ML20098A382

Proposed Tech Specs,Revising TS Upgrade Program & Improving Plant Submittals

ML20098A382
Person / Time
Site:	Quad Cities
Issue date:	09/20/1995
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20098A346	List: ML20098A345 ML20098A382
References
NUDOCS 9509250092
Download: ML20098A382 (34)

Text

.- .-. . - .- --

• t

., Responsibility 6.1 ADMINISTRATIVE CONTROLS .

6.1 RESPONSIBILITY 6.1.A The Station Manager shall be responsible for overall tacility operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.8 - The Shift Engineer shall be responsible for directing and commanding the safe overall operation of the facility under all conditions.

t QUAD CITIES UNITS 1 & 2 6-1 Amendment Nos.

9509250092 950920 PDR ADOCK 05000254 P- _ - . .. _ EDR

n

. Organization 6.2 ADMINISTRATIVE CONTROLS 6.2 ORGANIZATION 6.2.A Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shallinclude the positions for activities affecting the safety of 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 documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Manual.

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.

3. The Chief Nuclear Officer (CNO) shall have corporate 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.

4. The individuals who train the operating staff and those who carry 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.

OOAD CITIES - UNITS 1 & 2 6-2 Amendment Nos, s

l

. Organization 6.2  :

ADMINISTRATIVE CONTROLS 6.2.B Unit Staff 1

I The unit staff shallinclude the following:

i i

1. Three non-licensed operators shall be on site at all times. i

2. _. At least one licensed Reactor Operator shall be present in the control room when fuel is in the reactor, in addition, while the unit is in MODE (s) 1, 2, 3 or 4, at least one  :

) licensed Senior Reactor Operator shall be present in the control room. {

3. Shift crew composition may be less than the minimum requirement of 10 CFR f 50.54(m)(2)(i) and 6.2.B.1 and 6.2.C for a period of time not to exceed two hours in

, order to accommodate unexpected absence of on-duty shift crew members provided j immediate action is taken to restore the shift crew composition to within the minimum requirements.

t

4. A Radiation Protection Technician shall be on site when fuel is in the reactor. The position may be vacant for not more than two hours, in order to provide for j unexpected absence, provided immediate action is taken to fill the required position.  ;

5. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g, senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance i personnel.

The amount of overtime worked by unit staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12).

6. The Operations Manager or Shift Operations Supervisor shall hold a Senior Reactor Operator License.

6.2.C Shift Technical Advisor The Shift Technical Advisor (STA) shall provide technical advisory support to the Unit Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the facility. In addition, the STA shall meet the

qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. A single STA may fulfill this function for both units.

I QUAD CITIES - UNITS 1 & 2 6-3 Amendment Nos. '

i

. Unit Staff Qualifications 6.3 r

ADMINISTRATIVE CONTROLS . . - .. .. .. - . ..

6.3 UNIT STAFF QUALIFICATIONS I

Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, " Selection and Training of Nuclear Plant Personnel", dated March 8, 1971, except for the Rad / Chem Superintendent or Lead Health Physicist, who shall meet or exceed the qualifications of the Radiation Protection Manager as specified in Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents. ,

i i

I QUAD CITIES- UNITS 1 & 2 64 Amendment Nos.

i

l 1

.' I

. Training 6.4 'j

' ADMINISTRATIVE CONTROLS .. .

l 6.4 TRAINING A retraining and replacement program for the unit staff shall be maintained under the i l

direction of the appropriate on site manager. Training shall be in accordance with ANSI N18.1-1971 and 10 CFR 55 for appropriate designated positions and shallinclude familiarization with relevant industry operational experience.

i e

k l

l l

l i

)

i i

I OUAD CITIES - UNITS 1 & 2 65 Amendment Nos.  !

l

. [lNTENTIONALLY LEFT BLANK] 6.5 ADMINISTRATIVE CONTROLS 6.5 IINTENTIONALLY LEFT BLANK]

l THIS PAGE INTENTIONALLY LEFT BLANK.

l l

l l

1 l

l

' QUAD CITIES - UNITS 1 & 2 6-6 Amendment Nos.

, [lNTENTIONALLY LEFT BLANK] 6.6 ADMINISTRATIVE CONTROLS 6.6 IINTENTIONALLY LEFT BLANK)'

THIS PAGE INTENTIONALLY LEFT BLANK.

QUAD CITIES - UNITS 1 & 2 67 Amendment Nos.

Safety Limit Violation 6.7 ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.A -The following actions shall be taken in the event a Safety Limit is violated:

1. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Site Vice-President or his designated alternate shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. Within 30 days, a Licensee Event Report (LER) shall be prepared documenting the event pursuant to 10 CFR 50.73. The LER shall be submitted to the NRC.

3. Critical operation of the Unit shall not be resumed until authorized by the Commission.

QUAD CITIES - UNITS 1 & 2 6-8 Amendment Nos.

'l e.- ' Procedures and Programs 6.8

- ADMINISTRATIVE CONTROLS l i

gj PROCEDURES AND PROGRAMS l

6.8.A Written procedures shall be established, implemented, and maintained covering the l activities referenced below. >

.1. The applicable procedures recommended in Appendix A, of Regulatory Guide 1.33,  ;

Revision 2, February 1978, I

2. The Emergency Operating Procedures required to implement the requirements of .

NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Section 7.1 of Generic  !

Letter No. 82-33, . -l

. 3. Station' Security Plan implementation, j l

4. Generating Station Emergency Response Plan implementation,

.l t

L5. PROCESS CONTROL PROGRAM (PCP) implementation, j

6. OFFSITE DOSE CALCULATION MANUAL (ODCM) implementation, and  ;

l

7. Fire Protection Program implementation. -

6.8.B Deleted i I

j. 6.8.C Deleted j I-6.8.D ' The following programs shall be established, implemented, and maintained:

! )

1. Reactor Coolant Sources Outside Primary Containment )

l l

This program provides controls to minimize leakage from those portions of systems l j outside primary containment that could contain highly radicactive fluids during a j serious transient or accident to as low as practical levels. The systems include CS,-  !

HPCI, LPCI, RCIC, process sampling, containment monitoring, and standby gas j l treatment systems. The program shallinclude the following:

a. Preventive maintenance and periodic visual inspection requirements, and l l

b. Leak test requirements for each system at a frequency of at least once per  ;

j operating cycle. ]

i

. QUAD CITIES - UNITS 1 & 2 6-9 Amendment Nos. 1 f

1

i j

. Procedures and Programs 6.8 - l l

. ADMINISTRATIVE CONTROLS

.i l

2. . In-Plant Radiation Monitoring

(

This program provides controls which will ensure the capability to accurately )

determine the airborne iodine concentration in vital areas under accident conditions. l This program shall include the following:  !

a. Training of personnel, l r

b. Procedures for monitoring, and i

c. Provisions for maintenance of sampling and analysis equipment. l

3. Post Accident Sampling This program provides controls which will ensure the capability to obtain and analyze l reactor coolant, radioactive lodines and particulates in plant gaseous effluents, and i primary containment atmosphere samples under accident conditions. The program  !

shall include the following: j

a. Training of personnel,

b. Procedures for sampling and analysis, l f

c. Provisions for maintenance of sampling and analysis equipment, j 1

i i

1 l

l QUAD CITIES - UN!TS 1 & 2 6-10 Amendment Nos.' i i

t

Procedures and Programs 6.8 ADMINISTRATIVE CONTROLS

4. Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of i radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC""6"*"d"* from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by station procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shallinclude the following elements:

a. Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,

b. Limitations on the instantaneous concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to ten (10) times the concentration values in 10 CFR Part 20, Appendix B, Table 2, Column 2 to 10 CFR Part 20.1001 - 20.2402,

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM,

d. Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each Unit conforming to Appendix I to 10 CFR Part 50,

e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, a A MEMBER OF THE PUBLIC shall be an individualin a CONTROLLED or UNRESTRICTED AREA. An individual is not a MEMBER OF THE PUBLIC during any period in which the individual receives an occupational dose.

b The CONTROLLED AREA shall be an area. outside of a RESTRICTED AREA but inside the SITE BOUNDARY, access to which can be limited by the licensee f ar any reason.

c An UNRESTRICTED AREA shall be any area, access to which is neither limited nor controlled by the licensee, d RESTRICTED AREA shall be an area, access to which is limited by the licensee for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials. RESTRICTED AREA (s) do not include areas used as residential quarters, but separate rooms in a residential building may be set apart as a RESTRICTED AREA.

e The SITE BOUND ARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

DRESDEN - UNITS 2 & 3 6-11 Amendment No.

9 Procedures and Programs 6.8 ADMINISTRATIVE CONTROLS

f. 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 31-day period would exceed 2 percent of the guidelines for the annual dose conforming to l Appendix I to 10 CFR Part 50,

g. Limitations on the dose rate resulting from radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following:

1 a) For noble gases: less than or equal to a dose rate of 500 mrem /yr to the j whole body and less than or equal to a dose rate of 3000 mrem /yr to the 4 skin, and 4 b) For lodine-131, lodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: less than or equal to a dose rate of 1500 mrem /yr to any organ.

[ h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each Unit to areas beyond the SITE BOUNDARY conforming to Appendix i to 10 CFR Part 50,

i. Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from

lodine-131, lodinti-133, tritium, and all radionuclides in particulate form with h

:!f!!ves greater than 8 days in gaseous effluents released from each Unit conformirig to Appendix l to 10 CFR Part 50,

j. Limitations on the annual dose or dose commitment to any MEMBER OF THE i PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

4 1

i  !

l 4

QUAD CITIES - UNITS 1 & 2 6-12 Amendment Nos.

4

..- - . . - . . . . . - . . ~ . . . - .. . . .-.

.. Reporting Requirements 6.9 ADMINISTRATIVE CONTROLS .

i

- 6.9 REPORTING REQUIREMENTS In' addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Regional

Administrator of the appropriate Regional Office of the NRC unless otherwise noted.

6.9 A. Routine Reports l

1. Deleted

2. Annual Report l Annual reports covering the activities of the Unit for the previous calendar year, as 4 described in this section shall be submitted prior to March 1 of each year.

'l QUAD CITIES - UNITS 1 & 2 6-13 Amendment Nos.

. Reporting Requirements 6.9 ADMINISTRATIVE CONTROLS The reports required shallinclude:

a. Tabulation of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem / year and their associated person rem exposure according to work and job functions, e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignments to various duty functions may be estimated based on pocket dosimeter or TLD.

Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources should be assigned to specific major work functions.

b. The results of specific activity analysis in which the reactor coolant exceeded the limits of Specification 3.6.J. The following information shall be included: (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 radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up system 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; (4) Graph of the 1-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the reactor coolant exceeded the radiciodine limit.

3. Annual Radiolegical Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the Unit during the previous calendar year shall be submitted prior to May 1 of each year.

The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix l to 10 CFR Part 50.

QUAD CITIES - UNITS 1 & 2 6 14 Amendment Nos.

, Reporting Requirements 6.9 ADMIN!STRATIVE CONTROLS

4. Radioactive Effluent Release Report ,

The Radioactive Effluent Release Report covering the operation of the facility during  !

the previous calendar year shall be submitted prior to April 1 of each year. The report shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility. 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 Section IV.B.1 of Appendix l to 10 CFR Part 50.

5. Monthly Operating Report Routine reports of operating statistics and shutdown experience, including documentation of all challenges to safety valves or safety / relief valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S.

Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the NRC Regional Office, no later than the 15th of each month following the calendar month covered by the report.

6. CORE OPERATING LIMITS REPORT

a. Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

(1) The Control Rod Withdrawal Block Instrumentation for Table 3.2 E-1 of Specification 3.2.E.

(2) The Average Planar Linear Heat Generation Rate (APLHGR) Limit for Specification 3.11. A.

(3) The Linear Heat Generation Rate (LHGR) for Specification 3.11.D.

(4) The Minimum Critical Power Operating Limit (including 20% scram insertion time) for Specification 3.11.C. This includes rated and off-rated flow l conditions. ,

1

b. The analytical methods used to determine the operating limits shall be those l previously reviewed and approved by the NRC in the latest approved revision or supplement of topical reports:

(1) NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel,"

(latest approved revision).

(2) Commonwealth Edison Topical Report NFSR-0085, " Benchmark of BWR Nuclear Design Methods," (latest approved revision).

QUAD CITIES - UNITS 1 & 2 6 15 Amendment Nos.

l

Reporting Requirements 6.9 ADMINISTRATIVE CONTROLS (3) Commonwealth Edison Topical Report NFSR-0085, Supplement 1,

" Benchmark of BWR Nuclear Design Methods - Quad Cities Gamma Scan Comparisons," (latest approved revision).

(4) Commonwealth Edison Topical Report NFSR-0085, Supplement 2,

" Benchmark of BWR Nuclear Design Methods - Neutronic Licensing Analyses," (latest approved revision).

c. The core operating limits shall be deterrnined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The CORE OPERATING LIMITS REPORT, including any mid-  !

cycle revisions or 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.

6.9.8 Special Reports Special reports shall be submitted to the Regional Administrator of the NRC Regional Office within the time period specified for each report.

5 l

l l

1,  :

'i i

i l

t i I i

l l

I l

I QUAD CITIES - UNITS 1 & 2 6-16 Amendment Nos.

. [lNTENTIONALLY LEFT BLANK] 6.10 ADMINISTRATIVE CONTROLS 6.10 IINTENTIONALLY LEFT BLANK]

t

+

4 a

n 2

(

1

THIS PAGE INTENTIONALLY LEFT BLANK.

i i

d t

i QUAD CITIES - UNITS 1 & 2 '6-17 Amendment Nos.

. Radiation Protection Program 6.11 ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM 1 1

Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

i l

l I

i OUAD CITIES - UNITS 1 & 2 6-18 Amendment Nos.

High Radiation Area 6.12 ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA 6.12.A Pursuant to 10 CFR 20.1601(c), in lieu of the requirements of paragraph 20.1601 of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr at 30 cm (12 in.) shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP)* (or equivalent document). Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

1. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

2. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas

, with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or

3. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the RWP (or equivalent document).

6.12.B in addition to the requirements of 6.12.A, above, areas accessible to personnel with radiation levels greater than 1000 mrem /hr at 30 cm (12 in.) from the radiation source or from any surface which the radiation penetrates shall require the following:

1. Doors shall be locked to prevent unauthorized entry and shall not prevent individuals l from leaving the area. In place of locking the door, direct or electronic surveillance that is capable of preventing unauthorized entry may be used. The keys shall be maintained under the administrative control of the Shift Engineer on duty and/or health physics supervision.

2. Personnel access and exposure control requirements of activities being performed within these areas shall be specified by an approved RWP (or equivalent document). l I

f Health Physics personnel or personnel escorted by health physics personnel shall be exernpt from the RWP issuance requirements during the performance of their assigned radiation protection dutias, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.

QUAD CITIES - UNITS 1 & 2 6-19 Amendment Nos.

. .- =- _ .

l 1

I High Radiation Area 6.12 ADMINISTRATIVE CONTROLS

3. Each person entering the area shall be provided with an alarming radiation monitoring device that continuously integrates the radiation dose rate (such as an electronic ]

dosimeter.) Surveillance and radiation monitoring by a Radiation Protection Technician  ;

may be substituted for an alarming dosimeter.  !

l i

4. During emergency situations which involve personnel injury or actions taken to )

prevent major equipment damage, surveillance and radiation monitoring of the work ,

area by a qualified individual may be substituted for the routine RWP procedure (or equivalent document). ,

5. For individual HIGH RADIATION AREAS accessible to personnel with radiation levels of greater than 1000 mrem /h at 30 cm (12 in.) that are located within large areas  !

where no enclosure exists for purposes of locking, and where no enclosure can be t reasonably constructed around the individual areas, then such individual areas shall be  ;

barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.

QUAD CITIES - UNITS 1 & 2 6-20 Amendment Nos.

l

.. . PCP 6.13 -

6 ADMINISTRATIVE CONTROLS 6.13' PROCESS CONTROL PROGRAM (PCP)

' 6.13.A Changes to the PCP:

1. Shall be documented and records of reviews performed shall be retained. This-documentation shall contain: ,

a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and,

b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

2. Shall become effective after approval of the Station Manager. i l

T P

QUAD CITIES - UNITS 1 & 2 6-21 Amendment Nos.

I

1

-. ODCM 6.14 l l ADMINISTRATIVE CONTROLS l

-l l

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) d 6.14.A Changes to the ODCM:

1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain: ,

a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and,

b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix i to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

t

2. Shall become effective after approval of the Station Manager. -

P

3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Report for the period of the report in which any change to the ODCM was made effective. Each l change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,

month / year) the change was implemented.

l

)

l I

1 l

I

' 1 I

QUAD CITIES - UNITS 1 & 2 6 22 Amendment Nos.

l ATTACHMENT 4 EXISTING TECHNICAL SPECIFICATIONS Technical Specification 6.0

" ADMINISTRATIVE CONTROLS"

)

i i

l I

k:\nla\ quad \tsup\60,att2.wpf 1

ATTACHMENT 4 DELETION OF CURRENT TECHNICAL SPECIFICATIONS This proposed technical specification amendment will replace the current section 6.0, Administrative Controls, for the Quad Cities Unit 1 and Unit 2 Technical Specifications. The specifications are replaced in its entirety with revised pages that combine the Unit 1 and Unit 2 specifications. In addition, the proposed TS changes relocate requirements from the Operating License to TSUP Section 6.0. To reduce the administrative requirements to process this amendment package, a list of the deleted pages for Quad Cities Unit 1 and 2 are provided; the current versions of existing .

pages will be provided separately for the NRC Staff's information and for comparative purposes. In addition, a marked-up version of the revised pages from Facility Operating Licenses DPR-29 and DPR-30 are included in this Attachment. <

Delete the following pages:

DPR - 29 DPR - 30 DPR - 29 DPR - 30 .

6.11 6.1-1 6.41 6.4-1 6.12 6.1-2 6.5-1 6.5-1 6.1-3 6.13 6.5-2 6.52 l 6.14 6.1-4 6.6-1 6.61 6.1-5 6.1-5 6.6-2 6.6-2, 6.6-2a 6.1-6 6.1-6 6.6-3 6.6-3 6.17 6.1-7 6.6-4 6.6-4 6.1-8 6.1-8 6.65,6.6-6 6.6-5 6.19 6.19 6.7-1 67-1 6.110 6.1 10 6.8-1 6.81 1 6.1 11 6.1-11 6.9-1 6.91 6.2-1 6.2-1 6.10-1 6.10-1 6.2-2 6.22 6.11 1 6.11 1 6.23 6.23 6.12-1 6.12 1 l 63-1 63-1 Fir 6.1-3 Fir 6.1-3 Delete License Condition 2.G,2.J and 2.L in DPR-29.

Delete License Condition 2.H,2.I and 2.K in DPR-30.

kAnla\ quad \tsup\60,att2.wpf l

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

DPR 29

I Am.108 E. Physical Protection j

. 06/09/88 The licensee shall fully implement and maintain in effect all provisions of the

! - Commission approved physical security, guard training and qualification, and s safeguards contingency plans including amendments made pursuant to i provisions of the Miscellaneous Amemdments and Search Requirements

! revisions of 10 CFR 73.55 (51 FR 27817 and 27822), and to the authority of 10

( CFR 50.90 and 10 CFR 50.54(p). These plans, which contain Safeguards i I

information protected under 10 CFR 73.21, are entitled: " Quad Cities Nuclear Power Station Security Plan," with re' visions submitted through January 14,  !

l l ' 1988; " Quad Cities Nuclear Power Station Security Personnel Training and j j- Qualification Plan," with revisions submitted through October 29,1987; and  !

j " Quad Cities Nuclear Power Station Safeguards Contingency Plan," with  ;

q revisions submitted through February 16,1984. Changes made in accordance l 1 with 10 CFR 73.53, shall be implemented in accordance with the schedule set  ;

. forth therein. l

. Am; 141 F. Commonwealth Edison Company shall implement and maintain in effect all '

. 05/13/93 provisions of the approved fire protection program as described in the Updated

Final Safety Analysis Report for the' facility and as approved in the Safety y Evaluation Reports dated July 27,1979 with cupplements dated November 5,1980, and February 12,1981; December 30,1982; December 1, .

i- 1987 with supplement dated April 20,1988; December 11,1987 with  !

supplement dated July 21,1988; and February 25,1991, subject to the following l provision:  ;

l The license may make chanegs to the approved fire protection program without ,,

t prior approval of the Commission only if those changes would not adversely  :

I

affect the ability to achieve and maintain safe shutdown in the event of a fire.

r Am. 2 i G. Systams Intearity 02( 91 The lic see shall implement a rogram to reduce leak e from systems outside contain nt that would or could c tain highly radioactiv luids during a serious transient o accident to as low as p cticallevels. This pro am shallinclude the

following

i i l

} 1. Provisions stablishing preventive aintenance and perio ' visual inspection re irements, and

2. Leak test require nts for each system a a frequency not to exceed refueling cycle intervals.

J l Am. 64 H. Deleted 1 03/19/81 (Open)

~

1.

i De\ere d

=

~

4 o m. a ..=aa w e Amendment 150 I

i

D 61CTf d DPR-29 l l (J. -

odine Monitorina

, Am ,

e licensee shall implement a prog m which will ensure the apability to accurately determine e airbome lodine conc ntration in vital area nder accident conditions. This p gram shall include th following:

1. Tral of personnel;

2. Procedures monitoring, and

( 3. Provisions for maintenance of smpling and ana ' sis e,q i ment.

Am.103 K. Deleted 12/15/87 jam. 4 L. Post Accident Samoling r 06/10/86 program will be establishe implemented, and m tained which will ensure]

I t capability to obtain and an ze reactor coolant, ra ioactive lodines and pa ulates in plant chimney eff ents, and containment tmosphere samples under cident conditions. The p ram shall include the llowing:

1. Tral g of personnel pdt.T6d for sampling and analysi and

2. Procedu ,

3. Provisions for maintenance of sampling and analysis equipment.

Am.128 4. This license is effective as of the date of issuance, and shall expire at midnight, 02QV91 December 14,2012.

t Date of issuance: December 14,1972 k nie guad amend opt 7 Amendment 150 l

l DPR-30 Am.12 D. Equalizer Valve Restriction d

-04/21/75 The valves in the equalizer piping between the recirculation loops shall be closed .l at all times during reactor operation. .l 1

Am.103 E. Physical Protection l' 06/09/88. The licensee shall fully implement and maintain in effect all provisions of the ]

j Commission approved physical security, guard training and qualification, and

safeguards contingency plans including amendments made pursuant to provisions )

of the Miscellaneous Amemdments and Search Requirements revisions of 10 CFR i j 73.55 (51 FR 27817 and 27822), and to the authority of 10 CFR 50.90 and 10 1 CFR 50.54(p). These plans, which contain Safeguards Information protected  :

under 10 CFR 73.21, are entitled: " Quad Cities Nuclear Power Station Security i Plan," with revisions submitted through January 14,1988; " Quad Cities Nuclear

Power Station Security Personnel Training and Qualification Plan," with revisions ,

submitted through October 29,1987; and " Quad Cities Nuclear Power Station i Safeguards Contingency Plan," with revisions submitted through Februa,y 16, 1984. Changes made in accordance with 10 CFR 73.55, shall be implemented in accordance with the schedule set forth therein, i

3 Am.136 F. Commonwealth Edison Company shall implement and maintain in effect all 05/13/93 provisions of the approved fire protection program as described in the Updated i Final Safety Analysis Report for the facility and as approved in the Safety ,

4

, Evaluation Reports dated July 27,1979 with supplements dated November 5, l' 1980 and February 12,1981; December 30,1982; December 1,1987 with "

! supplement dated April 20,' 1988; December 11,1987 with supplement dated July 21,1988; and February 25,1991, subject to the following provision:

l The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect ,

l

the ability to achieve and maintain safe shutdown in the event of a fire.

4

. Am. 58 G. Deleted

! 03/19/81 Am.[5 H. Systems Intearity ,

02.06/81 The licensee shall i lement a program to reduce lea ge from systems outsid c tainment that wou or could contain highly radioacts fluids during a serious tra lent or accident to low as practicallevels. This p ram shall include the 4

follow g:

i 1. Pro 'sions establishing ventive maintenance and peri ' visual ,

, inspe n requirements, a j l 2. Leak test requirements for each system at a frequency not to exceed l refueling cycle intervals. --

l 7 t umA )  :

1 k:ntaquad: amend.wpt:24 Amendment 146 I

J

--~ . _ .

. DPR-30

^

Am 6 1. lodine Monitoring 02/06/81 The licensee shall implement a prog m which will ensure

, the capability o accurately determine e airbome iodine concentration in vital areas under a ident conditions. This ogram shall include the following:

1. Training personnel;

2. Procedures r monitoring, and Provisions for intenance of sampling and' analysis equipment.

~

Am.95 J. Deleted 01/16/87 Amf95 K. Post Accident Semoling

@ /10/86 A program will be tablished, implemented, a maintained which ill ensure th]e capability to obtain a analyze reactor coolant, dioactive iodines a particulates in' plant chi ney effluents, and contain ent atmosphere sa pies under accident conditions. The program shall include e following:

1. Training of personnel

2. Pr edures for sampling an nalysis, and

3. Provisions for maintenance of samoling and analysis equipment.

Am.123 4. This license is effective as of the date of issuance, and shall 02/13/91 expire at midnight, December 14,2012.

/

Date of Issuance: December 14,1972 Od M k:nlaquadamend.wpf:25 Amendment 146

\

ATTACHMENT 5 QUAD CITIES 1/2 DIFFERENCES Technical Specification 6.0

" ADMINISTRATIVE CONTROLS" l

l l

l l

l l

l l

l l

i l

k:\nla\ quad \tsup\60_stt2.wpf l

l l

ATTACHMENT 5 COMPARISON OF QUAD CITIES UNIT 1 AND UNIT 2 TECHNICAL SPECIFICATIONS FOR THE IDENTIFICATION OF TECHNICAL DIFFERENCES l

Commonwealth Edison has conducted a comparison review of the Quad Cities 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 presentation style (e.g. table formats, use of capital letters, etc.), punctuation or spelling errors, but rather to identify areas which the Technical Specifications are technically or administratively different.

The review of Section 6.0 " Administrative Controls" did not reveal any technical differences, i

l I

i l

l I

k:\nla\ quad \tsup\60_at:2.wpf -1

ATTACHMENT 6 SIGNIFICANT HAZARDS CONSIDERATIONS AND ENVIRONMENTAL ASSESSMENT EVALUATION Technical Specification 6.0

" ADMINISTRATIVE CONTROLS" kAnla\ quad \tsup\M_at:2.wpf

ATTACHMENT 6 EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION  ;

Commonwealth Edison has evaluated this proposed amendment and determined that it involves ,

no significant hazards consideration. According to 10 CFR 50.92(c), a proposed amendment to i an operating license involves no significant hazards 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; or

2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or -

3) Involve a significant reduction in a margin of safety.

The' proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated because: ,

In general, the proposed amendment represents the conversion of current requirements to a  !

more generic format, or the addition of requirements which are based on the current safety analyses. Implementation of these changes will provide increased reliability of equipment  :

assumed to operate in the current safety analyses, or provide continued assurance that specified pa-ameters remain within their acceptance limits, and as such, will not significantly increase the probability or consequences of a previously evaluated accident. ,

i Some of the proposed changes represent minor cunailments of the current requirements which are based on generic guidance or previously approved provisions for other stations. The proposed amendment for Quad Cities Station's Technical Specification Section 6.0 are based on STS guidelines or later operating plant's NRC accepted changes. Any deviations from STS '

requirements do not significantly increase the probability or consequences of any previously evaluated accidents for Quad Cities Station. The proposed amendment is consistent with the i current safety analyses and has been previously determined to represent sufficient requirements j for the assurance and reliability of equipment assumed to operate in the safety analyses, or provide continued assurance that specified parameters remain within their acceptance limits. As such, these changes will not significantly increase the probability or consequences of a previously evaluated accident.

l l

k:\nla\ quad \uup\60_attiwpf 1 ,

1 I

ATTACHMENT 6 O

Create the possibility of a new or different kind of accident from any previously evaluated because:

In general, the proposed amendment represents the conversion of current requirements to a more generic format, or the addition of requirements which are based on the current safety analyses. Others represent minor curtailments of the current requirements which are based on generic guidance or previously approved provisions for other stations. These changes do not involve revisions to the design of the station. Some of the changes may involve revision in the operation of the station; however, these provide additional restrictions which are in accordance with the current safety analyses, or are to provide for additional testing or surveillances which will not introduce new failure mechanisms beyond those already considered in the current safety analyses.

The proposed amendment for Quad Cities Station's Technical Specification Section 6.0 is based on STS guidelines or later operating plants' NRC accepted changes. The proposed amendment has been reviewed for acceptability at the Quad Cities Nuclear Power Station considering similarity of system or component design versus the STS or later operating plants. Any deviations from STS requirements do not create the possibility of a new or different kind of accident previously evaluated for Quad Cities Station. No new modes of operation are introduced by the proposed changes. The proposed changes maintain at least the present level of operability. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.

Involve a significant reduction in the margin of safety because:

In general, the proposed amendment represents the conversion of current requirements to a more generic format, or the addition of requirements which are based on the  ;

current safety analyses. Others represent minor curtailments of the current requirements which are based on generic guidance or previously approved provisions for  !

other stations. Some of the later individual items may introduce minor reductions in the margin of safety when compared to the current requirements. However, other individual changes are the adoption of new requirements which will provide significant enhancement of the reliability of the equipment assumed to operate in the safety analyses, or provide enhanced assurance that specified parameters remain with their

acceptance limits. These enhancements compensate for the individual minor reductions, such that taken together, the proposed changes will not significantly reduce the margin of safety.

1 The proposed amendment to Technical Specification Section 6.0 implements present requirements, or the intent of present requirements in accordance with the guidelines set  !

fonh in the STS. Any deviations from STS requirements do not significantly reduce the margin of safety for Dresden or Quad Cities Station. The proposed changes are l intended to improve readability, usability, and the understanding of technical specification requirements while maintaining acceptable levels of safe operation. The proposed changes have been evaluated and found to be acceptable for use at Quad Cities based on system design, safety analyses requirements and operational performance.

Since the proposed changes are based on NRC accepted provisions at other operating plants that are applicable at Quad Cities and maintain necessary levels of system or component reliability, the proposed changes do not involve a significant reduction in the margin of safety.

kAnh\ quad \tsup\60_at:2.wpf

. - . . -= - .

ATTACHMENT 6 e

) ENVIRONMENTAL ASSESSMENT STATEMENT APPLICABILITY REVIEW

Commonwealth Edison has evaluated the proposed amendment against the criteria for the identification of licensing and regulatory actions requiring environmental assessment in  !

accordance with 10 CFR 51.20. It has been determined that the proposed changes meet the

criteria for a categorical exclusion as provided under 10 CFR 51.22 (c)(9). This conclusion has been determined because the changes requested do not pose significant hazards consideration or do not involve a significant increase in the amounts, and no significant changes in the types, of  ;

any effluent that may be released offsite. Additionally, this request does not involve a significant increase in individual or cumulative occupational radiation exposure. Therefore, the Environmental Assessment Statement is not applicable for these changes.

1 t

1  ;

a W

1 r

k:\nla\ quad \tsup\60,,attiwpf 3-