established alternate who satisfies the formal training A. The Supervisor of the Offsite Review and and experience requirements for the Investigative Function shall be appointed by Supervisor of the Offsite Review and i the Manager of Nuclear Safety. The Audit Investigative Function. ,

l Function shall be the responsibility of the ,

i Manager of Quality Assurance and shall be The responsibilities of the personnel '

! independent of operations, performing this function are stated below.

) The Offsite Review and Investigative i

1. The Supervisor of the offsite Review and Function shall review:

Investigative Function shall: (1) provide directions for the review and (a) The safety evaluations for changes to

, investigative function and appoint a procedures, equipment or systems as 1

senior participant to provide appropriate described in the safety analysis report '

direction (2) select each participant and for tests or experiments completed for this function (3) select a under the provision of 10 CFR Section complement of more than one participant 50.5g to verify that such actions did

('

who collectively possess background and not constitute an unreviewed safety gealifications in the subject matter guestion. Proposed changes to the i under review to provide comprehensive Quality Assurance Program description interdisciplinary review coverage under shall be reviewed and approved by the this function. (4) independently review Manager of Quality Assurance.

j and approve the findings and recommendations developed by personnel (b) Proposed changes to procedures, performing the review and investigative equipment or systems which involve an l function. (5) approve and report in a unreviewed safety guestion as defined '

3 timely menner all findings of in 10CFR Section 50.5g.

! noncampliance with NRC requirements and

! provide recommendations to the Station (c) Proposed tests or experiments which l Manager Assistant Vice-President and involve an unreviewed , safety guestion i General Manager Nuclear Stations, Manager as defined in 10CFR Section 50.5g.

of Quality Assurance, and the Executive -

l Vice-President of Construction. (d) Proposed changes in Technical i Production. Engineering, Licensing and Specifications or NRC facility

} Environmental Affairs. During periods operating licenses.

l when the Supervisor of the Offsite Review j and Investigative Function is (e) Noncompliance with NRC requirements, or

. unavailable, he shall designate of internal procedures or instructions

j. having nuclear safety significance.

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I 10140/10150 301 TSC 84-03(4)

Amendment Nos. 103, 93

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! 601.1.A.1 (Continued)

(f) Significant operating abnorms11 ties or i deviations from normal and expected The Audit Function shall be the performance of plant equipment that responsibility of the Manager of Quality l affect nuclear safety as referred to it Assurance independent of the Production '

! by the Onsite Review and Investigative Department. Such responsibility is i Function. delegated to the Operations Quality Assurance Manager, to the Director of l (g) Reportable Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Quality Assurance operations and to the notification to the Commission. Director of Quality Assurance Maintenance. ,

i (h) All recognized indications of an Either of the above, or designated Corporate unanticipated deficiency in some aspect Staff or Supervision approved by.the Manager

, of design or operation of safety of Quality Assurance, shall approve the i related structures, systems or auditagendaandchecklists,the' Adinq ,

! camponents. and the report of each audit. ,tishall I be performed in accordance with the company - t (1) Review and report findings and Quality Assurance Program and Proc'edures.

j recommendations regarding all changes Audits shall be performed to assure that

. to the Generating Stations Emergency safety-related functions are covered within i Plan prior to taplementation of such a period of two years or as designated below

change.

(a) Audit of the conformance of facility (j) Review and report findings and operation to provisions contained recommendations regarding all items

• within the Technical specifications and referred by the Technical Staff applicable license conditions at least 3

Supervisor, Station Manager, Assistant once per year.

j Vice President and General Manager - '

j' Nuclear Stations and Manager of Quality (b) Audit of the adherence to precedures, i Assurance. training and qualification of the  !

station staff at least once Mr year.  ;

(k) Changes to Offsite Bose Calculation

, Manus 1 (00CM). (c) Audit of the results of actions taken

to correct deficiencies occurring in

! (1) Changes to the PROCESS CONTR0t. PROGRAM. facility equipment, structures, systems

) or methods of operation that affect j nuclear safety at least once per six

months.

) .

{ Amendment Nos. 103, 93

! 10140/10150 302 TSC 04-03(4) l l . .

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i 6.1.7.A.2 (Continued) (a) Report all findings of noncompliance l with NRC requirements and '

, (d) Audit of the performance of activities recommendations and results of each j required by the Quality Assurance audit to the Station Manager, the '

j Program to meet the Criteria of 10 CFR Assistant Vice-President and General l l 50 Appendix "B".. Manager Nuclear Stations, Manager of 1 Quality Assurance, Vice-Pr'esident i (e) Audit of the Generating Stations (Nuclear Operations), and Manager of  ;

j Emergency Plan and Implementing Nuclear Safety. '

4 Procedures.

] (n) Audit the Offsite Dose Calculation

! (f) Audit of the Facility Security Plan and Manual at least once per 24 months.

1eplementing procedures, j 6.1.7.A.3. Authority' 1 (g) Audit Onsite and Offsite Reviews.

l The Manager of Quality Assurance  !'

l (h)- Audit the Radiological Environmental reports to the Chairman and President j Monitoring Program at least once per 12 and the Supervisor of the Offsite i months. Review and Investigative Function reports to the Manager of Duclear

, (1) Audit the Facility Fire Protection Safety who reports to the Chairman and i Program and taplementing procedures at President. Either the Manager of.

least once per 24 months. Quality Assurance or the harvisce of ,

the Offsite Review and Investigative  ;

i (j) An independent fire protection and less Function has the authority :s order I prevention program inspection and audit unit shutdown or request any other j shall be performed at least once per 12 action which he deems necessary to 4

months utilizing either qualified avoid unsafe plant conditions.

offsite licensed personnel or an

outside fire protection fire. 4. Records l

(k) An inspection and audit of the fire , (a) Reviews, audits and recommeadations protection and loss prevention program shall be documented and distributed as i shall be performed by a quellfied covered in 6.1.7.A.1 and 6.1.7.A.2 l

I outside fire consultant at least once -

per 36 months. (b) Copies of documentation, reports, and  ;

correspondence shall be.kept on file at (1) The PROCESS CONTROL PROGRAM and the station.

i implementing procedures at least once per 24 months.

Amendment Nos. 103, 93 i

10140/10150 303 TSC 84-03(4)

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J 6.1.7.A.6 (Continued) l 6.1.7.A.6.(b) (Continued) l (c) The Supervisor of the Offsite Review and (4) Power Plant Desien Investigative Function shall have i

experience and training which satisfy I Engineering graduate or equivalent with at ANSI N18.1 - 1971 requirements for plant least 5 years of experience in power plant managers. i design and/or operation.

l (5) Reactor Eneineerine I Engineering graduate or equivalent with at 1. The Onsite Review and Investigative Function i least 5 years of experience in nuclear plant shall be supervised by the Station Manager. ,

i engineering, operation, and/or graduate work '

l in nuclear engineering or equivalent in The Station Manager or his designee, shall:

l reactor physics. l

• (a) Provide direction for the Onsite Review l and Investigative Function and appoint the

]

(6) Radiological Safety Technical Staff Supervisor, or other l comparably qualified individual as a senior

) Engineering graduate or equivalent with at participant to provide appropriate l 1 east 5 years of emperience in Radiation direction; (b) Approve participants for this

Centrol and Safety function; (c) Assure that a complement of

more than one participant who collectively i (7) Safety Analysis -

possess background and qualifications in the

[ subject matter under review are selected to i

Engineering graduate or equivalent with at provide comprehensive interdisciplinary least 5 years emperience in nuclear review coverage under this function; (d)

) engineering. Independently review and approve the l findings and recommendetiens developed by i (e) Instremontation and Centrol personnel perfonsing the Review and

Investigative Function; (e) Report all 1

Enginee' ring graduate er equivalent with at findings of noncompliance with NRC i- least 5 years of experience in instrumentation requirements, and provide recommendations to

and control design and/or operation. the Assistant Vice-President and General l . Manager-Nuclear Stations and the Supervisor

] (9) Metallurgy of the Gifsite Review and Investigative

! Function; and (f) submit to the Offsite

! Engineering graduate or equivalent with at Review and Investigative Function for least 5 years of experience in the

! concurrence in a timely manner, those items metallurgical field. described in Specification 6.1.7.A.1 which 1

1 have been approved by the Onsite Review and

. Investigative Function.

Amendment Nos. 103, 93

- 10140/10150 305 TSC 84-03(4)

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I 6.1.7.B- (Continued) (h) Review of the Station Security Plan and shall l submit receamended changes to the Assistant l Vice-President and General Manager-Nuclear

2. The responsibilities of the personnel performing Stations.

l this function are stated below:

! (1) Review of the Emergency Plan and station I (a) Review of precedures required by Specification Implementing Procedures and shall submit i 6.2 an1 changes thereto, and any other recommended changes to the Assistant presosed procedures or changes thereto as Vice-President and General Manager-Nuclear i determined by the Station Manager to affact Stations.

i nuclear safety.

(j) Review of Reportable Events and actions taken (b) Review of all proposed tests and experiments to prevent recurrence.

that affect nuclear safety.

(k) Review of changes to the Offsite Dose (c) Review of all proposed changes to the Calculation Manual (00CM).

i ' Technical Specificattens.

(1) Review of changes to the PROCESS CONTROL i (d) Review of all proposed changes or PROGRAM (PCP).

{ modifications to plant systems or equipment ,

that affect nuclear safety.

l (e) Investigation of all violattens of NRC 2 requirements and shall prepare and forward a report covering evaluation and receanendations to prevent recurrence to the Assistant Vice 1 President and General Manager-Nuclear Stations and to the Superviser of the Offsite Review and Investigative Function. ,

(f) Review of facility operattens to detect potential safety hazards.

l

! (g) Performance of special reviews and

) investigattens and reports thereen as I requested by the Superviser of the Offsite

! Review and Investigative Function.

1 Amendment Nos. 103, 93 10140/10150 306 TSC 84-03(4)

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1 6.1.'1.B (Continued) (a') Content and method of suteission and

) presentation to the Station Manager, j 3. Authority Assistant Vice President and Generai t

Manager-Nuclear Stations and the The Assistant Superintendent - Technical Services Supervisor of the Offsite Review and

'! is responsible to the Station Manager and shall Investigative Function. t make reconumendations in a timely manner in all areas of review, investigation, and quality control (b) Use of committees.

phases of plant maintenance, operation and administrative procedures relating to facility (c) Review and approval.  :

operations and shall have the authority to request i

{ the action necessary to ensure compliance with (d) Detailed listing of items to be reviewed.  ;

i rules, regulations, and procedures when in his i

i opinion such action is necessary. The Station (e) Procedures for administration of the l i Manager shall follow such recommendations or select quality control activities. ,

j a course of action that is more conservative

regarding safe operation of the facility. All such (f) Assignment of responsibilities.

i disagreements shall be reported tamediately to the Assistant Vice-President and General 6. Personnel Manager-Nuclear Stations'and the Supervisor of the Offsite Review and Investigative Function. *

(a) The personnel perfoming the Onsite Review and ,

Investigative Function, in addition to the '

4. Records Station Manager or his designee, shall consist of persons having expertise in:

, (a) Reports, reviews, investigations, and (1) Nuclear power plant technology

! recommendations shall be documented with (2) Reactor operations I copies to the Assistant Vice President and (3) Reactor engineering

} General Manager-Neclear Stations, the (4) Radiological safety i Supervisor of the Offsite Review and (5) Instrumentation and control j Investigative Function, the Station Manager (6) Chemistry and Radiochemistry

{ and the Manager of quality Assurance. (7) Mechanical and electric systems. i j (8) Metallurgy (b) Copies of all records and documentation shall l

l i be kept en file at the station. (b) Personnel performing the Onsite Review and

! Investigative Function shall meet minimum '

t

5. Procedures acceptable levels as described in ANSI N18.1 Written administrative procedures shall be prepared l and maintained for conduct of the Onsite Review and

) Investigative Function. These procedures shall l

. include the following:

1-Amendment Nos. 103, 93

! 10140/10150 307 TSC 84-03(4)

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• Station Security Plan cnd implementing 6.2. Plant Operatine Procedures procedures.

i Written procedures including applicable K. Fire Protection Program implementation.

1.

checkoff lists covering items listed below shall be prepared, implemented, and maintained: L. Post Accident Sampling Program A. Normal startup, operation, and shutdown M. Working hours of the Shift Engineer, g of the reactor and other systems and Shift Control Room Engineer, Shift i

I components involving nuclear safety of Foreman, and Nuclear Station Operator the facility. such that the heavy use of overtime is

} not routinely required.

j I B. Refueling operations.

2. Radiation control procedures shall be 1

l C. Actions to be taken to correct specific prepared, implemented and maintained. These and foreseen potential malfunctions of procedures shall specify permissible radiation 1 exposure limits and shall be consistent with  !

I systems or components including responses to alarms, suspected primary the requirements of 10 CFR 20. The radiation system leaks, and abnormal reactivity protection program shall meet the requirements j

changes. of 10 CFR 20.

0. Emergency conditions involving 3. Procedures for items identified in i Specification 6.2.1 and any changes to such potential or actual release of l

radioactivity " Generating Stations procedures shall be reviewed and approved by l

! Emergency Plan" and station emergency the Operating Engineer and the Technical Staff and abnormal procedures. Supervisor in the areas of operation and fuel

{ handling, and by the Assistant Superintendent i

! E. Instrumentation operation which could Maintenance and Technical Staff Supervisor in have an offact on the safety of the the areas of plant maintenance, instrument l

facility. maintenance, and plant inspection. Procedures j for items identified in Specification 6.2.2 F. Preventive and corrective maintenance and any changes to such procedures shall be l

I operations which could have an offact reviewed and approved by the Technical Staff i on the safety of the facility. Supervisor and the Radiation Protection Manager (RPM). At least one person approving i

G. Surveillance and testing requirements. each of the above procedures shall hold a i l valid Senior Reactor operator's license. In l

'l addition, these procedures and changes thereto 1 H. Tests and experiments.

l must have the authorization of the Station

1. Procedures to ensure safe shutdown of Manager or cognizant Superintendent before the plant. being implemented.

Amendment Nos. 103, 93 308 TSC 84-03(4) l l . ,10140/10150 1

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6.2.3. (Continued) i I Work and instruction type procedures which implement approved maintenance or modification procedures shall

{ be approved and authorized by the Production Superintendent. The " Maintenance / Modification Procedure" utilized for safety related work shall be so

) approved only if procedures referenced in the 1 " Maintenance /Redification Procedure" have been approved

as required by 6.2.1. Procedures which do not fall 1 within the requirements of 6.2.1 or 6.2.2 may be j approved by the Department Heads.

l 4. Temporary changes to procedures identified in Specifications 6.2.1 and 6.2.2 above may be made provided:

) .

l A. The intent of the original procedure is not altered. 4

5. 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.

j C. The change is documented, reviewed by the Onsite i

Review and Investigative function and approved by the 1 Station Manager or cognizant Superintendent within 14 l days of tapiteentatten.

I

5. Brills of the emergency procedures described in i specification 6.2.1.5 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 i year, commuunicatten links are tested and outside agencies

. are contacted.

l i

Amendment Nos. 103, 93

. 10140/10150 309 TSC 84-03(4)'

\ .. ..

8. Record of principal maintenance activities, 6.3 Action to be Taken in the Event of a Reportable including inspection, repair and replacements, Event in Plant Doeration: regarding principal items of equipment pertaining to nuclear safety. i Any Reportable Event shall be promptly reported to the Assistant Vice President and General C. Records and reports of Reportable Events and l Manager-Nuclear Stations or his designated Safety Limit occurrences, alternate. The incident shall be promptly reviewed pursuant to Specification 6.1.7.B.1.(e) and a O Records and periodic checks, inspection and/or separate report for each reportable event shall be calibrations perfonned to verify the prepared in accordance with the requirements of Surveillance Requirements (Section 4 of these l 10 CFR Part 50.73. Specifications) are being met. All equipment failing to meet surveillance requirements and l 6.4 Action to be Taken in the Event a safety Limit is the corrective action taken shall be recorded.

Exceeded:

E. Records of changes made to procedures required If a safety limit is exceeded, the reactor shall be by Specifications 6.2.1 and 6.2.2.

tripped tamediately and reactor operation shall not be resumed until authorized by the NRC. The F. Records of radioactive shipments.

conditions of shutdown shall be promptly reported l to the Assistant Vice President and General G. Records of physics tests and other tests Manager-Nuclear Stations or his designated pertaining to nuclear safety.

alternate. The incident shall be reviewed pursuant to Specification 6.1.7.A.1 and 6.1.7.5.1 and a H. Records of sealed source and fission detector separate report for each occurrence shall be leak tests and results.

l prepared in accordance with of 10 CFR Part 50.36.

I. Shift Engineers Logs.

6.5 Plant Oseratine Records J. By-product material inventory records.

1. Records relative to the following items shall be retained for at least five wears:

A. Records of norgs1 plant operation, including power levels and periods of operation at each power level. - >

Amendment Nos. 103, 93 10140/10150 310 TSC 84-03(4)

6.5..(Continued) 1. Records of transient or operational cycling for those components that have been designed to operate safely for a limited number of *

2. Records relative to the following items shall transient or operational cycles.

be retained for the duration of the Operatine .o -

License. J. Records of training and qualificdtion'for

current members of the station staff.

j A. Substitution or replacement of principal j items of equipment pertaining to nuclear K. Inservice inspections and testing perfonned l j

safety. pursuant to the Technical Specifications.

l S. Records and drawing changes reflecting L. Minutes of meetings and results of reviews i plant design modifications made to performed by the Offsite and Onsite Review i systems and equipment described in the Functions. ,

i Safety Analysis Report.

M Records of secondary water sampling and water C. Records of new and irradiated fuel quality.

Inventory, fuel transfers and assembly burnup histories. N. Records for environmental qualification of  !

components required by the. Environmental ,

S. Updated, corrected, and as-built drawings Qualification (EQ) program.

of the plant.

i 0. Records of the service lives of all snubbers ,

j E. Records of plant radiation and covered by Specification 3.22 including the i contaminatten surveys. date at which the service life commences and

associated installation and maintenance I F. Records of offsite environmental records.

l monitoring surveys.

1

p. Records of reviews performed for changes made j s. Records of radiation exposure for all to procedures or equipment or reviews of tests i plant personnel, including all and experiments pursuant to 10 CFR 50.5g.

!- centracters and visitors to the plant in j accordance with 10 CFR 20. Q. Records of Quality Assurance activities i

required by the Q.A. Manual.

H. Records of radioactivity in liquid and -

, gaseous westes released to the R. Records of reactor tests and experiments, j environment.

i I

Amendment Nos. 103, 93 10140/10150 311 TSC 84-03(4)

j. .. ..

6.6.1.C (Continued)

This report shall also include an assessment D. Eg_miannual Radioactive Release Report:

of radiation doses to the likely most exposed real individual from reactor Within 60 days after January 1 and July 1 of releases and other nearby uranium fuel cycle each year a report shall be submitted sources (including doses from primary covering the radioactive conter.t of effluents effluent pathways and direct radiation) for released to unrestricted area; during the the previous 12 consecutive months to show previous six months operation. The data conformance with 40 CFR 190, Environmental shall be in the format of Reguistory Guide Radiation Protection Standards for Nuclear 1.21. Rev.1 (June 1974) and si,all be Power Operation. Acceptable methods for summarized on a quarterly basis and shall calculating the dose contribution from include as a minimum:

11guld and gaseous offluents are given in

• Regulatory Guide 1.109 Rev.1. .- Geseces Effluents (a) Gross Radioactivity Releases (9) 'This report shall also include a special report pursuant to the requirements of ,

(1) Total gross radioactivity (in Specification 3.3.6 whenever the reactor curies) primarily noble and coolant specific activity limits have been activation gases released.

(2) Maximum gross radioactivity release rate during any one-hour period.

(3) Total gross radioactivity (in curies) by nuclide released, l

based on representative isotopic analyses perferised.

(4) Percent of technical specificatten limit.

(b) Iodine Releases (1) Total iodine radioactivity (in curies) by nuclide released, based on representative isotopic analyses performed.

. (2) Percent of technical

- specification limit for 1-131 l released.

10140/10150 314 TSC 84-03 4 Amendment No(s.) 103, 93

I l

. 1 6.6.1.0. (Continued)

5. The radioactive effluent release reports shall include any changes to

- the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

4 E. Monthlv Operatine Report Routine reports ,

using the " Operating Data", " Unit Shutdowns and Load Reductions" and " Average Daily Unit Power Level" report fonants, shall be submitted on a monthly basis to the l Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory comunission, Washington, D.C. 20555 with a copy to the appropriate NRC Regional Office -

of Inspection and Enforcement, no later than t the 15th of each month following the calendar month covered by the report.

Included with the report will be a

" Narrative Susumary of Operating Experience"

• that describes the operation of the facility, including major safety related maintenance, for the monthly report period. ,

Any changes to the Offsite Sose Calculation i Manual shall be submitted with the monthly Operating Report within 90 days of the offective date of the change.

i 1

Amendment Nos. 103, 93 I

10140/10150 316 TSC 84-03(4)-

6.6.E. Reportable Events 6.6.2.A.2 Non-Entreency Reports:

A. Immediate Notification:

1. Emergency Reports: a. One-Hour Reports - If not reported as a declaration of an Emergency

a. The licensee shall notify the NRC Class under paragraph 6.6.2.A.1 of Operations Center via the Emergency this section, the licensee shall Notification System (ENS) of: notify the NRC as soon as

1) The declaration of any of the practical and in all cases within

. Emergency Classes specified in one hour of the occurrence of any the Generating Station of the following.

i Emergency Plan (ESEP).  :

2) Those Non-Emergency events 1) The initiation of any nuclear specified in paragraph plant shutdown required by 6.6.2.A.2 below. . the plant's Technical Specifications.

b. If the Emergency Notification System -

is inoperative, the required 2) Any deviation from the notifications shall be made via plant's Technical commercial telephone service, other specifications authorized dedicated telephone system, or any pursuant to 10CFR50.54(x).

other method which will ensure that a report is unde as soon as '

3) Any event or condition during practical to the NRC Operations operation that results in the Center. condition of the nuclear powerplant, including its

c. The licensee shall notify the NRC principal safety barriers, l 1mmediately after notification of being sertoasly degraded, or the appropriate state or local results in the nuclear power agencies and not later than one hour plant being:

after the time the licensee declares one of the Emergency Classes. a) In an unanalyzed condition that

d. When making a report under paragraph significantly compromises 6.6.2.A.1.c above, the licensee plant safety, shall identify:

1) The Emergency Classification b) In a condition that is declared; or outside the design basis

2) Either paragraph (2)(a), of the plant, or

'One-Hour Report," or paragraph (2)(b), "Four-Hour Report." as c) In a condition not covered by the plant's

~

the paragraph of this section requiring notification of the operating and emergency Non-Emergency Event. procedures.

. 10140/10150 317 TSC 84-03(4)

Amendment Nos. 103, 93

o t

6.6.3.8 Special Reports Reports on the following areas shall be sutxaltted as indicated:

Topic SUBMITTAL DATE

a. In-Service Inspection Evaluation In accordance with the requirements of Section XI  :

ASME Boiler Code (IWA-6000) I

b. (Deleted) f 4

c. Containment Building Structural Testing Within 90 days following completion of each test.

Report (ILRT, Tendon) l

d. Changes to the Offsite Dose Calculation Within 90 days of effective date as part of the Manual (ODCM) Monthly Operating Report.

e. Waukegan Regional Airport Expansion The expansion plans and status of such plans for I' Plans.

- the Waukegan Regional Airport will be reported l yearly in the Annual Report, including FAA form 85010 report.

f. Low Temperature Overpressure Protection Within 30 days of operation.

System Operation

g. Primary Coolant Specific Activity As part of the Annual Report whenever Specification 3.3.6.has been exceeded. See page 124 for required report content. ,

h. pressurizer PORV or Safety Valve within 30 days as an LER.

Ea11ure to close SPECIAL REPORTS 1-Table 6.6-1 Amendment Nos. 103, 93 323

., 3n140/10150

6.6.3.B Special Reports (Continued)

I TOPlc SUBMITTAL DATE

1. Pressurizer PORV or Safety Valve Document the event in the Annual Report challenges -

}

j. (Future) v

k. Steam generator tube inspection and/or Per surveillance requirements 4.3.1.B.5 plugging.

1. Emergency Core Cooling System (ECCS) Within 30 days as LER - include nozzle usage l actuation and injection when RCS temp 1 factor per T.S. 3.3.2.F.3 350*F

m. Fire detector inoperability Within 30 days per T.S. 3.21.1.C

n. Fire pump system inoperability Within 30 days per T.S. 3.21.2.8

o. Fire suppression system inoperability Within 30 days per T.S. 3.21.2.C or 3.21.2.D I

p. Sprinkler system inoperability Within 30 days per T.S. 3.21.3.C

q. Low pressure 002 system inoperability Within 30 days per T.S. 3.21.4.C SPECIAL REPORTS Table 6.6-1 (Continued)

Amendment Nos. 103, 93

, , 3n140/10150 324