ML20079H214
| ML20079H214 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/02/1991 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20079H211 | List: |
| References | |
| NUDOCS 9110100204 | |
| Download: ML20079H214 (36) | |
Text
,
O O
l EXISTING TECH SPEC o
TS 6.0 .
O ' ADMINISTR ATIVE CONTROLS
- O O
3 3
D b
I b 9110100204 911002 PDR ADOCK 050002?.4 P PDR
O QUAD-CITIES OPR-29 6.0 ADMINISTRATIVE CON 1ROLS
.O 6.1 ORGANIZATION, REVIEW, INVESTIGATION, AND AUDIT A. Onsite and offsitt organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organiza-tions shall include the positions for activities affecting the safety of
- O the nuclear power plant.
- 1. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships, shall be documenter 1 and updated, as
'O appropriate, in the form of organization charts, functional descrip-tions of department responsibilities and relationships, and job descriptions for key personnel positions, or in the equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3'Organizatio O ,
" Interdepartmental Rel,ationships'.' puthority, Activitiesx* anoSection 6,
- 2. The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
O 3. The Senior Vice President-Nuclear Operations shall have the corpo-rate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
pe ric em
.O 4. The/ndividualswhotraintheoperatingstaffandthosewhocarey
-out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
O B. Deleted. l C. The shift manning for the station shall be as shown in Figure 6.1-3.
The Operating Assistant Superintendent. Operating Engineer, Shift Engi- I neers, and Shift Foremen shall have a Senior Operator's License. The fuel Handling Foreman has a limited Senior Operator's License. The O Vice President 6aWR Operations on the corporate level has responsibility I for the Fire Protection Program. The Maintenance Assistant Superintend- I ent will be responsible for implementation of the Fire Protection Progrcm. A-fire-beiged e-o f-e t-l ea s t-5-sembets-* %H-be-e a k ta hed-en-54te-et-aH-t4mes. This-exelvdes-the-shift-trew-necessary for safe s h u tdown1f-the-plen tr-end a ny-pees o nne4-requi red-fo r-o the r-etsen t4el
'O funet4 ens-during-a-ftee-emergency, 6.1-1 Amendment No. 117 O
- O -
a OtitD-CITIES
} .PR-29 J
4 D. Qualifications of the station management and operating staLf, excluding 3
the Health Physics Services Supervisor and the Radiat1orffrotection and ;
- O Chemistry Technicians, shall meet minimum acceptable levels as described '
in ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel",
j dated March 8, 1971. The Health Physics Services Supervisor or the Lead
- health Physicist shall meet the requirements of radiation protection manager of Regulatory Guide 1.8. The individual filling the position of j
Technical Superintendent shall meet the minimum acceptable level for
- O " Technical Manager" as described in Section 4.2.4 of ANSI N18.1-1971.
The Shif t Control Room Engineer shall have a bachelor's degree or equiva-lent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and i
accidents.
10 TheRadiatio[otectionTJecniciansshallhavesuccessfullycompleted 1
the established RadiatforgProtection Technician training program. The Chemistry Technicians shall have successfully completed the r.:tablished Chemistry Technician training program. Both shall have at seast a total of one year of general power plant, chemical or radia4:,,, prot experience, or equivalent training. In addition, %e Radiatforhraion rotection
- O t Technicians shall meet the criteria for " Individuals Qualified in Radia-i tionProtectionProcedures",asdescribedinthe0.L.Ziemann(NR letter to R. L. Bolger (CECO.) dated March 15, 1977. The Radiation Protection or Chemistry Technician training programs consists of the
] following:
- O 1. Satisfactory completion of an academic program. Topics of these c
courses include mathematics, nuclear physics, radioactive decay, i
4 chemistry, sampling techMoues, reactor coolant parameters, radia-tion exposure, shielding, biological effects of radiation exposure, radiation survey techniques, personnel monitoring, and emergency
.O procedures, as appropriate for their area.
- 2. Satisfactory performance on a compr hensive examination following completion of academic training.
- 3. On-Shift training under the supervision of a qualified Radiatior[
Protection or Chemistry Technician.
!O-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.
.4 A training program for the fire brigade shall be maintained under the direction of the Station Fire Marshal and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 except that training sessions shall be at least quarterly.
F. Retraining for licensed operators, senior operators, and senior operators
- O (limited) shall be conducted at intervals not exceeding 2 years.
6.1-2 Amendment No. 117 lO d
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QUAD CITIES OPR-29 i
G.
The Review and Investigative Function and the Audit Function of activ-O ities affecting quality during facility operations shall be constituted ;
and have the responsibilities and authcrities outlined below:
- 1.
The Superinterndent of the Offsite Review and Investigative Function shall be appointed by the Manager of Quality Assurance / Nuclear j; Safety (QA/NS). The Corporate Audit Function shall be the respon-sibility of the Manager of QA/NS and shall be independent of i
operations.
The Manager of QA/NS reports directly to the Chief Executive Officer 1
! ^ and has the responsibility to set Corporate Policy for both the areas of Quality Assurance and Nuclear Safft/. Policy is promul-i
- O gated through a central policy committee directed by the Manager of QA/NS. The Manager of QA/NS has the responsibility for the perform-i ance of periodic audits of each nuclear station and corporate departments to determine that QA/NS policy is being carried out,
- a. Offsite Review and Investigative Function l The Superintendent of the Offsite Review and Investigative Function shall: (1) provide directions for the review and investigative function and appoint a senior participant to provide appropriate direction, (2) select each participant j for this function, (3) select a complement of more than one participant who collectively possess background and qualifica-tions in the sub ect matter under review to provide comprehen-sive interdiscip inary review coverage under this function, (4) independently review and approve the findings and recom-mendations developed by personnel performing the review and 0- investigative function, (5) approve and report in a timely manner all findings of noncompliance with NRC requirements to
- the Station Manager Vice President 6BWR Operations, Manager of QA/NS, Assistant Vice President (AVP) Quality Programs and Assessment and the Senior Vice President-Nuclear Operations, j
1 During periods when the Superintendent of Offsite Review and
'o Investigative Function is unavailable, he shall designate this responsibility to an established alternate, who satisfies i
the formal training and experience requirements for the Superin-tendent of the Offsite Review and Investigative Function. The responsibilities of the personnel performing this function are stated below. The Offsite Review and Investigative Function shall review:
9 i
(1) The safety evaluations for (1) changes to procedures, equipment, or systems as described in the safety analysis report and (2) tests or experiments completed under the i provision of 10 CFR 50.59 to verify that such actions did g not constitute an unreviewed safety question. Proposed changes to the Quality Assurance Program description shall b2 reviewed and approved by the Manager of QA/NS. I-6.1-3 Amendment No. 117 D
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QUAD-CITIES DPR-29 (2) Proposed changes to procedures, equipment or systems O which involve an unreviewed safety question as defined in 10 CFR 50.59.
(3) Proposed tests or experiments which involve an unreviewed safety question fined in 10 CFR 50.59.
0 (4) Proposed changes in Technical Specification NRC operating licenses.
(5) Noncompliance with NRC requirement , or of internal proceduren")or instructions causin ear safety signi ficarM.
O (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.
g (7) R//>$///)I// //////.
(8) All recognized indications of an unanticipated deficiency 4
in some aspect of design or operation of safety-related structures, systems, or components.
O (9) Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such change.
(10) Review and report findings and recommendations regarding g all items referred by the Technical Staff Supervisor, Station Manager Quality Programs, and Assessment,Vice President?BWR Ope
- b. Station Audit function i
g The Station Audit Function shall be the responsibility of the AVP Quality Programs and Assessment independent of BWR Opera-tions. Such responsibility is delegated to the Nuclear Quality Programs Manager.
The Nuclear Quality Programs Manager shall approve the audit I agenda and checklists, the findings and the report of each 3 audit. Audits saall be performed in accordance with the Company Quality Assurance Program and Procedures. Audits shall be performed to assure that safety-related functions are covered within a period of 2 years or less as designated below.
, (1) Audit of the-/onformance of facility operation to provi-V sions contained within the Technical Specifications and applicable license conditions at least once per year.
6.1-4 Amendment No. 117 D
O .
QUAD-CITIES OPR-29 (2) Audit-+Mhe-/dherence to procedures, training and o qualification of the station staff at least once per year.
(3) Ad't- of-the /esults of actions taken to correct derb ciencies occurring ir. facility equipment, structures, systems, or methods of operation that affect nuclear safety at least once per 6 months.
(4) AudR-eHhe/erformance of activities required by the Quality Assurance Program to meet the Criteria of Appendly "B" 10 CFR 50.
(5) A t-of Ah Facility Emergency Plan and implementing o . procedures at least once per year.
(6) As,dit ;f-/he facility Security Plan and implementing procedures at least once per year.
(7) Audk/nsiteandoffsitereviews.
(8) Audit,/he facility Fire Protection Program and implement-ing procedures at least once per 24 months.
(9) The radiological environmental monitoring program and the i results thereof at least once per 12 months.
O (10) The ODCH and implementing procedures at least once per 24 months.
(11) The PCP and implementing procedures for solidification of radioactive waste at least once per 24 months.
O .
(12) Report all findings of noncompliance with NRC requirements and recommenoations and results of each audit to the Station Manager, Manager of QA/NS, AVP Quality Programs and Assessment, Vice President BWR Operations the Senior Vice President-Nuclear Operations, and the Chief Operating
!O Officer.
- c. Authority The Manager of. QA/NS reports to the Chief Execu i Officer.
The Manager of QA/NS has the authority to order unit shutdown g or request any other action which he deems necessary to avoid unsafe plant conditions.
p Q
- v. 5 Amendment No. 117
'O
. _ - . _ _ . . _ . . . . _ . . , , . _ . . _ . ._.._.___._~,...;__,--.-_,_._,,~..,___ - - . _ _ - . _ . , . . . . . , - . .
D QUAD-CITIES DPR-29 The AVP Quality Programs and Assessment reports to the Senior 4 Vice President-Nuclear Operations.
The AVP Qu ity Programs and Assessment has the authority to recommend nit shutdown or 4
request any other action ansofa plant conditions. which he deems necessary to avoid reported immediatel All such disagreements shall be OperatingOfficer,ytothe/hr.agerofQA/NSandtheChief
- d. Records ,
(1)
Reviews, audits, and recommendations shall be documented and distributed as covered in 6.1.G.I.a and 6.1 G.1.b.
(2)
Copies of documentation, reports, and correspondence shall be kept on file at the station,
- e. Procedures Written administ,rative procedures shpil be prepared and main-described in Specifications 6.1.G.1.a.tained 0 Those procedures shall for the,4f f sit cover the following:
(1)
Content and method of submission of presentations to the Superintendent of the Offsite Review and Investigative Function, s
(2) Use of committees and consultants.
(3) Review and approval, 2 (4) Detailed listing of items to be reviewed.
(5) Hethod of (1) appointing personnel investigations,(3)reportingfindIng(2)performingreviews s and recommendations of (5)reviews and reports.
distributing investigations, (4) approving reports, and (6)
Determining satisfactory completion of action required based on approved findings and reccmmendations reported by personnel performing the review and investigative function,
- f. Personnel 1)
The persons, including consultants, performing the review and investigative function, in addition to the Super-intendent tion, shallof the Offsite Review and Investigative func-have expertise in one or more of the following 6.1-6 Amendment No. 117
m ~
O QUAD-CITIES OPR-29 being reviewed and investigated: disciplines as ap a) nuclear power plant technology, b) reactor operations, c) utility operations, d) power plant design, O e) reactor engineering, ;
f) radiological safety, t g) reactor safety analysis, h) instrumentation and control,
- 1) metallurgy, j)
O characteristics of the facility.any other appropriate d 2)
Individuals performing the Review and Investigative Function shall possess a minimum formal trainin experience as listed below for each discipline.g and O a) Nuclear Power Plant Technology Engineering graduate or equivalent with 5 years operations. in the nuclear power field design and/or experience
'O N *** *' OP ***
Engineering graduate ce equivalent witt 5 years experience in nuclear power plant operations, t c) Utility Operations Q
Engineering graduate or equivalent with at least 5 years of experience in utility operation and/or engineering, d) Power Plant Design e
Engineering yeart of ex graduate or equivalent with at least 5 operation, perience in power plant dan,ign and/or e) heactor Engineering 8
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) Radiological Safety Engineering graduate or equivalent with at least 5 years of experience in radiation control and safety.
6,1 '/-
D Amendment No. 117 l _ . . . . . . . . . _ . . . . . . ,
.O i
QUAD-CITIES l DPR-29
- O g) Reactor Safety Analysis !
En,.ineering graduate or equivalent, with at least 5 years of experience in nuclear engineering.
y h) Instrumentation and Control Engineering graduate or equivalent with at least 5 years of experience in instrumentation and control
- design and/or operation.
.O i) Metallurgy Engineering graduate or equivalent with at least 5 years of experience in the metallurgical field.
- 3) The Superintendent of the Offsite Review and Investigative O '
. 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 Manager.
- O a. Onsite Review and Investigative Function The Station Manager shall
- (1) provide direction for thn Review and Investigative Function and appoint the Technical Staff Supervisor, or other comparably que.lified individual as a senior participant to provide a.ppropriate directions; (2)
- O approve participants for this function;-(3) assure that a complement of more than one participant who collectively possess background and qualifications in the subject matter under review are selected to provide comprehensive interdisciplinary review coverage under this function; (4) independently review and approve the. findings and
,O rec mmendations vieveloped by personnel performing the Review i
and Investigative Function; (5) report all findings of noncompliance with NRC requirements, and provide recommenda-tions; and (6)-submit-to the Offsite Review and Investigative Function concurrence in a timely manner, those items-described in Specification 6.1.G.I.a which have been approved by the
'g Onsite Review and Investigative Function. The. responsibilities of the [ersonnel performing this function are. stated below:
- 1) Revitw of (1) procedures required by Specification 6.2 and changes thereto and (2) any other proposed procedures
! or changes thereto as determined by the Station Manager O to affect nuclear safety.
- 2) Review cf all proposed tests and experiments that affect
, nuclear safety, O 6.1-8 Amendment No. 117
O QUAD-CITIES OPR-29 0 3) Review of all proposed changes to the Technical Specifications.
- 4) Review of all proposed cileages or modifications to plant systems or equipment that affect nuclear safety.
O S) Investigation of all noncompliance with NR, requirements and shall prepare and forward a report ceverhg evaluation and recommendations to prevent recu,'rence.
6)
Review of facility operations to detect potential safety hazards.
O
- 7) Performance of special reviews and investigations and j .
reports thereon as requested by the Superinteadent of the Offsite Review and Investigative Function.
O 8) Review of the Station Security Plan and shall submit t
recommended changes to the Director of Corporate Security and the AVP Quality Programs and Assessment in lieu of the distribution in accordance with 6.1.G 2. 1).
- 9) Review of the Emergency Plan and station implementing O procedures and identification of recommended changes.
- 10) Review of f//(([//// /)fjl/// and actions taken to prevent recurrence.
- 11) Review of any unplanned on site release of radioactive O. 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 Vice PresidentG8WR Operations and to the Superintendent of the Offsite Review and Investigative Function.
O
--> to the radwaste treatment systems.
- b. Authority 3 The Technical Staff Supervisor is responsible to the Station Manager and shall make recommendations in a timely manner in all areas of review, investigations, 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 O
- 13) RevoeuJ cf +he Forc Projecken Progra w, and ]
in, plea.cnfing preccclares and the submiHal cf reccmmendect chany tc the ($si/C
~ i Re vieuJ a nd in Vesh quNvc t d n C*t en _
6.1-9 Amendment No. 117
- O QUAD-CITIES DPR jo compliance with rules, regulations, and procedures when in
' his opinion such action is necessary. The Station Manager shall follow such -recommendations -or select a-course of action that is more conservative regarding safe operation of the facility. All such disagreements shall te reported immediately to the Vice President 3 WR Operations and the lO Superintendent of the Off site Review and Investigative Function.
- c. Records
- 1) Reports, reviews, investigations, and recommendations
- prepared and performed for specification 6.1 G.2,a'shall be
- O documentedwithcopiestotheVicePresident26WROperationg the Superintendent of the Offsite Review and Investigative Function, the Station Manager, and the AVP Quality Programs
- and Assessment.
- 2) Copies of all records and documentation shall-be kept on 20 file at the station,
- d. Precedures Written administrative procedures shall be prepared and maintained for conduct of the Onsite Review and Investigative O function. These procedures shall include the following:
i 4
- 1) Content and method of submission and presentation to the Station Manager, Vice President _BWR Operations, and the Superintendent of the Offsite Review and Investigative Function.
- O j 2) Use_of committees when necessary.
l 3) Review and approval, j
- 4) Detailed listing-of items to be reviewed. -
- O Procedures-for administration of the quality control-5)-
activities.
- 6) Assignment of responsibilities.
- O e. Personnel i
1)_ The personnel performing the Onsite Review and 4
Investigative Function, in addition to the Station Manager,_ shall consist of persons having expertise in:
O a) . nuclear power plant technology,_
b) reactor operations, c)_ reactor engineering, 6.1-10 Amendment No. 117 O
i -- . . -_ .- - . _ . . . . - -. .. -
O .- -
QUAD-CITIES DPR-29 chemisfr O d) radiological safety and :M;;.ist,]
e) instrumentation and control, and f) mechanical and electric systems, 2)
Personnel performing the Onsite Review and-Investigative Function shall meet minimum acceptable levels u O described in ANSI N18.1 1971, Sections 4.2 and 4.4.
H. Fire Protection Program An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing O, either qualified protection firm. offsite licensee personnel or an outside fire An inspection and audit of the fire protection and loss-prevention program least onceshall per 36 bemonths.
performed by a qualified outside fire consultant at O'
O O
O O
, ,0 6.1-11 O Amendment No. 117
9 4 OVA 0,.R!?!!1 0029 KletteJw tuf t? Manette f Matte C0401730 OF ont Wh!T (he fuel in Secono untt)
Ltcense g Category intttal Fuel toastop Cola shutsown or ase,e Cold er Durtag gefueling tefueling Shutcowi Shutta=n lentor Operator ,
License 3 1 3
Operator License 2
O sea. erot. a.a ---
i 2 3 i i son- ucense. ai seguire.) i a Salf t Techntcel Asvtsor mene Reguired none Seguired 1 O
Concli!C. OF 5tCon0 UNIT (One Unit at Mot shutsown or at Pomer)
Lttensa Category Initial fuel toastng Cole shutoo 3 or aoove Cols er Curtng tefueling Refueling SM tsoen Shutoown lentor' Opera tor License 2 2 2 Operator
- License 3' 3 3 ass. Prot. Man i
' , i I son.a tcorises 3, ( As tequires)
O J e Shif t Technical Aeviser 1
1 1 Com0!T10m 0F $tCCm0 Unit 3 (9te teitt at Cold shutcom er Refueling shutcomml License Category Insttal Fuel toasteg Cole snutoomn or er Ourtng tofueltog ecove Cole --
aefueling Shutsoun Shutsomn.
Santor*
j Coerator
.. License 2 1
! 2 Operator' O License- 3 2 1 Ras. Prot. Men i I l man. Licensed ie (As n0guires) 3 3 Snif t fecantcal Aertsor mone tenutres mene Required 1
- Asswes each instvidual is licensed on each facility.
refuell'ag. one Senior engineer (1tetted license) =111 supervise fuel hans11ag.During inttlet fuel loading t Shtf t crew composition may W 1ess than the sintaue requirerwnts for a pertoe of time not to esteed 2 nours in creer to acconocente ueespectee 40tence of on duty shif t crew nereers Orovised Isreciate action recuirarments is taken of rigure s.l.a.to restore the shif t crew ccrcosition to althin the sinimum Figure s.i-a i
Amendment No. II4 -
D
. ~ _ _
f 4
O QUAD-CITIES OPR-29 6.2 PLANT OPERATING PROCEDVRES s ANo re4 cam O A.
Detailed written procedures covering items listed below,shall be preparedincluding applicable
- 1. , approved, and adhered Normal startup O
2.
systems and com,ponents involving nuclear safe Refueling operations. e facility.
3.
Actions to be taken to correct specific and f O
malfunctions of systems or components, alarms including oreseen potential responses to P.hanges,. suspected primary system leaks,yand abno 4
Emergency radioactivity conditions involving potential or act
" Generating Station Emergency ual release Pla " of emergency and abnormal procedures. n and station O 5.
of the facility. Instrumentation operation which could have 6.
effect on the safety 7
an effect on the safety ofons the facility. Preve which could have Surveillance and testing requirements .
B.
Tests and experiments.
9.
10.
Procedure to erisure safe shutdown ant.
of the pl O '
11.
Station Security Plan and implementation p rocedures.
Fire Protection Program implementation
- 12. .
ODCH implementation.
O 13.
PCP implementation.
14 Working hours of the Shift Engineer Shift FoNman, and the Nuclear Station Oper t
.O such that the heavy use ofa or overtime is not routi, job classifications nely required.
O 6.2-1 O Amendment No. 117 i
)
QUAD-CITIES OPR-29 6.2 PLANT OPERATING PROCEDURES AND PRc4R An15
) '
B. Radiation control procedures shall be maintained, made available to all L station personnel, and adhered to. The procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20. This radiation protection program shall be B organized to meet the requir2ments of 10 CFR 20.
! C. 1. Procedures for items identified in Specification 6.2. A and 6.2.B and any changes to such procedures shall be reviewed and approved by the
- ! Technical Staff Supervisor, an Assistant Superintendent or the Technical Superintendent, and department head responsible for the D activity performed. 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 authoriza-tion by the Station Manager before being implemented.
- 2. Work and instruction type procedures which implement approved B
maintenance or modification procedures shall be approved and authorized by the Maintenance Assistance Superintendent where th-)
written authority has been provided by the Station Manager. The
" Maintenance work shall be soModification approved onlyProcedure" if procedures utilized for safet$inelated referenced the
" Maintenance Modification Procedure " have been approved as required by 6.2.A. Procedures which do not fall within the requirement of 6.2. A or 6.2.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:
D
- 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.
P "
Onsite.
- 3. The change is documented, reviewed the On-Site Review and Investigative Function, and approved by the Station Manager within 14 days of implementation.
E. Drills of the emergency procedures described in Specification 6.2.A D
shall be conducted in accordance with the GSEP manual.
P. 4 G . INS E R.T" A TTAOIED lb)fCKmf9 7/Cr)
D D
6.2-2 Amendment No. 117
)
> INSERT FOR TECHNICAL SPECIFICATION PAGE 6.2-2 F.
Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for doses low as reasonably to MEMBERS OF Tile PUBLIC f rom radioactive ef fluen achievable. The program contained in the ODCM, (2) shall be implemen(ted 1) shall be by operating procedures, and 3 whenever the prog (ra)m limits are exceeded.shall include remedial actions to be t include the following elements: The program shall i
1.
Limitations on the OPERABILITY of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint methodology determination in accordance with the in the ODCM, 2.
Limitations released in liquid on the concentrations ef fluents of radioactive to UNRESTRICTED AREAS material conforming 2.
to 10 CFR Part 20, Appendix B, Table II, Column 3.
Monitoring, and gaseous sampling, effluents and analysis of radioactive liquid with the methodology and parameters in the ODCM.in accordance with 4.
Limitations on the ar.nual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materialn 50, in liquid effluents released from each unit toUN S.
Determinativn of cumulative and projected dose contributions calendar quarterfrom andradioactive effluents current calendar yearfor in the current accordance with everythe 31 methodology days, and parameters in the ODCM at least 6.
Limitations on the OPERABILITY and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a the I to 10 annual CFR Part dose
- 50. or dose commitment conforming to Ap 7.
Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITEPart CFR BOUNDARY conforming 20, Appendix B, Tableto the doses associated with 10 II, Column 1, 1
i O
O INSERT FOR TECHNICAL SPECIFICATION PAGE 6.2-2 (Continued)
- 8. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents f rom each unit to areas beyond the SITE BOUNDARY g conforming to Appendix I to 10 CFR Part 50,
- 9. Limitaticns on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to O Appendix I to 10 CFR Part-50,
- 10. Limitations on the annual dose or dose commitment to any MEMBER CF THE PUBLIC due to releases of radioactivity and to radiation - from uranium fuel cycle sources conforming to 40 CFR Part 190.
3 G. Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.- The program shall nrovide (1) representative measurements of radioactivity in the highest potential exposure pathways 3
of the accuracy of the effluent monitor 1n.and g program (2)-verification and-modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the.
guidance of Appendix I to 10 CFR Part 50, and-(3) include the following:
- 1. Monitoring, sampling, analysis, and reporting of radiation 0 and radionuclides in the environment in accordance with the methodology and parameters-in the-CDCM,
- 2. A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this-census, and g
- 3. Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in' environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
)
J-4
O QUAD-CITIES OPR-29
- 6. 3 REPORTABLE EVENT ACTION O
A. The following actions shall be taken for Reportable Events:
- 1. The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 of 10 CFR Part 50.
n t>
- 2. ensite.
Each Reportable Event shall be reviewed by the On-;ite Review Committee, and the results af this review shall be submitted to the eff-Site Review and Investigative function and to the Vice Presidenb"BWR Operations.
O 0$1fe_
O O
O o
O D
- 6. 3- 1 Amendment No. 117 D
e O
QUAD-CITIES OPR-29
.3 6.4 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIM.T IS EXCEEDED t
If a /j//// //ff/ 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 Vice PresidentE8WR Operations or his designated alternate. The incident shall be reviewed g
pursuant to Specifications 6.1.G.I.a and 6.1 G.2.a and a separate report for each occurrence shall be prepared in accordance with Specification 6.3.A.1.
3 G
9 9.
O S
3 6.4-1 Amendment No. 117
10 QUAD-CITIES DPR-29 ,
O 6.5 PLANT OPERATING RECORDS A. Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained for at least 5 years:
O l' " 'd5 I " '**I PI'"t Pti "' i"Cl"di"9 P *'" IIS '"d periods of operation at. each power level;
- 2. Records of principal maintenance tivities, including inspection and repair, regarding principal items of equipment pertaining to nuclear safety; O 3. Records and reports of ////////// ////// and ////// ////[
occ'Jrrences ;
- 4. Records and periodic checks, inspection and/or calibrations performed to verify that the surveillance requirements (see Section 4 of these specifications) are being met (all equipment O failing to meet surveillance requirements and the corrective action taken shall be recorded);
- 5. Records of changes made to the equipment or reviews of tests and experiments to comply with 10 CFR 50.59; O 6. Records of radioactive shipments;
- 7. Records of physic tests and other tests pertaining to nuclear safety;
- 8. Records of changes to operating procedures; O
- 9. Shiftenoineefs* legs;and
- 10. Byproduct material inventory records and source leak test results.
B, Records and/or logs relative to the following items shall be recorded g in a manner convenient for review and shall be retained for the life of the plant:
- 1. Substitution or replacement of principal items of equipment pertaining to nuclear safety;
- 2. changes made to the plant as it is described in the SAR; O
- 3. Records of new and spent fuel inventory and assembly histories;
- 4. Updated, corrected, and as-built drawings of the plant;
- 5. Records of plant radiation and contamination surveys; O
- 6. Records of offsite environmental monitoring surveys; 6.5-1 Amendment No. 114 0
)
1
O QUAD-CITIES DPR-29 g 7. Records of radiation exposure for all plant personnel, including all contractors and visitors to the plant, in accordance with 10 CFR 20; i 8. Records of radioactivity in liquid and gaseous wastes released to the j environment; l
.n 9. Records of 6ransient or operational cycling for those components that
" have been designed to operate safely for a limited number of transient li or operational cycles;
- 10. Records of individual staff members indicating qualifications, s experience, training, and retraining; I
O 11. Inservice inspections of the reactor coolant system;
- 12. Minutes of meetings and results of reviews and audits performed by the
/ffsiteandpnsitefeviewandJuditfunctions;and
- 13. Records for Environmental Qualification which are covered under the
,J provisions of paragr aph 6.7.
l H. R e co r ch cy re vi ctus pe rf e r ru cc( po t" chctnges melde. fc the CFFStrE DCSE eRLcut A T'icN MANU AL- cn n cl. th e, PAccESS C c N r K O L. PRcQfLA m .
O
)
l3 l
r3 D
e 6.5-2 Amendment No. 114 e
1
O QUAD-CITIES OPR-29 O 6.6 REPORM NG REQUIREMENTS In addition to the applicable reporting requirement.s of Title 10, Code of federal Regulations, the following identified reports snall be submitted to the
.tinistraterwf the e[propi iate hgien&' Off k enin 3 othera se noted.
9 Os h.NuncarRoutineRepwory Repo 'rts Reyienni tfflee Ade NRC Rcenrmssier Dccument lent sider, + fr sf echt.
- 1. Startup Report A summary report of plant startup and power escalation testing shall be submitted 411owing (1) receipt of an operating license.
O (2) amendment to the license involving a planned increase in power level, (3) irstallation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered J.e nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the SAR and shall in O general include a description of the measured values of the cperating 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 O 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 reports shall be submitted at least every-three months until-all three events have been completed.
2.
9-
- 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 function (Note: this ttbulation supplements the requirements of Section 20.407 of 10 CFR 20), e.g. , reactor operations and surveillance, inservice
-inspection, routine maintenance, special maintenance (describe O- maintenance), waste processing, and refueling. The dose assignments to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling less than 20% of the individual total dose need not be_ accounted for, in the aggregate, at least 80% of_the total O
6.6-1 Amendment No. 114 0
O QUAD-CITIES OPR-29 whole body dose received from external sources shall be assigned O to soecific major work functions.
- 3. Monthly Operating Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis te the Directer, Officc cf O *"89****t-4*f****t4'n ind I"*9 **-C'"t**4 ' U 5 WCI'**
Regu le te ry-Goms h54en,-Washing tenrDC-20555rwith-e-topy-to-the-wprop+44te--Regi-on:1 Of' ice, to arrive no later than the 15th of each month Tollowing the-calendar month covered by the report. in-additien, any--chenges-to-the-00CM-shal4-be-submitted-wfth-the Mont hly4pera ti ng-Repo rt-wit h in-90-days-o f-t he-ef-fect-i ve-da te-of
.O th0 Ch2"0*-
A-repoet-of-wajoe-change-to-the radiocet4ve-waste-treatment sys tem s-she H-be-strbe i-t te&vit h-the-Monthly 1perirting-Rep u r i, iur the pericd in whkn 1.he avaiuot1Dn was reviewea and accepted by the-endte-review-hnc14onr-1-f--such-change b rreveheted-eM g not instc11edr-notM4 cat 4on-of-cance444t4on-of-4he-change cheel4 bc provi< fed-to-the-MG. .
- 4. Cl Q///Af(($ LlNf$ R$/ffi
- a. Core operating limits shall be established and documented in
'O the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part, of a reload cycle for the following: (1) The Rod Withdrawal Block Monitor Upscale Instrumentation Setpoint_ for Table 3.2-3 of Specification 3.2.C and for Specification 3.6.H. O (2) The overall average of the 20% inserticn scram time data for Specification 3.3.C. (3) The A////// P///// H/dl G/////[/// RJf/ (APLHGR) for Specification 3.5.I. (4) The L//ll/ H/// G///////ff Rlfi (LHGR) for Specifica-tion 3.5.J. (5) The M////// C//ff/// P//// RM// (MCPR) for Specifica-tion 3.5.K and 3.6.H. O (6) The K, core flow MCPR adjustment factor for Specifica-tion 3.5.K.
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by NRC O in NEDE-24011-P- A, General Electric Standard Application for Reactor Fuel (latest approved revision).
6.6-2 Amendment No. 120 'O
t O QUA']-CITIES DPR-29
- c. T% ctre operating limits shall be determined so that all 1
0 apolicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS litrits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
- d. The CORE OPERATING LIMITS REPORT, including any mid-cycle O revisi ns r supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control-Desk with copies to the Regional Administrator and Resident inspector.
B. Unique Reporting Requirements O
- 1. Raciesetis e C f f1 vent-Refeese-Repeet- (Semi- AnnuaW-A-semi-annual-report-shell be submit 4ed-to-the-Commi+eion-witMn 60-days-af ter Janvery 1 and July 1-of-each-year-specifying Lthe quant 4tt+f-each-of-the-rad 4cauc44 des-re19ased to unrest"icted O areas-f n liquid end-gateous-ef4hents-dueing-the--previcu: 5 months. The format-and-content-of-the repcrt : hall be 4a accoP6ance-*itbRe 19747--Any rnangesgulatory to-the PCPGuide 1.21-(43ev4s4cn shai-Hnr included in this1) report, d:ted June,
- 2. Environmental Program-Dete (Annuel Repvri-)
O so'o g#g 0y An-annual report containing the det: taker la the standard radiologicel .iuvni tvring prvyram (Touie-4.64) snaii ce suomit1.ea prier te u,;j ; 3; 33c3 jg37, 7he uvoluni of 1.ne repurL shall
&nclude:
O 6-N'* Ult; GI GII 00V4+*"502t3I ??2'"I?"IN!! E ~ 1"h?d i" 'h9 format-of-the-Reguhtery Cuide 4.0 Table 1 (Deceinber 1370'r. (Individuel sample result-s-will be retained at the Stat 4on), l*-the-event-that-seme rc: ult: Orc not--available fer- inclu; ion
*+th-the report, the-ceport- chal' bc tubmitted noting-ant explaining-tte reason; fcr the missing results. Summeries, o interpretet4cas, and analyti: Of_ trend: Of the-results are to
-be-prov4dedr-
- b. An assetsment-ef-the monit+ ring result: and radiction-dose-v4a the principel pathways cf expecure resultin; frc= plant O embsfofia ef redieactivity inc4uding-the maximum nob 4e-gas gamma-end4 eta air dosas ia the unrestricted area. The_
assessment of radiation-dese: cha44-be-performed in Octeedance with-the-ef4s44e-Gose-Galt+4ation Manual (ODCM).
- c. Resuks-of-4he con +us--to-deterene the locat4 ens--of-pearest res4dences -God-ef-neseby-animals-producing-ail' for human o consumpt4cn (Tab!c A. 0-4 )-
6.6-3 Amendment No. 120 0
.O l' jg INSERT FOR TECHNICAL SPECIFICATION PAGE 6.6-3 i ! 1. Semiannual nadioactive Effluent Release Report l The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of 'O peration shall be submitted within 60 days after January 1 .' and July 1 of each year. The report shall include a summary of the cuantities of radioactive liquid and gaseous effluents and solfd waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and L Section IV.B.1 of Appendix I to 10 CF3 Part 50. A single lO - submittal may be made for a multi-unit station. The submittal should combine those sections that are common to all units at the station. 4 2. Annual Radiological Environmental Operating Report
- O~
The Annual Radiological Environe. ental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and i analysis of trends of the results of the Radiological
- Environmental Monitoring Program for the reporting period.
, The material provided shall be consistent vlth the objectives i
~O outlined in (1) the occM and.(:s Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50. i IO i i 'O i i O i 0 _ . - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - , ~ 4 _.._._.,._m.
- . , , _ ~ , .- , . . . , _ y. , . , , .,,,,,m ,.,..,.,y e., - . . _ , . , - _ , _ . ,,
. . = - - -- . .. .- . .= - - -. .
O QUAD-CITIES OPR-29 The reason for the omission if the nearest dairy to the
- O station is not in the monitoring program (Table 4.8-4 e.
n annual summary of meteorological conditions concdrrent with ' e releases of gaseous effluents in the form of 'oint f Quency distributions of wind speed, wind dir tion, and atm'*pheric stability. a
- O f. The re uits of the Interlaboratory Comparisen Program describe in section 3.8,0.7.
g. The result of the 40 CFR 190 uranium J el cycle dose analysis s for each ca ndar year. / M ' h. A summary of U monitoring progr including maps showing sampling locatic s and tables gi ng distance and direction of sampling locatiu from the St ion. i
' 3. If a confirmed measured r dionucijde concentration in an O environmental sampling medi m avdraged over any calendar quarter sampling period exceeds the e acting level given in Table 4.8-5 and if the radioactivity is tributable to plant operation, a written report shall be suby:t d to the Administrator of the NRC Regional Office, with a copy to he Director, Office of Nuclear Reactor Regulation, with' 30 day from the end of the quarter.
O a. When detected more than in the o% of the inedium, the radio reco uclides in Table 4.8-5 are ing level shall have been exceeded if / Ci ~> 1 1 R.L.i. where is the average quarterly concent ation of the i th radiopuclide in the medium and RL is the r orting level of radi nuclide i. O b. I radionuclides other than those in Table 4.8 5 are detected nd are due to plant'ef fluents, a reporting lev is exceeded if the potential annual dose to an individual is qual to or greater than the design objective doses of 10 CFR Appendix 1. , g c. This report shall include an evaluation of any release conditions, environmental f actors, or other aspects nece sary to explain the' anomalous effect.
.3 7 Special Reports g Special Reports shall be submitted as indicated in Table 6.6-1.
6.6-4 Amendment No. 120 b
O QUAD-CITIES OPR-29 TABLE 6.6-1 .O SPECIAL REPORTS Spee+ % eti?n
,4fw Descrj7, gen Reference Submittal Date 9 a. Secondary containment leak rate test (1) 4.7.1 1 Upon completion of each test,
- b. Summary status of fel ?ceformance 1.1 Bases After each refueling outage c.
Materials specimens radiation surveillance 4. 6. B. / .5 O After each specimen remova and completion of analyses. d. Radioactive Source Leak Testing (2) 4.8.70 Annual report,
- e. Special Effluents Reports
&&A occM 30 days following 3*& occurrence.
O P6 . fr-{nt-S. [. E1plcsiVC Qas Hidurc ~ incperable recembiner 3 0. A g , c y ,p.e,
- O _ Notes 1.
subject of a shenry technical report.Each integrated leak rate the wind speed This report should include data on wind direction, outside and inside temperatures during the O test, rate. concurren,t reactor building pressure, and emergency ventilation data which demonstrate compliance with the specified . 2. microcu les or more of removable contamination.This report i O t O O 6.6-5 Amendment No. 114 O
O QUAD-CITIES OPR-29 . C) 6.7 ENVIRONMENTAL QUALIFICATION A. All safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of: Assistant of Operating Reactors " Guidelines for Evaluating Environmental Qualification of
$ Class IE Electrical Equipment in Operating Reactors" (00R Guidelines);
or, NUREG-0588 " Interim Staf f Position on Envir onmental Qualification of Safety-Related Electrical Equipment", December 1979. Copies of these documents are attacheo to Order for Modification of License DPR-29, dated October 24, 1980. and DPR- So () 8. 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 00R Guidelines or NUREG-05Ba. Such records should be updated and maintained current as equipment is replaced, furtt.er tested, or otherwise further qualified. O O O C) . O O 6.7-1 Amendment No. 114 O
O QUAD CITIES DPR-29 6.8 0FFSITE 00SE CALCULATION MANUAL (OOCH) A The ODCM shall describe the methodology and paramtters - to be used the calculation of offsite doses due to radioactive gaseous and liq T } (fluents and in the calculation of gaseous and liquid effluent moh(toring instrumentation alarm / trip setpoints consistent with .e {O applicable LCO's contained in these Technical Specifications. Methodd1 l Repla ce. are contahed in NUREG-0133.99ies and calculationalCommission procedures accepta
'* The ODCM sh "l Radiological Effhe submitted to the Commission at th ime of proposed review and approva nt Technical Specifications an hall be subject to the Commission prior plementation.
, B. 1 Licensee initiated chan'g s to the OOCH may l e made provided the change: 1.
! Shall be submitted to Operating Report pursuantxtohe Commis ' n by inclusion in the Monthly O of the date the change (s) w ification 6.6.A.3. within 90 days ade effective and shall contain:
- a. Sufficiently detaile'd info Information submit'ted should,ation to support the change.
pages of the ODCM to be chang (edqogether with appropriateon analyses or efaluations justifying the change (s); o b. A dete of rel ,rm1 nation that the change will reduce the accuracy iability of dose calculations or tpoint det(rminations; and cumentation of the fact that the change has O [c. and found acceptable by the onsite review functi en s.reviewed b Shall reviewbecome function. ef fective upon review and acceptance byite the o t
}.
O 9 4 6.8-1 Amendment No. 114 9
'O
.O INSERT FOR TECHNICAb SPECIFICATION PAGE 6.8-1 A. Changes to the ODCM:
- 1. Shall be documented and records of reviews performed shall be retained as required by S This d cumentati n shall contaln:pecification 6.5.B.14.
O
- a. Sufficient information to support the change together with the appropriate analyses or evaluations 9- justifying the change (s) and -
- b. A determination that the change will maintain the 13 level of radioactive effluent control required by 10 CFR 20.106, 40lCFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Iart 50 and not adversely impact 4 the accuracy or reli*'ility of effluent, dose, or setpoint calculatir .
- 2. Shall become effect2<e after review and acceptance by the 33 onsite review function and the approval of t:1e Plant Manager.
- 3. Shall be submitted to the Commission in the form of a 2
complete, legible copy of the entire ODCM as a part_of or concurrent with the Semiannual Radioactive Effluent- 'o Roleaso Report for the period of the report in which any ~ change to the ODCH was made. Each change.shall be 2 identified by markings in the margin of the affected pages, clearly indiceting the area of the page that was changed, and shall indicate the date (e.g., month / year)- the change was implemented. iO o O O 4 O
O QUAD CITIES OPR-29 O 6.0 PROCESS CONTROL PROGRAM (PCP) A The PCP shall contain the sampling, analysis, and formulation
-determination by which solidification of radioactive wastes from liquid-s' { ems is assured. ,/
O y . B. The PCbgil be approved by the Commission prior to implerpr on. nt ! wifh C. LicenseeinihaedchangesmaybemadetothePCPproviddthechange: a Hachect i l
- 1. Shall be subm tted to the Commission in t Semi-Annual Radioactive Effluent Releasele ort for the period which the change was O made and shall cont :
- a. Sufficiently deta dC f ation to suppert the change; I
Adeterminationth%tthe\chs.edidnotreducetheoverall b. conformance i dhe solidified ste product to existing O criter solid wastes; and
- c. Doc #entation that the change has been viewed and found 3(ceptable by the onsite review function.
- 2. $ hall become effective upon review and acceptance by e onsite O review function.
/
O 1 i o 4 9 6.9-1 Amendment No. 114 6
O INSERT FOR TECHNICAL SPECIFICATION PAGE 6.9-1 O A. Changes to the PCP: 1. Shall be be documented retained andbyrecords as required S of reviews performed chall documentation shall contain:pecification 6.5.B.14. This O a. Sufficient information to support the chango together with the appropriato analyses or evaluations justifying the change (s) and
- b. A determination that the change will maintain the O overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
2. Shall become effective after review and acceptance by the Manager.review function and the approval of the Plant onsite O O O l 1 o l 3 D 9 I ____ - - - - - - - - - - a
. _. . .- - . -. ._. . . . . - = _ . - __ - - --
O QUAD *CITl[5 DPR 29 6.10 k 10R CHANGES TO RADI0ACilVE WAST
, CASEOUS, 5pt l0)
A. L. be ensee initiated major changes to the radioactive waste
'de provided: / systetns O 1. I per change is reported in the Monthly Operating Repott for the funct don. in which the evaluation was reviewed by the/onsite review the discussion of each change shall cohtain:
- a. As ary of the evaluation that led to,,the determinntion
/
that ~O he change could be made in accopfance with 10 CFR 50.59
- b. /
Suf ficie change; t detailed information toAupport the reason for the c.
/
A detailed description of the/quipment, components and O process involveds.and the intprf aces with other plant systems, d. An evaluation of t s chan/ ga which snows the predicted releases of radioact fVr' materials in liquid and gas.>ous ef fluents and (or quant'ty of solid waste that dif f er from those previously py4 dict amendments); , in the license application and =O e.
/
Acmparisn.ofthepredictedyleses t radioactive materials in' liquid and gaseous gf fluents and in solid waste to the were actdal made; releases for the peKiod in which the changes
- f. \
An res61t estimate of the exposure of the change; and to plant operating personnel as a 9 found acceptable by the onsite review functio .ocume 'O 2. /The review
/ onsite change shall become effective upon review and acc function. .O o
6.10-1 1 Amendment No. I14 ,O
- o .
l lo l 1 SIGNIFICANT -HAZARDS' CONSIDERATIONS - iO AND - ENVIRONMENTAL ASSESSMENT EVALUATION- 'O PROPOSED TS 6,0- > g ' ADMINISTRATIVE CONTROLS" i.o 'O l lO f O . I 1 t-O i 4 .O-
. = - . . . . . . . - . . . . , , . . . - - . - . - . = . , - . . . . - . - . . .-
O O EYALUATION EQB RIGNIFICANI HAZARDS QQN_8_LD_ElhTJOli PROPOSED SPECIFICATION 6.0 ADMINISTRATIVE CONTROLS O The proposed changes provided in this amendment roguest are made in order to implement the recommendations of Generic Lotters 88-12, 86-10, and 89/01, and other minor changes. These changes have ' been reviewed by Commonwealth Edison Company and we believe that they do not present a Significant Hazards Consideration. The basis for our determination is documented as follows: O HASJfS EQB ((Q SIGNIFICANT HAZARDS CONSIDERATl.011 Commonwealth Edison has evaluated this proposed amendment and determined that it involves no significant hazards consideration. In accordance with the criteria of 10 CFR 50.92(c) a proposed
- amendment to an operating license involves no significant hazards O consideration if operation of the facility, in accordance with the proposed amendment, would not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated, because:
- a. The proposed change to remove the Jire Protection O Technical Specifications does not involve a significant increase in the probability or cons (quences of an accident previously evaluated because the change does not involve a physical modification to the plant, a change to any safety system or a change to any setpoint. The administrative concept of concurrently removing the fire protection o requirements from the Technical Specifications and incorporating these elements into the UFSAR and in implementing procedures, does not affect the safety analysis presented in the Quad Cities UFSAR. Adequate programmatic controls are added to Section 6.0 to ensure proper controls are maintained. The changes will not affect the functioning of the fire protection program, O which will be maintained pursuant to the operating license. No changes will be made to the program that conflict with the requirements of the operating license,
- d. The NRC issued Generic Letter 89/01 in order to allow the technical specification provisions for the Radiological Effluent Technical Specifications (RETS) and Process g Control Program (PCP) to be relecated to the Administrative Controls section of the technical specifications (programmatic requirements) and to the ODCM or PCP (procedural details). New programmatic controls for radioactive effluents and radiological environmental monitoring are relocated to Section 6.0 of the technical O specifications to conform to the regulatory requirements O
. . - . . - . ~ . . - - . . - - . . . - . - . . . - - -
lO l 7 1 10 of 10 CFR 20.106, 40 CFR Part 190,-10 CFR 50.36a, and j Appendix I to 10 CFR Part 50. Other changes to Sections
~
3.2/4.2 and 3.8/4.8, and described in the proposed changes ' for those sections, complete the requirements for The im lementation of the recommendations of GL 89/01. re ocation of the present technical specification requirements and the inclusion of programmatic controls in
- O Section 6.0 are not intended-to reduce Since thethe proposed level ofchanges
- radiological effluent control.
' to implement GL 89/01 provisions meet NRC requirements and l retain adequate programmatic controls for RETS in the ' !- technical specifications, the proposed change does involve ! a significant increase in the probability or consequences f an accident previously evaluated. lO ! c. The remaining changes for Section 6.0 provide Monthly Operating Report requirements that are consistent with later operating plants. These changes are applicable to Quad Cities and do not involve a significant increase in l
- the probability or consequences of an accident previously
- O evaluated.
l 2) Create the possibility of a new or different kind of accident from any previously evaluated because:
- a. The proposed changes to the Facility Operating License and l
the Technical Specifications represent an administrative IO shifting of-responsibility-for the Fire Protection Program " Requirements from the Technical Specifications to the UFSAR. The
- analysis or proposed the operation changes or function do not affect of any the accident safety-
! related equipment since the Fire Protection Program requirements will continue to be maintained. No new modes 9 of operation-are introduced by these proposed changes. Therefore, the proposed changes do not create the l ! possibility of a new or different kind of accident from i any previously evaluated.
- b. The proposed changes to the technical specifications resulting from the implementation of Generic-Letter 89/01 lO
- follow NRC guidelines for-relocating RETS and PCP procedural requirements to tP' ODCM and programmatic requirements for the ODCM ano 7P to Section.6.0 of the
- technical specifications. Sitwe the present level of radiological effluent. monitoring is maintained by the-i' proposed change, the proposed-change does not create-the 1 - possibility-of a new or different kind of accident from
%) any previously evaluated.
- c. The proposed changes to the Monthly. Operating Reporting requirements provide consistency with later operating i
plants' provisions. The proposed change in frequency of reporting requirements will not create the possibility.of a-new or different kind of accident from any previously O l O
%-- , - . - ..-,,me, , e-.-..w-, , , - - . . , _s,,,,e..,.yv, ,m.,-.,, ,,,,__: ,.,,.y.. y -.p ,~.,es ,g--,,,.c,.-y. . , - - , - .=
O evaluated. C)
- 3) Involve a significant reduction in the r'rgin of safety because
- a. The deletion of the Fire Protection Technical Specifications and incorporation 6f those provisions into O the UFSAR does not change the level of fire protection in the plant. Additionally controls added to Section 6.0 of the technical specificatlons and by the standard licenso condition and t1e 10 CFR 50.59 criteria vill ensure future changes to the Fire Protection Program ara properly evaluated. Therefore, the p oposed changes do not involve a significant reduction in t e margin of safety.
g
- b. The proposed implementation of the guidelines of Generic Letter 89/01 retains required RETS and PCP programmatic controls in Section 6.0 of the technical specifications and specific procedural controls in the ODCM and PCP. As ruch, the present margins of safety are preserved and the o changes do not involve a significant reduction in the marg n of safety.
- c. The proposed deletion of requirements from the Monthly Operating Reports and retention these reporting requirements in the Semiannual Radioactive Effluent Release Deport or in the ODCM or PCP, ensures that changes O to the ODCM and major changns to the radioactive wasto systems are reported to the NRC in a timely manner.
Therefore,in reduction the margin of safety.the changes do not involve a significant O O O O-O
O MMMM Ammm amm O PROPOSED SPECIFICATION SECTION 6.0 ADMINISTRATIVE CONTROLS Commonwealth Edison has evaluated the pro
- 1) in accordance with the requirenants of 10 CFR posed s1.21 amendment and has determined that the amendment meets the requirements for categorical exclusion as specified by 10 CFR 51.22(c)(9).
Commonwealth Edison has determined that the amendment , involvos no sign.ificant hazards consideration, there are no significant change in the types or significant increase in Q the amounts of any offluent that may be released offsite, and there is no significant increase in individual or cumulative l occupational radiation exposure. The proposed amendnsnt does not modify the existing _ mility and does not involve any now operation of the plant. a c, such, the proposed amendment does not involve any change O in the type or uignificant increases in offluents, or increase individual nr cumulative occupational radiation l exposure. The proposed amendment to Section 6.0,
" Administrative Controls" implomonts the guidance contained in Generic Letter 89-01 and Generic Letter 88-12 for the removal of the Radiological Effluent Technical Specification and Fire Protection Program, respectively. As such, the ,13 amendment does not impact those irreverslbin consequences beyond those already accepted by the NRC in the Finni Environmental Statement.
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f . O O QC-1 / QC-2 DIFFERENCES O TS 6.0 , O ' ADMINISTR ATIVE CONTROLS' O O 1 O O O O e
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O COMPARISON OF UNIT 1 AND UNIT 2 TECHNICAL 8PECIFICATIONS O roR THE l IDENTIFICATION OF TECHNICAL DIFFERENCE 8 SECTION 6.0 ADMINISTRATIVE CONTROLS O Commonwealth Edison has conducted a comparison review of the Unit 1 and Unit 2 Technical Specifications to identify any technical differences in support of combining the Technical Specifications into one document. The intent of the review was not to identify any differences in O presentation style (e.g. table formats, use of capital letters, etc.) or punctuation but rather to identify areas which the Technical Specifications are technically different. The review of Section 6.0 " Administrative Controis" did not identify any technical differences. O The following administrativo differences were t identified: EAga 6.1-2 Paragraph D Unit 1: Radiation / Protection and Chemistry O Technicians Unit 2: Radiation Protection and Chemistry Technicians Paragraph D.1 Unit li procedures, as appropriate for their area Unit 2: procedures, as appropriate to their C, area EAga 6.1-3 Paragraph G.1 Unit 1: of the Manager of QA/NS and shall... Unit 2: of the Manager of Quality Assurance / Nuclear Safety (QA/NS) O Paragraph G.1.a Unit 1: Assessment, and the Senior Vice President-Nuclear-operations Unit 2: Assessment,-and the Senior V1ce President of Nuclear Operations . g Pace f.1-9 Paragraph b. Unit 1: the distribution-in accordance with 6.1.G.2.C(1). Unit 2: the distribution in accordance with 6.1.G.2.c.(1). O 1 O 2
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I P O EAge 121-12 Paragraph c.1 Unit 1: documented with copies to the Vice President BWR Operations the Unit 2: documented with copies to the Vice President BWR Opurations, the 0 2agp 6,?,-1 Paragraph C.1 Unit 1 Technical Staff Supervisor, an Assistant Superintendent or the Technical Unit 2: Technical Staf f Supervisor, an Assistant Superintendent or Technical O pag 9 41b-L 1 i Paragraph A.1 Unit 1: shall be submitted at least every l three months Unit 2: shall be submitted at least overy 0 3 months Paragraph A.2 Unit 1: of station, utility, and Unit 2: of station utility, and EAq9 Lth-A O Paragraph h Unit 1: sampling locations Unit 2: samplings locations Eage 6.6-5 flote 2 Unit 1: presence of the 0.005 microcuries g Unit 2: presence of 0.005 microcuries EAge 6.9-1 Paragraph C.1 Unit 1: Shall ha submitted to the Commission in the Semi-Annual Radioactive Effluent O Unit 2: Shall be submitted to the Commission in the Radioactive Effluent EAtagEARh 6.10-1 Paragraph A.2 Unit 1: upon review and acceptance by onsite Unit 2: upon review and acceptance by by V onsite 3 3
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