ML032400533
| ML032400533 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/22/2003 |
| From: | NRC/NRR/DLPM |
| To: | |
| Shared Package | |
| ML032370494 | List: |
| References | |
| Download: ML032400533 (18) | |
Text
3/4 LIMITING CONDITIONS FOR OPERATION-AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
- 3.
CONTAINMENT ISOLATION
- a. Phase "A" Isolation
- 1) Manual
--- See Functional Unit 9 ---------
- 2) FromSafety 2
1 2
1,2,3,4 13 Injection Automatic Actuation Logic
- b. Phase "B' Isolation
- 1) Manual
~
~
See Functional Unit9 -------------
- 2) AutomaticActuation 2
1 2
1,2,3,4 13 Logic
- 3) Containment 4
2 3
1, 2, 3 16 Pressure-High-High
- c. Purge and Exhaust Isolation
- 1) Mlanual
-- See Functional Unit 9-
- 2) Containment 3
1 2
1,.2,3, 4 17 Radioactivity-* High Train A (VRS-2101, ERS-2301, ERS-2305)
- 3) Containment 3
1 2
1, 2, 3,4 17 Radioactivity-* High Train B (VRS-2201, ERS-2401, ERS-2405)
- 'This specification only applies during PURGE.
COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-17 AMENDMENT 82, i, 261
-3/44 LIMFITNGCONDlTIONS FOR OPERATIONAND SRVEILL-ANCE REQUIREMENTS-3/4.3 INSTRUMENTATION I-TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TOTAL NO.
OF CHANNELS MINIMUM CHANNELS CHANNELS TO TRIP OPERABLE APPLICABLE MODES FUNCTIONAL UNIT ACTION
- e.
Steam Line Pressure-Low Four Loops Operating Three Loops Operating I pressurelloop I pressure/
operating loop 2 pressures any loops in# pressure in any operating loop I pressure any 3 loops I pressure in any 2 operating loops 1, 2, 3" 14*
3#
15
- 5. TURBINE TRIP &
FEEDWATER ISOLATION
- a. Steam Generator Water Level - High-High 3/loop 2/loop in any operating loop 2/loop in each operating loop 1,2,3 14*
- 6. MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS
- a. Steam Generator Water Level - Low-Low
- b. 4 kV Bus Loss of Voltage 3/Stm. Gen.
2/Stm. Gen.
any Stm. Gen.
2/Stm. Gen.
1,2,3 14*
14*
3/Bus 2/Bus 2/Bus 1,2,3 Pump Start Valve Actuation (Both trains) 2/bus (TMA -
Train B; T21D
- Train A) 2/bus on (T2IA
&T21Bor 2/busses T21C
& 771D)
I 2
2
- c.
Safety Injection
- d. Loss of Main Feedwater Pumps 2
1,2,3 1,2 18*
18*
2 2
AMENDMENT 92,4M, 4W, 261 COOK NUCLEAR PLANT-UNIT 2 Page 314 3-19
3/4 LIMiTING DONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TOTAL NO.
OF CHANNELS CHANNELS TO TRIP MUNIMUM CHANNELS OPERABLE APPLICABLE MODES FUNCTIONAL UNIT ACTION
- 7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS
- a. Steam Generator Water Level - Low-Low 3/Stn. Gen.
2/Stn. Gen. any 2 Stm. Gen.
2/Stm. Gen.
1,2,3 14*
- b. Reactor Coolant Pump Bus Undervoltage 4-l/Bus 2
3 1,2, 3 19*
- 8. LOSS OF POWER
- a. 4 kV Bus Loss of Voltage 3/Bus 2/Bus 2/Bus 1,2,3,4 14*
- b. 4 kV Bus Degraded Voltage 3/Bus M21A - Train B)
(T2 ID - Train A) 2/Bus (T2MA-Train B)
(T2ID-Train A) 2/Bus MIA-Train B)
(121ID-Train A) 1,2,3,4 14*
- 9. MANUAL
- a.
Safety Injection (ECCS)
Feedwater Isolation Reactor Trip (SI)
Containment Isolation-Phase "A" Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System
- b. Containment Spray Containment Isolation -
Phase "B" Containment Purge and Exhaust Isolation
- c. Containment Isolation -
Phase "A" Containment Purge and Exhaust Isolation 2/train l/train 2/train 1/train l/train 1,2,3,4 18 1,2,3,4 18 1,2,3,4 18 I/train I/train 1/train I/train
- d. Steam Line Isolation 2/steam line (I per train) 2/steam line (1 per train) 2/operating steam line (I per train) 1,2,3 20 COOKNUCLEARPLANT-UNIT2 Page 3/4 3-20 AMENDMENT U, 4O, +,
2i, 24, 261
314
_A
-IMMNG-QNDmONS FOR OPERATION-AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION
-1 TABLE 3.3-6 (Continued)
RADIATION MONITORING INSTRUMENTATION (OPERABILITY BASES DISCUSSED IN BASES SECTION 3/4 3.3.1)
MINIMUM CHANNELS OPERABLE ALARM TRIP SETPOINT SETPOINT OPERATION MODE/INSTRUMENT ACTION
- 2.
Mode 6 A. Train A
- i. Containment Area+
Radiation Channel (VRS 2101) ii. Particulate Channel+
(ERS 2301) any 2/3 channels 22 N/A N/A
< 54 mR/hr S 2.52 pCi iii. Noble Gas Channel+
(ERS 2305)
B. Train B
- i. Containment Area+
Radiation Channel (VRS 2201)
N/A
< 4.4x10 3 pCi cc any 2/3 channels 22 NIA S54 mRlhr ii. Particulate Channel+
(ERS 2401)
N/A S 2.52 gCi iii. Noble Gas Channel+
(ERS 2405)
N/A S4.4x10 3 pCi cc
- 3.
Mode ***
A. Spent Fuel Storage (RRC 330)
I
- 15 mR/hr
- 15 mR/hr 21
- With fuel in storage pool or building
+
This specification only applies during PURGE I
AMENDMENT 80, +1.9, M, 261 1 COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-35a
3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS -
3/4A REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:
- a.
Less than or equal to 1 microCurie per gram DOSE EQUIVALENT 1-1 31, and
- b.
Less than or equal to 100/ EmicroCuries per gram of gross radioactivity.
APPLICABILITY:
MODES 1, 2, 3, 4 and 5 ACTION:
MODES 1, 2 and 3
- a.
With the specific activity of the reactor coolant greater than 1 microCurie per gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in HOT STANDBY with Tavl less than 5000F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- b.
With the specific activity of the reactor coolant greater than 100/ E microCuries per gram, be in HOT STANDBY with Tavg less than 5000F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODES 1,2,3,4and5
- a.
With the specific activity of the reactor coolant greater than 1 microCurie per gram DOSE EQUIVALENT I-131 or greater than 100/ E microCuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the reactor coolant is restored to within its limits.
SURVEILLANCE REQUIREMENTS I
4.4.8 The specific activity of the reactor coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.44.
With Tvg greater than or equal to 5000F.
COOK NUCLEAR PLANT-UNIT 2 Page 3/4 4-20 AMENDMENT 4n, 261
3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE-REQUIREMENTS 3/4.7 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE when tested pursuant to Specification 4.0.5 by:
- a.
Verifying that each motor driven auxiliary feed pump's developed head at the test flow point is greater than or equal to the required developed head.
- b.
Verifying that the turbine driven auxiliary feedwater pump's developed head at the test flow point is greater than or equal to the required developed head. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
- c.
Verifying at least once per 31 days that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position.
- d.
Verifying at least once per 31 days that each automatic valve in the flow path is in the correct position whenever the auxiliary feedwater system is placed in automatic control or when above 10% RATED THERMAL POWER. This requirement is not applicable for those portions of the auxiliary feedwater system being used intermittently to maintain steam generator level.
I I
- e.
Verifying at least once per 18 months that each automatic valve in the flow path actuates to its correct position upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.
- f.
Verifying at least once per 18 months that each auxiliary feedwater pump starts as designed automatically upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.
- g.
Verifying at least once per 18 months that the unit cross-tie valves can cycle full travel.
Following cycling, the valves will be verified to be in their closed positions.
COOK NUCLEAR PLANT-UNIT 2 Pa-e 3/4 7-6 AMENDMENT X,
, 4, 4,
49, S, 49, 48, 2O, 2A, 2, 261
3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
- d.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by either:
- 1.
Verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister shows a penetration of less than or equal to 1.0% for radioactive methyl iodide when the sample is tested in accordance with ASTM D3803-1989, 300C, 95% R.H; or
- 2.
Verifying within 31 days after removal that a laboratory analysis of at least two carbon samples shows a penetration of less than or equal to 1.0% for radioactive methyl iodide when the samples are tested in accordance with ASTM D3803-1989, 300C, 95% R.H. and the samples are prepared by either:
a)
Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or b)
Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.
Subsequent to reinstalling the adsorber tray used for obtaining the carbon sample, the system shall be demonstrated OPERABLE by also:
a)
Verifying that the charcoal adsorbers remove 2 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm +/- 10%, and b)
Verifying that the HEPA filter banks remove 2 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm +/- 10%.
COOK NUCLEAR PLANT-UNIT 2 Page 3/4 7-16 AMENDMENT 2A, 261
-3/4-----LIMITNG CONDIMIONS FOR OPER-A-TIONANI) SURVEILLANCEREQIREMENTS 3/4.8 ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) a)
A kinematic viscosity of greater than or equal to 1.9 centistokes but less than or equal to 4.1 centistokes at 400C (alternatively, Saybolt viscosity, SUS at 1000F of greater than or equal to 32.6 but less than or equal to 40.1), if gravity was not determined by comparison with supplier's certification.
b)
A flash point equal to or greater than 1250F.
- 2)
By verifying, in accordance with the test specified in ASTM D1298-80 and prior to adding the new fuel to the storage tanks, that the sample has either an API gravity of greater than or equal to 30 degrees but less than or equal to 40 degrees at 600F or an absolute specific gravity at 60/600F of greater than or equal to 0.82 but less than or equal to 0.88, or an API gravity of within 0.3 degrees at 600F when compared to the supplier's certificate or a specific gravity of within 0.0016 at 60/600F when compared to the supplier's certificate.
- 3)
By verifying, in accordance with the test specified in ASTM D4176-82 and prior to adding new fuel to the storage tanks, that the sample has a clear and bright appearance with proper color.
- 4)
By verifying within 31 days of obtaining the sample that the other properties specified in Table 1 of ASTM D975-81 are within the appropriate limits when tested in accordance with ASTM D975-81 except that the analysis for sulfur may be performed in accordance with ASTM D2622-82.
- d.
At least once per 31 days by obtaining a sample of fuel oil from the storage tanks in accordance with ASTM D2276-83, and verifying that total particulate contamination is less than 10 mg/liter when tested in accordance with ASTM D2276-83, Method A*.
- e.
At least once per 18 months, during shutdown, by:
- 1.
Subjecting the diesel engine to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service, The actions to be taken should any of the properties be found outside of the specified limits are defined in the Bases.
COOK NUCLEAR PLANT-UNIT 2 Page 314 8-4 AMENDMENT +ia, U9, 261
3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.9 REFUELING OPERATIONS STORAGE POOL VENTILATION SYSTEM**
LIMITING CONDITION FOR OPERATION 3.9.12 The spent fuel storage pool exhaust ventilation system shall be OPERABLE.
APPLICABILITY:
Whenever irradiated fuel is in the storage pool.
ACTION:
- a.
With no fuel storage pool exhaust ventilation system OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE status.*
I
- b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.9.12 The above required fuel storage pool ventilation system shall be demonstrated OPERABLE:
- a.
At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.
- b.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:
- 1.
Deleted.
- 2.
Verifying that the charcoal adsorbers remove 2 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfm +/- 10%.
The crane bay roll-up door and the south door of the auxiliary building crane bay may be opened under administrative control during movement of fuel within the storage pool or crane operation with loads over the storage pool.
Shared system with D. C. COOK - UNIT 1.
I COOK NUCLEAR PLANT-UNIT 2 Page 3/4 9-12 AMENDMENT +14,,V4, 261
5.0 ADMINISTRAT1VECONTROLS -
5.6 FUEL STORAGE (Continued) 5.6.2 The new fuel storage racks are designed and shall be maintained with:
- a.
Westinghouse fuel assemblies having either a maximum enrichment of 4.55 weight % U-235, or an enrichment between 4.55 and 4.95 weight % U-235 with the minimum number of integral fuel burnable absorber pins as shown on Figure 5.6-4 (interpolation of the Boron-10 loading between L.OX and 1.5X and 2.OX is acceptable);
- b.
kff < 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.7 of the UFSAR; C.
kff < 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.7 of the UFSAR; and
- d.
A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.
DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 629'4".
CAPACITY 5.6.4 The spent fuel storage pool is designed and shall me maintained with a storage capacity limited to no more than 3613 fuel assemblies.
I COOK NUCLEAR PLANT-UNIT 2 Page 5-9 AMENDMENT A, 443, 4,452,86, 408,220, 261
6.0 -
-ADMINISTRATIVE CONTROLS - - --
6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Shift Manager (or during his absence from the control room complex, a designated individual) shall be responsible for the control room command function. A management directive to this effect signed by the Site Vice President shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION ONSITE AND OFFSITE ORGANIZATIONS 6.2.1 Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.
The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
- a.
Lines of authority, responsibility, and communication shall be established and defined for the highest management level through intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organizational charts. These organizational charts will be documented in the UFSAR and updated in accordance with 10 CFR 50.71(e).
- b.
The Plant 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.
- c.
The Senior Vice President - Nuclear Operations 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.
- d.
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.
COOK NUCLEAR PLANT-UNIT 2 Page 6-1 AMENDMENT 58, 447, 43, M, 49, 261
6.0 ADMINISTRATIVE CONTROILS 6.2 ORGANIZATION (Continued)
FACILITY STAFF 6.2.2 The Facility organization shall be subject to the following:
- a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
- b.
At least one licensed Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in Mode 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room.
- c.
An individual* qualified in radiation protection procedures shall be on site when fuel is in the reactor.
- d.
All CORE ALTERATIONS shall be directly supervised by a licensed Senior Operator trained or qualified in refueling and CORE ALTERATIONS (SO-CA) who has no other concurrent responsibilities during this operation.
- e.
The amount of overtime worked by plant staff members performing safety-related functions must be limited in accordance with NRC Policy Statement on working hours (Generic Letter 82-12).
- f.
The Shift Manager and Unit Supervisor shall hold a Senior Operator License.
- g.
The Operations Director must hold or have held a Senior Operator License at Cook Nuclear Plant or a similar reactor, or have been certified for equivalent senior operator knowledge. If the Operations Director does not hold a Senior Operator License, then a line (v. staff) operations middle manager shall hold a Senior Operator License for the purposes of directing operational activities.
The unexpected absence, for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, of the on-site individual qualified in radiation protection procedures is permitted provided immediate action is taken to fill the required position.
I COOK NUCLEAR PLANT-UNIT 2 Page 6-2 AMENDMENT 7a, 44I, 1, 492,497,261
6.0 ADMINISTRATIVE CONTROLS--
TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION*
LICENSE CATEGORY APPLICABLE MODES
_1,2,3&4 5&6 SM 1**
I**'
SOL I
None OL 2
1 Non-Licensed 2
1 Shift Technical Adv.
1**
None I
Does not include the licensed Senior Operator - CA supervising CORE ALTERATIONS.
Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
Shared with Cook Nuclear Plant Unit I COOK NUCLEAR PLANT-UNIT 2 Page 6&3 AMENDMENTQ,+rt,4m, 261
6.0 ADMINISTRATIVE CONTROLS --
6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) 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 and, (3) the Operations Director, who must be qualified as specified in Section 6.2.2.g.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.
6.5 DELETED COOK NUCLEAR PLANT-UNIT 2 Page 6-4 AMENDMENT 4, 14, 438, 4, 48, COOK NUCLEAR PLANT-UNIT 2 Page 6-4 AMENDMENT-34,4-1;,+38,4;12,+78, 49;, m, am, 261
6.0 ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
- a.
The Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.73.
- b.
Each REPORTABLE EVENT shall be reviewed by the PORC, and the results of this review shall be submitted to the NSRB and the Site Vice President.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:
- a.
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 Chairman of the NSRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- b.
A Safety Limit Violation Report shall be prepared. This report shall be reviewed by the PORC.
The report shall describe (1) applicable circumstances preceding the violation; (2) effects of the violation upon facility components, systems or structures; and (3) corrective action taken to prevent recurrence.
- c.
The Safety Limit Violation Report shall be submitted to the Commission, the Chairman of the NSRB and the Senior Vice President - Nuclear Operations within 14 days of the violation.
- d.
Operation of the unit shall not be resumed until authorized by the Commission.
COOK NUCLEAR PLANT-UNIT 2 Page 6-5 AMENDMENT 3, 438, S, iq8, *,
261
6.0 ADMINISTRATIVE CONTROLS-MONTHLY REACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITS REPORT 6.9.1.9.1 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:
- a.
Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4,
- b.
Rod Drop Time Limits for Specification 3/4.1.3.4,
- c.
Shutdown Rod Insertion Limits for Specification 3/4.1.3.5,
- d.
Control Rod Insertion Limits for Specification 3/4.1.3.6,
- e.
Axial Flux Difference for Specification 3/4.2.1,
- f.
Heat Flux Hot Channel Factor for Specification 3/4.2.2,
- g. Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and
- h.
Allowable Power Level for Specification 3/4.2.6.
6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:
- a.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology,"
July 1985 (Westinghouse Proprietary),
- b.
WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report,"
September 1974 (Westinghouse Proprietary),
- c.
WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control/FQ Surveillance Technical Specification," February 1994 (Westinghouse Proprietary),
- d. WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).
- e.
`VANTAGE+ Fuel Assembly Reference Core Report," July 1991 (Westinghouse Proprietary).
COOK NUCLEAR PLANT-UNIT 2 Page 6-12 AMENDMENT A, I, I5, S,
0, Au, 261
6.0 ADM1NISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM 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.
6.12 HIGH RADIATION AREA 6.12.1 Pursuant to 10 CFR 20.1601(c), in lieu of the requirements of 10 CFR 20.1601(a) and (b), each high radiation area in which radiation levels from radiation sources external to the body could result in an individual receiving a dose equivalent in excess of 100 mrem but less than or equal to 1000 rnrem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm from the radiation source or 30 cm from any surface that the radiation penetrates, 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. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
- a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
- b.
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 level in the area has been established and personnel have been made aware of it.
- c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Plant Radiation Protection Manager in the Radiation Work Permit.
6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which the radiation level at 30 cm from the radiation source or 30 cm from any surface that the radiation penetrates is greater than 1000 mrem in I hour. When possible, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative control of the Shift Manager on duty and/or the Plant Radiation Protection Manager. Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the inmmediate work areas. In the event that it is not possible or practicable to provide locked doors due to area size or configuration, the area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.
Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
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6.0 ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 Changes to the PCP:
- a.
Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Description, Appendix C, Section 6.10.2.n. This documentation shall contain:
- 1.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and
- 2.
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.
- b.
Shall become effective after review and acceptance by the PORC and the approval of the Plant Manager.
6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 Changes to the ODCM:
- a.
Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Description, Appendix C, Section 6.10.2.n. This documentation shall contain:
- 1.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and
- 2.
A determination that the change will maintain the level of radioactive effluent control pursuant to 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.
- b.
Shall become effective after review and acceptance by the PORC and the approval of the Plant Manager.
- c.
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 Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each 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.
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