ML17324A884
| ML17324A884 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/22/1986 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17324A885 | List: |
| References | |
| NUDOCS 8605090401 | |
| Download: ML17324A884 (59) | |
Text
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 0
INDIANA AND MICHIGAN EL'ECTRIC COMPANY'OCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applicatio'n for amendment by Indiana and Michi'gan Electric Company (the licensee) dated January 21, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment
'can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No.
DPR-58 is hereby amended to read as follows:
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(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
94, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The change in Technical Specifications is to become effective within 30 days of issuance of the amendment.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensee shall adhere to the Technical Specifications for the systems, components, or operation existing at the time.
The period of time during changeover of systems, components or operation shall be minimized or compensated for by suitable temporary alternatives.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
April. 22, 1986
~
B. J.
Youngbl ood, Director PWR Project Directorate ¹4 Division of PWR Licensing-A, NRR
I( '
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
94
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The change in Technical Specifications is to become effective within 30 days of issuance of the amendment.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensee shall adhere to the Technical Specifications for the systems, components, or operation existing at the time.
The period of time during changeover of systems, components or operation shall be minimized or compensated for by suitable temporary alternatives.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance: April 22, 1986 B. J.
Youngbl ood, Director PWR Project Directorate ¹4 Division of PWR Licensing-A, NRR PWR¹4:DPWR-A DWig inton:mac 04/
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(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 78
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The change in Technical Specifications is to become effective within 30 days of issuance of the amendment.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensee shall adhere to the Technical Specifications for the systems, components, or operation existing at the time.
The period of time during changeover of systems, components or operation shall be minimized or compensated for by suitable temporary alternatives.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 22, 1986 B. J.
Youngblood, Director PWR Project Directorate ¹4 Division of PWR Licensing-A, NRR PWR¹4.
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2
'AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 8o License No.
DPR-74 l.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated January 21, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comnission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is 'in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended-by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No.
DPR-74 is hereby amended to read as follows:
(2)
Technical S eci ficati ons The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 80
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The change in Technical Specifications is to become effective within 30 days of issuance of the amendment.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensee shall adhere to the Technical Specifications for the systems, components, or operation existing at the time.
The period of time during changeover of systems, components or operation shall be minimized or compensated for by suitable temporary alternatives.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 22, 1986 B. J.
Youngblood, Director PWR Project Directorate 84 Division of PWR Licensing-A, NRR
g, ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.
94 AMENDMENT NO.
SO FACILITY OPERATING LICENSE NO.
DPR-58 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NOS. 50-315 AND 50-316 Revise Appendix A,as follows:
Remove Pa es 3/4;~
3/4 3-26 3/4 3-36 W Ot 3/4 3-37 3/4 3-38 3/4 3-58 3/4 3-63 3/4 3-64 3/4 3-66 3/4 3-67 3/4 11-8 3/4 12-3 B3/4 3-1 B3/4 3-la B3/4 3-lb B3/4 3-lc B3/4 3-2 B3/4 11-1 B3/4 11-2 6-21 UNIT 2 3~~
3/4 3-24 3/4 3-35 W
WW 3/4 3-36 3/4 3-37 W
3/4 3-54 3/4 3-59 3/4 3-60 3/4 3-62 3/4 3-63 3/4 11-8 3/4 12-3 B3/4 3-1 W 0 B3/4 11-1 83/4 11-2 6-21 Insert Pa es 3/4 3-19 3/4 3-26 3/4 3-36 3/4 3-36a 3/4 3-36b 3/4 3-37 3/4 3-38 3/4 3-38a 3/4 3-38b 3/4 3-58 3/4 3-63 3/4 3-64 3/4 3-66 3/4 3-67 3/4 11-8 3/4 12-3 B3/4 3-1 B3/4 3-la B3/4 3-lb B3/4 3-lc B3/4 3-2 B3/4 11-1 B3/4 11-2 6-21 3/4 3-18 3/4 3-24 3/4 3-35 3/4 3-35a 3/4 3-35b 3/4 3-36 3/4 3-37 3/4 3-37a 3/4'-37b 3/4 3-54 3/4 3-59 3/4 3-60 3/4 3-62 3/4 3-63 3/4 11-8 3/4 12-3 B3/4 3-1 B3/4 3-la 83/4 3-lb B3/4 3-lc B3/4 11-1 B3/4 11-2 6-21
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO.
OF CHANNELS MINIMUM CHANNELS CHANNELS APPLICABIE TO TRIP OPERABLE MODES ACTION 3
CONTAINMENT ISOLATION a.
Phase "A" Isolation
- 1) Manual
- 2) From Safety Injection Automatic Actuation Logic 1,2,3,4 1,2,3,4 18 13 b.
Phase "B" Isolation
- 1) Manual
- 2) Automatic Actuation Logic
- 3) Containment Pressure-High-High 1,2,3,4 1,2,3,4 1I2I3 18 13 16 c.
Purge and Exhaust Isolation*
- 1) Manual
- 2) Containment Radioactivity-High Train A (VRS-1101, ERS-1301, ERS-1305)
- 3) Containment Radioactivity-fligh Train B (VRS 1201~
ERS 1401'RS 1405) 1,2,3,4 1,2,3,4 1,2,3,4 17 17 17
- This specification only applies during purge.
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SFTPOINTS O
FUNCTIONAL UNIT 8
I C
2.
Containment Radioactivity High Train A (VRS-1101, ERS-1301, ERS-1305)
TRIP SETPOINT See Table 3.3-6 ALLOWABLE VALUES Not Applicable 3.
Containment Radioactivity-fligh Train B (VRS-1201, ERS-1401, ERS-1405)
See Table 3.3-6 Not Applicable 4.
STEAM LINE ISOLATION a ~
Manual b.
Automatic Actuation Logic c.
Containment Pressure High-High Not Applicable Not Applicable S 2.9 psig Not Applicable Not Applicable
~ 3 psig d.
Steam Flow In Two Steam Lines High Coincident with Tave Low-Low or Steam Line Pressure Low
- 4. 1.42 x 10 lbs/hr from 0%
6 load to 2N)%, load.
Linear from 1.42 x 10 lgs/hr at 20% load to 3.88 x 10 lbs/hr at 100K load.
T 541 F
avg 600 psig steam line pressure c 1.56 x 30 lbs/hr from 0%
6 load to 20% logd.
Linear from 1.56 x 10 lbs/hg at 20~ load to 3.93 x 10 lbs/
hr at 100% load.
T 539 F
avg 2 580 psig steam line pressure 5
TURBINE TRIP AND FEEDMATER ISOLATION a.
Steam Generator Mater Level--
High-High 67% of narrow-range instrument span each steam generator
~ 68% of narrow-range instrument span each steam generator
TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION (OPERABILITY BASES DISCUSSED IN BASES SECTION 3/4.3.3.1)
OPERATION MODE/INSTRUMENT MINIM/M OPERA CHANNELS BLE ALARM SETPOINT TRIP SETPOINT ACTION 1.
Modes 1, 2, 3, 6 4 A)
Area Monitors i) Upper Containment (VRS 1101/1201)
N/A C 54 mR/hr 21 B)
Process Monitors i)
Particulate Channel (ERS 1301/1401)
N/A 2.52 uCi 20 ii) Noble Gas Channel (ERS 1305/1405)
N/A 4.4 x 10 uCi CC 20 C)
Noble Gas Effluent Monitors i)
Unit Vent Effluent Monitor a)
Low Range (VRS 1505)
(See T/S Section 3.3.3.10)
TABLE 3.3-6 (Cont'd)
RADIATION MONITORING INSTRUMENTATION (OPERABILITY BASES DISCUSSED IN BASES SFCTION 3/4.3.3.1) n 8
OPERATION MODE/INSTRUMENT MINIMUM CHANNELS OPERABLE ALARM SETPOINT TRIP SETPOINT ACTION RM ii)
Gland Steam Condenser Vent Monitor a)
Low Range (SRA 1805)
(See T/S Section 3.3.3.10) iii) Steam Jet Air Ejector Vent Monitor a)
Low Range (SRA 1905)
(See T/S Section 3.3.3.10) 0 0
2.
Mode 6 A)
Train A i)
Containment Area Radiation Channel (VRS 1101)
+
ii)
Particulate Channel (ERS 1301) iii)
Noble Gas Channel (ERS 1305)
B)
Train B i)
Containment Area Radiation Channel (VRS 1201) ii)
Particulate Channel (ERS 1401) any 2/3 channels any 2/3 channels N/A N/A N/A N/A N/A C 54 mR/hr
+ 2.52 uCi 4.4 x 10 uCi 3
~ 54 mR/hr 2.52 uCi 22 22
TABLE 3.3-6 (Cont'd)
O 8
I C
OPERATION MODE/INSTRUMENT
+
iii)
Noble Gas Channel (ERS 1405)
MINIMUM CHANNELS OPERABLE ALARM SETPOINT N/A RADIATION MONITORING INSTRUMENTATION (OPERABILITY BASES DISCUSSED IN BASES SECTION 3/4.3.3.1)
TRIP SETPOINT
~ 4.4 x 10 uCi CC ACTION 22 3.
Mode ***
A) Spent Fuel Storage (RRC-330) 15 mR/hr C
15 mR/hr 21 e *** With fuel in storage pool or building.
+
This specification applies only during purge.
0
TABLE 3.3-6 (Continued)
TABLE NOTATION ACTION 20 With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, comply with the ACTION requirements of Specification 3.4.6.1.
ACTION 21 -
With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per day.
ACTION 22 -
With the number of channels OPERABLE less than required by the Minimum Channels Operable requirements, comply with the ACTION requirements of Specification 3.9.9.
This ACTION is not required during the performance of containment integrated leak rate test.
D. C.
COOK - UNIT 1 3/4 3-37 Amendment.No.
94
TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS OPERATION MODE/INSTRUMENT CHANNEL CHECK CHANNEL CALIBRAT ON CHANNEL FUNCTIONAL TEST MODES FOR WHICH SURVEILLANCE RE UIRED 1.
Modes 1, 2, 3, a
4 A)
Area Monitors i) Upper Containment (VRS 1101/1201) 1, 2, 3, 4
B)
Process Monitors i) Particulate Channel (ERS 1301/1401)
S*
1, 2, 3, 4
ii) Noble Gas Channel (ERS 1305/1405) 1, 2, 3, 4
C)
Noble Gas Effluent Monitors i) Unit Vent Effluent Monitors a)
Low Range (VRS 1505)
(See Table 4.3-9, Item 3.a, 4a, 5a)
TABLE 4. 3-3 (Cont.'d)
RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RF. UIREMENTS OPERATION MODE/INSTRUMENT CHANNEL CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES FOR WHICH SURVEILLANCE REQUIRED ii) Gland Steam Condenser Vent Monitor a)
Low Range (SRA 1805)
(See Table 4.3-9 Item 6.a) iii) Steam Jet Air Ejector Vent Monitor a)
Low Range (SRA 1905)
(See Table 4.3-9, Item 2.a) 2.
Mode 6 A)
Train A i) Containment Area Radiation Channel (VRS 1101)
S*
ii) Particulate Channel (ERS 1301)
S*
iii) Noble Gas Channel (ERS 1305)
S*
B)
Train B i) Containment Area Radiation Channel (VRS 1201)
S*
ii) Particulate Channel (ERS 1401)
S*
TABLE 4.3-3 (Cont'd)
RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS O
8 I
OPERATION MODE/INSTRUMENT H
iii) Noble Gas Channel (ERS 1405)
CHANNEL'HECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES FOR WHICH SURVEILLANCE RE UIRED 2.
Mode**
A) Spent Fuel Storage (RRC-330) g' To include SOURCE CHFCK per T/S Section 1.27.
- With fuel in storage pool or building.
0
~ IT
~
TABLE 3. 3-12 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION Instrument
- 1. Gross Radioactivity Monitors Providing Automatic Release Termination Minimum Channels
~Oezeh le Applicabilit Acticc
- a. Liquid Radwaste Effluent Line (1-R-18)
At times of release 23 b.
Steam Generator Blowdown Line (1-R-19)
At times of release 24 c.
Steam Generator Blowdown Treatment Effluent (1-R-24)
At times of release 24
- 2. Gross Radioactivity Monitors Not Providing Automatic Release Termination
- a. Service Water System Effluent Line (1-R-20, 1-R-28)
- 3. Continuous Composite Sampler Flow Monitor (1) per train At a'1 times 25
- a. Turbine Building Sump Effluent Line At all times 25
- 4. Flow Rate Measurement Devices
- a. Liquid Radwaste Line(RFI-285)
- b. Discharge Pipes*
c.
Steam Generator Blowdown Treatment Effluent (1-DFI-353)
At times of release At all times At times of release 26 NA 26
- Pump curves and valve settings may be utilized to estimate flow; in such cases, Action Statement 26 is not applicable.
D. C.
COOK - UNIT 1 3/4 3-58 Amendment No.
94
TABLE 3.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation Instrument (Instrument I) 1.
Waste Gas Holdup System Explosive Gas Monitoring System a.
Hydrogen Monitor (QC-31)
- b. Oxygen Monitor (QC-31, QC-370)
Minimum Channels
~actable (1)
(2)
A licabilit Action 30 29 2.
Condenser Evacuation System
- a. Noble Gas Activity Monitor (SRA-1905)
- b. Flow Rate Monitor (SFR-401)
(1-MR-0543 and/or SRA-1910)
(1)
(1)
(1) 28 27 27 3.
Unit Vent, Auxiliary Building Ventilation System
- a. Noble Gas Activity Monitor (VRS-1505)
- b. Iodine Sampler Cartridge for VRS-1503
- c. Particulate Sampler Filter for VRS-1501
- d. Effluent System Flow Rate Measuring Device (VFR-315)
(1-MR-054 and/or VRS-1510)
- e. Sampler Flow Rate Measuring Device (VFS>>1521) 28 32 32 27 27 27 4.
Containment Purge System
- a. Aux. Building Vent. System Noble Gas Activity Monitor (VRS-150S)
- b. Aux. Building Vent. System Particulate Sampler for VRS-1501 31 32 5.
Waste Gas Holdup System a; Noble Gas Activity Monitor Providing Alarm and Termination of Gas Decay Tank Releases (VRS-1505) 33 6.
Gland Seal Exhaust
- a. Noble Gas Activity Monitor (SRA-1805)
- b. Flow Rate Monitor (SFR-201)
(1-MR-054 and/or SRA-1810)
D. C.
COOK - UNIT 1 (1)
(1)
(1) 3/4 3-63 l***
28 27 27 Amendment No.
9p
TABLE 3.3-13 (Cont)
At all times During waste gas holdup system operation (treatment for primary system gases)
- During releases via this pathway.
1 For purge purposes orly.
See Technical Specifications 3.3.3.10, Table 3.3-13 and Table 4.3-9 (Items 3a, 5a) for other requirements associated with this instrument.
2 For gas decay tank releases only, see Item 3 (Unit Vent, Auxiliary Building Ventilation System) for additional requirements.
D. C.
COOK - UNIT 1 3/4 3-64 Amendment No. 94
TABLE 4.3-9 Radioactiv'e Gaseous Effluent Monitoring Instrumentation Surveillance Re uirements Instrument (Instrument I)
Channel Check Source Check Channel Calibration Channel Functional Test
- 1. Waste Gas Holdup System Explosive Gas Monitoring System a.
Hydrogen Monitor (QC-31) b.
Oxygen Monitor (QC-31)
- c. Oxygen Monitor (Alt. (QC-370)
D***
NA NA NA Q(3)
Q(4)
Q(4)
- 2. Condenser Evacuation System
- a. Noble Gas Activity Monitor (SRA-1905) b.
System Effluent Flow Rate (SFR-401, 2-MR-054, SRA-1910)
D**
D**
NA R(2)
Q (1)
- 3. Auxiliary Building Ventilation System
- a. Noble Gas Activity Monitor (VRS-1505)
- b. Iodine Sampler (For VRS>>1505)
- c. Particulate Sampler (For VRS-1501)
- d. System Effluent Flow Rate Measurement Device (VFR-315, 2-MR-054, VRS-1510) e.
Sampler Flow Rate Measurement Device (VFS-1521)
D%
DA D*
NA NA NA R(2)
NA Q(1)
NA NA
- 4. Containment Purge System a.
Aux. Building Vent. System Noble Gas Activity D**
Monitor (VRS-1505)
- b. Aux. Building Vent. System Particulate Sampler W**
(For VRS-1501)
R(2)
NA Q(5)
NA
- 5. Waste Gas Holdup System
- a. Noble Gas Activity'onitor Providing Alarm & Termination of Gas Decay Tank Release (VRS-1505)
D. C.
COOK - UNIT 1 3/4 3-66 R(2)
Q(5)
Amendment No.
94
TABLE 4. 3-9 (Cont)
Instrument (Instrument 0)
Channel Check Source Check Channel Calibration Channel Functional Test
- 6. Gland Seal Exhaust a.
Noble Gas Activity (SRA-1805)
- b. System Effluent Flow Rate (SFR 201i 1
D**
D**
NA R (2)
Q(1)
At all times
- During release via this pathway
- During waste gas holdup system operation (treatment for primary system offgases)
D. C.
COOK - UNIT 1 3/4 3-67 Amendment No. 94
TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Type Frequency Minimum Analysis Frequency Type of Activity Analysis Lower Limit-of Detection (uci/ml)
P Each Tank a.
Waste Gas Storage Tank Grab Sample P
Each Tank Principal Gamma Emitters e Principal Gamma e
Emitters 1
X 10 1
X 10 b.
Containment Purge Each Purge b
Grab Sample Each b Purge H-3 1 X 10 c.
Condenser Evacuation System and Gland Seal Exhaust*
W Grab b
Sample M
Particulate Principal Gamma Sample Emitters e H-3 1 X 10 1
X 10 M
Iodine Adsorbing/
Media I-131 1
X 10 d
Continuous Noble Gas Monitor Noble Gases 1
X 10 d.
Auxiliary Building Vent Continuous d W
Media 1X10 d
Continuous W
Particulate Sample Principal Gamma Emitters e 1X10 Continuous d M
Composite Particulate Sample Gross Alpha 1X10 Continuous d M
Composite H>>3 1X10 d
Continuous Q
Composite Particulate Sample Sr-89, Sr-90 1X10 d
Continuous Noble Gas Monitor Noble Gases 1 X 10
- As equipment becomes operational D. C.
COOK - UNIT 1 3/4 11-8 Amendment No.9p
TABLE 3. 12-1 RADIO ICAL ENVIRONMENTAL MONITORING OGRAM Exposure Pathway
~/
- l. Airborne
- a. Radioiodine
& Particulates Sam le Locations Al-A6 (Site)
New Buffalo South Bend,
- Dowagiac, and Coloma are
Background
Sampling and Collection Fre enc Continuous operation of sampler with Sample Collection as required by Dust Loading but at least once per 7 days Type
& Frequency of Anal sis Radioiodine canister Analyze:
Weekly for I-131 Particulate sample Gross Beta Rad-ioactivity following Filter Change a composite (by loca-tion) for gamma isotopic quarterly
- 2. Direct Radiation a) Tl-T9 (Site) b)
New Buffalo South Bend Dowagiac Coloma At least once per 92 days Gamma Dose. At least once per 92 days
.c) 10 TLD Monitor Locations in the Five Mile Radius
- 3. Waterborne
- a. Surface Ll, L2, L3 Composite sample over one-month period Gamma Isotopic Analysis monthly.
Composite for tritium analysis-quarterly.
- b. Ground Wl-Wj Quarterly Gamma Isotopic and Tritium analysis quarterly.
- c. Drinking St. Joseph Lake Township Composite sample collected over a period of~31 days Composite sample over a 2-week period if I-131 analysis is performed Gross Beta and Gamma Isotopic Analysis of each composite sample.
Tritium Analysis of composite Quarterly.
I-131 analysis on each composite when the dose calculated for the consumption of the water is greater than 1 mrem per year.
- Composite samples shall be collected by collecting an aliquot at intervals not exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D C.
COOK - UNIT 1 3/4 12-3 Amendment No. 94
3/4. 3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGZNEERED SAFETY FEATURES (ESF)
INSTRUMENTATION The OPERABILITY of the protective and ESF instrumentation systems and interlocks ensure that
- 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint,
- 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and
- 4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundancy and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.
The irtegrated operation of each of these systems is consistent with the assumptions used in the accident analyses.
The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards.
The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.
The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses.
No credit was taken in the analyses for those channels with response times indicated as not applicable.
Response
time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined.
Sensor response time verification may be demonstrated by either
- 1) in place, onsite or offsite test measurements or
- 2) utilizing replacement sensors with certified response times.
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3 1
RADIATION MONITORING INSTRUMENTATZON The OPERABZLITY of the radiation monitoring channels ensures that
- 1) the radiation levels are continually measured in the areas served by the individual channels and
- 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
D. C.
COOK - UNIT 1 B 3/4 3-1 Amendment No.94
INSTRUMENTATION BASES Radiation Monitoring Instrumentation (Continued)
Table 3.3-6 is based on the following Alarm/Trip Setpoints and Measurement Ranges for each instrument listed.
INSTRUMENT 1)
Area Monitor-Upper Containment (VRS 1101/1201)
ALARM/TRIP SETPOINT The monitor trip setpoint is based on 10 CFR 20 limits.
A homogeneous mixture of the containment atmosphere is assumed.
The setpoint value is defined as the monitor reading when the purge is operating at the maximum flow rate.
MEASUREMENT RANGE*
-4 10 R/hr to 10R/hr.
2)
Process Monitor Particulate (ERS 1301/1401) 3).
Process Monitor Noble Gas (ERS 1305/1405)
-4 The monitor trip setpoint 1.5 x 10 uCi to 7.5 is based on 10 CFR 20 uCi.
The setpoint was determined using the Noble gas setpoint and historical monitor data of the ratio of particulates to Noble gases.
-7 The-monitor trip setpoint 1 x 10 2 uCi/cc to is based on 10 CFR 20 4 x 10 uCi/cc limits.
A homogeneous mixture of the containment atmosphere is assumed.
The setpoint value is defined as the monitor reading when the purge is operating at the maximum flow rate.
- This is the minimum required sensitivity of the instrument.
Indicated values on these instruments above or below these minimum sensitivity ranges are acceptable and indicate existing conditions not instrument inoperability.
D. C.
COOK - UNIT 1 B 3/4 3-la Amendment No.
9C,
INSTRUMENTATION BASES Radiation Monitoring Instrumentation (Continued)
INSTRUMENT ALARM/TR1P SETPOINT MEASUREMENT RANGE*
4)
Noble Gas Unit Vent Monitors a)
Low Range (VRS 1505)
See Bases Section 3/4.3.3.10
-7
-2 lx10 uCi/cc to 4x10 uCi/cc.
, 5)
Gland Steam Condenser Vent Noble Gas Monitor a)
Low Range (SRA 1805) 6)
Steam Jet Air Ejector Vent Noble Gas Monitor a)
Low Range (SRA 1905)
See Bases Section 3/4.3.3.10 See Bases Section 3/4.3.3.10
-7
-2 lx10 uCi/cc to 4x10 uCi/cc.
-7
-2 lx10 uCi/cc to 4x10 uCi/cc.
- This is the minimum required sensitivity of the instrument.
Indicated values on these instruments above or below these minimum sensitivity ranges are acceptable and indicate existing conditions not instrument inoperability.
D.
Co COOK - UNIT 1 B 3/4 3-lb Amendment No.
94
INSTRUMENTATION BASES Radiation Monitorin Instrumentation (Continued)
INSTRUMENT 7)
Spent Fuel Storage (RRC-330)
ALARM/TRIP SETPOINT The monitor setpoint is selected to alarm and trip consistent with 10 CFR 70.24(a)(2)
MEASUREMENT RANGE*
>>1 4
1xl0 mR/hr to 1xl0 mR/hr The Radiation Monitoring Instrumentation Surveillance Requirements per Table 4.3-3 are based on the following interpretation:
1)
The CHANNEL FUNCTIONAL TEST is successfully accomplished by the injection of a simulated signal into the channel, as close to the detector as practical, to verify the channel's alarm and/or trip function only.
2)
The CHANNEL CALIBRATION as defined in T/S Section 1.9 permits the "known values" generated from radioactive calibration sources to be substituted with "known values" represented by simulated signals for that subset of "known values" required for calibration and not practical to generate using the radioactive calibration sources.
- This is the minimum required sensitivity of the instrument.
Indicated values on these instruments above or below these minimum sensitivity ranges are acceptable and indicate existing conditions not instrument inoperability.
D. C.
COOK - UNIT 1 B 3/4 3-lc Amendment No. 9p
ZNSTRUMENTATZON BASES 3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained form use of this system accurately represent the spatial neutron flux distribution of the reactor core.
3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
This capability is required to permit comparison of the measured response to that used in the design basis for the facility.
3/4.3.3.4 METEOROLOGZCAL INSTRUMENTATZON The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATZON The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
DE C.
COOK - UNIT 1 B 3/4 3-2 Amendment No.
94
3/4. 11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1'I UID EFFLUENTS 3/4.11.1.1 CONCENTRATION.
This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II.
This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the population.
The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in the International Commission on Radiological protection (ICRP) Publication 2.
3/4.11.1.2 DOSE.
This specification is provided to implement the requirements of Sections II.A, III.Aand IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I.
The 'ACTION statements provide the required operating flexibilityand, at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonable achievable."
- Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the opera-tion of the facilitywill not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141.
The dose calculations in the ODCM implement the requirements in Section III.Aof Appendix I that conformance with the'guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, "Revision 1, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April. 1977.
NUREG-0133 provides methods for dose calculations consistent with Regulatory Guide 1.109 and 1.113.
This specification applies to the release of liquid effluents from each reactor at the site.
The liquid effluents from the shared system are proportioned among the units sharing the system.
D. C.
COOK - UNIT B 3/4 11-1 Amendment No.
t
RADIOACTIVE EFFLUENTS BASES 3/4.11.1.3 LIQUID WASTE TREATMENT.
The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.
The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonable achievable."
This specification implements the requirements of 10 CFR Part 50.36a, General Design Criteria Section 11.1 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant, and design objective Section IZ.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
3/4.11.1.4 LIQUID HOLDUP TANKS.
Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks'ontents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table IZ, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE.
This specification is provided to ensure that the dose rate any time at the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS.
The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an UNRESTRICTED AREA, to annual average concentrations exceeding the limits specified in Appendix B, Table ZZ of 10 CFR Part 20 (10 CFR Part 20.106(b)).
For individuals who may at times be within the SITE BOUNDARY, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.
The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to 1500 mrem/year for the nearest cow to the Plant.
Iodine adsorbing media refers to silver zeolite cartridges in Table 4.11-2 or the industry standard.
This specification applies to the release of gaseous effluents from all reactors at the site.
The gaseous effluents from the shared system are proportioned among the units sharing that system.
D. C.
COOK - UNIT 1 B 3/4 11-2 Amendment No.
94
ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECT1ON 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 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less 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 ~
e 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 facility Health Physicist 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 intensity of radiation is greater than 1000 mrem/hr.
In addition, 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 Supervisor on duty and/or the Plant Health Physicist (Plant Radiation Protection Supervisor).
- 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.
D. C.
COOK - UNIT 1 6-21 Amendment No.
94
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION O
8 FUNCTIONAL UNIT 3.
CONTAINMENT ISOLATION R
a.
Phase "A" Isolation H
- 1) Manual 2)
From Safety Injection Automatic Actuation Logic TOTAL NO.
CHANNELS OF CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE
'APPLICABLE MODES 1,2,3,4 1,2,3,4 ACTION 18 13 b.
Phase "B" Isolation
- 1) Manual
- 2) Automatic Actuation Logic
- 3) Containment Pressure-High-High 1,2,3j4 1,2,3,4 1,2,3 18 13 16 c.
Purge and Exhaust Isolation*
- 1) Manual
- 2) Containment Radioactivity-High Train A (VRS-2101, ERS-2301, ERS-2305)
- 3) Containment Radioactivity-High Train B (VRS 2201 g ERS 2401 g ERS 2405) 1,2,3,4 1,2,3,4 1,2,3,4 17 17 17 g'
- This specification only applies during purge.
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT 2.
CONTAINMENT SPRAY TRIP SETPOINT ALLOWABLE VALUES a.
Manual Initiation
- b. Automatic Actuation Logic
- c. Containment Pressure-High-High Not Applicable Not Applicable 2.9 psig Not Applicable Not Applicable 3.0 psig 3.
CONTAINMENT ISOLATION a.
Phase "A" Isolation
- 1. Manual
- 2. From Safety Injection Automatic Actuation Logic Not Applicable Not Applicable Not Applicable Not Applicable
- b. Phase "B" Isolation
- 1. Manual
- 2. Automatic Actuation Logic
- 3. Containment Pressure-High-High Not Applicable Not Applicable 2.9 psig Not Applicable Not Applicable 3.0 psig
- c. Purge and Exhaust Isolation
- 1. Manual Not Applicable Not Applicable
- 2. Containment Radioactivity High Train A (VRS-2101, ERS-2301, ERS-2305)
See Table 3.3-6 Not Applicable
- 3. Containment Radioactivity High Train B (VRS-2201, ERS-2401, ERS-2405)
See Table 3.3-6 Not Applicable
O O
8 I
OPERATION MODE/INSTRUMENT 1.
Modes 1, 2, 3, 6 4 MINIMUMCHANNELS OPERABLE ALARM SETPOINT TRIP SETPOINT TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION (OPERABILITY BASES DISCUSSED IN BASES SECTION 3/4.3.3.1)
ACTION A)
Area Monitors
+
i) Upper Containment (VRS 2101/2201)
N/A 54 mR/hr 21 B)
Process Monitors i)
Particulate Channel (ERS 2301/2401)
+
ii) Noble Gas Channel (ERS 2305/2405)
C)
Noble Gas Effluent Monitors N/A N/A 2.52 uCi 4
-3 4 4 x 10 uCi CC 20 20 i)
Unit Vent Effluent Monitor a)
Low Range (VRS 2505)
(See T/S Section 3.3.3.10) rt 0
00 cD
TABLE 3.3-6 (Cont'd)
RADIATION MONITORING INSTRUMENTATION (OPERABILITY BASES DISCUSSED IN BASES SECTION 3/4.3.3.1)
OPERATION MODE/INSTRUMENT MINIMUM CHANNELS OPERABLE ALARM SETPOINT TRIP SETPOINT ACTION ii)
Gland Steam Condenser Vent Monitor a)
Low Range (SRA 2805)
(See T/S Section 3.3.3.10) iii) Steam Jet Air Ejector Vent Monitor a)
Low Range (SRA 2905)
(See T/S Section 3.3.3.10) 2.
Mode 6 A)
Train A i)
Containment Area Radiation Channel (VRS 2101) any 2/3 channels N/A 54 mR/hr 22 ii)
Particulate Channel (ERS 2301)
+
iii)
Noble Gas Channel (HRS 2305)
N/A N/A
~ 2.52 uCi C 4.4 x 10 uCi CC B)
Train B i)
Containment Area Radiation Channel (VRS 2201) any 2/3 channels N/A 54 mR/hr 22 ii)
Particulate Channel (ERS 2401)
N/A 2.52 uCi
TABLE 3.3-6 (Cont'd)
RADIATION MONITORING INSTRUMENTATION (OPERABILITY BASES DISCUSSED IN BASES SFCTION 3/4.3.3')
OPERATION MODE/INSTRUMENT
+
iii)
Noble Gas Channel (ERS 2405)
MINIMUM CHANNELS OPERABLE ALARM SETPOINT N/A TRIP SETPOINT C 4.4 x 10 uci CC ACTION 22 3.
Mode ***
A) Spent Fuel Storage (RRC-330) 15 mR/hr 15 mR/hr 21.
- With fuel in storage pool or building.
+
This specification applies only during purge.
TABLE 3.3-6 (Continued)
TABLE NOTATION ACTION 20 -
With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, comply with the ACTION requirements of Speci ication 3.4.6.1.
ACTION 21 With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, perform area surveys of the monitored area with portable monitorin'g instrumentation at least once per day.
ACTION 22 -
With the number of channels OPERABLE less than required by the Minimum Channels Operable requirements, comply with the ACTION requirements of Specification 3.9.9.
This ACTION is not required during the performance of containment integrated leak rate test.
D. C.
COOK UNIT 2 3/4 3-36 Amendment No. 80
TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS OPERATION MODE/INSTRUMENT 1.
Modes 1, 2, 3, 8 4 A)
Area Monitors CHANNEL CHECK CHANNEl'ALIBRATION CHANNEL FUNCTIONAL TEST MODES FOR
%LICH SURVFILLANCE RE UIRED i) Upper Containment (VRS 2101/2201) 1, 2, 3, 4
B)
Process Monitors i) Particulate Channel (ERS 2301/2401) 1, 2, 3, 4
ii) Noble Gas Channel (ERS 2305/2405) 1, 2, 3, 4
C)
Noble Gas Effluent Monitors i) Unit Vent Effluent Monitors a)
Low Range (VRS 2505)
(See Table 4.3-9, Item 3.a.
4a.
5a)
TABLE 4.3-3 (Cont'.d)'ADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS 8
OPERATION MODE/INSTRUMENT ii)
Gland Steam Condenser M
Vent Monitor CHANNEL CHECK CHANNFL CALIBRATION CHANNEL FUNCTIONAL TF.ST MODES FOR WHICH SURVEILLANCE RE UIRED a)
Low Range (SRA 2805)
(See Table 4.3-9 Item 6.a) iii) Steam Jet Air Ejector Vent Monitor a)
Low Range (SRA 2905)
(See Table 4.3-9, Item 2.a) 2.
Mode 6 A)
Train A LJ i) Containment Area Radiation Channel (VRS 2101) ii) Particulate Channel (ERS 2301)
S*
iii) Noble Gas Channel (ERS 2305)
B)
Train B i) Containment Area Radiation Channel (VRS 2201)
S*
M 0
ii) Particulate Channel (ERS 2401)
S*
TABLE 4.3-3 (Cont'd)
RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS Ao OPERATION MODE/INSTRUMENT Fq iii) Noble Gas Channel g
(ERS 2405) 2.
Mode**
CHANNEL CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES FOR WHICH l SURVEILLANCE RE UIRED A) Spent Fuel Storage (RRC-330) o To include SOURCE CHECK per T/S Section 1.27.
- With fuel in storage pool or building.
TABLE 3.3-12 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION Instrument Minimum Channels Operable A plicabilit Actiorl
- 1. Gross Radioactivity Monitors Providing Automatic Release Termination
- a. Liquid Radwaste Effluent Line (2-R-18)
At times of release 23 b.
Steam Generator Blowdown Line (2-R-19)
At times of release 24 c.
Steam Generator Blowdown Treatment Effluent (2-R-24)
At times of release
- 2. Gross Radioactivity Monitors Not Providing Automatic Release Termination
- a. Service Water System Effluent Line (2-R-20, 2-R-28)
- 3. Continuous Composite Sampler Flow Monitor (1)per train At all times 25
- a. Turbine Building Sump Effluent Line At all times 25
- 4. Flow Rate Measurement Devices
- a. Liquid Radwaste Line(RFI-285)
- b. Discharge Pipes*
c.
Steam Generator Blowdown Treatment Effluent (2-DFI-353)
At times of release At all times At times of release 26 NA 26
- Pump curves and valve settings may be utilized to estimate flowt in such cases, Action Statement 26 is not applicable.
D. C.
COOK UNIT 2 3/4 3-54 Amendment No.80'
TABLE 3.3-13 Radioactive Gaseous Effluent Monitorin Instrumentation Instrument (Znstrument 8)
Minimum Channels Operable A licabilit Action 1.
Waste Gas Holdup System Explosive Gas Monitoring System a.
Hydrogen Monitor (QC-31)
- b. Oxygen Monitor (QC-31, QC-370)
(1)
(2) 30 29 Condenser Evacuation System
- a. Noble Gas Activity Monitor (SRA-2905)
- b. Plow Rate Monitor (SFR-401)
(2-MR-054 and/or SRA-2910)
(1)
(1)
(1) 27 27 3.
Unit Vent, Auxiliary Building Ventilation System
- a. Noble Gas Activity Monitor (VRS-2505)
- b. Zodine Sampler Cartridge for VRS-2503
- c. Particulate Sampler Filter for VRS-2501
- d. Effluent System Plow Rate Measuring Device (VFR-315)
(2-MR-054 and/or VRS-2510) e.
Sampler Plow Rate Measuring Device (VFS-2521) 28 32 32 27 27 27 Containment Purge System
- a. Aux. Building Vent. System Noble Gas Activity Monitor (VRS-2505)
- b. Aux. Building Vent. System Particulate Sampler for VRS-2501 31 32 5.
Waste Gas Holdup System
- a. Noble Gas Activity Monitor Providing Alarm and Termination of Gas Decay Tank Releases (VRS-2505) 33 6.
Gland Seal Exhaust
- a. Noble Gas Activity Monitor (SRA-2805)
- b. Flow Rate Monitor (SFR-201)
(2-MR-054 and/or SRA-2810)
(1)
(1)
(1)
~
- I 28 27 27 D. C.
COOK - UNIT 2 3/4 3-59 Amendment No. 80
TABLE 3.3-13 (Cont)
At all times During waste gas holdup system operation (treatment for primary system gases)
- During releases via this pathway.
For purge purposes only.
See Technical Specifications 3.3.3.10, Table 3.3-13 and Table 4.3-9 (Item 3a, 5a) for other non purging requirements associated with this instrument..
2 For gas decay tank releases only, see Item 3 (Unit Vent, Auxiliary Building Ventilation System) for additional requirements.
D. C.
COOK ~ UNIT 2
'3/4 3"60 Amendment No.
TABLE 4.3-9 Radioactive Gaseous Effluent Monitorin Instrumentation Surveillance Re uirements Instrument (Instrument 0)
Channel Check Source Check Channel Calibration Channel Functional Test
- 1. Waste Gas Holdup System Explosive Gas Monitoring System
- a. Hydrogen Monitor (QC-31) b.
Oxygen Monitor (QC-31) c.
Oxygen Monitor (Alt. (QC-370)
D***
NA NA NA Q(3)
Q(4)
Q(4)
- 2. Condenser Evacuation System
- a. Noble Gas Activity Monitor (SRA-2905) b.
System Effluent Flow Rate (SFR-401, 2-MR-054, SRA-2910)
D*%
D**
M NA R(2)
Q(1)
- 3. Auxiliary Building Ventilation System
- a. Noble Gas Activity Monitor (VRS<<2505)
- b. Iodine Sampler (For VRS-2505)
'. Particulate Sampler (For VRS-2501)
- d. System Effluent Flow Rate Measurement Device (VFR-315, 2-MR-054, VRS-2510) e.
Sampler Flow Rate Measurement Device (VFS-2521)
D*
D*
D*
M NA NA NA NA R(2)
NA NA NA NA
- 4. Containment Purge System
- a. Aux. Building Vent. System Noble Gas Activity D**
Monitor (VRS-2505)
- b. Aux. Building Vent. System Particulate Sampler W**
(For VRS-2501)
NA R(2)
NA Q(5)
- 5. Waste Gas Holdup System a.
Noble Gas Activity Monitor Providing Alarm 6 Termination of Gas Decay Tank Release (VRS-2505)
D. C.
COOK - UNIT 2 p**
3/4 3 62 R(2) g(5)
Amendment No.80
TABLE 4.3-9 (Cont)
Instrument (Instrument
"-.)
Channel Check Source Check Channel Calibration Channel Functional Test
- 6. Gland Seal Exhaust
- a. Noble Gas Activity D**
(SRA-2805) b.
System Effluent D**
Flow Rate (SFR-201, 2-MR-054, SRA-2810)
NA R(2)
At all times
- During release via this pathway
- During waste gas holdup system operation (treatment for primary system offgases)
D. C.
COOK - UNIT 2 3/4 3-63 Amendment No. 80
TABLE 4.11-2 RADIOACTI GASEOUS WASTE SAMPLING AND ANA SIS PROGRAM Gaseous Release Type Frequency Minimum Analysis Frequency Type of Activity Analysis Lower Limit of Detection (uci/ml)
P Each Tank a.
Waste Gas Storage Tank Grab Sample P
Each Tank Principal Gamma e
Emitters Principal Gamma Emitters e 1
X 10 1
X 10 b.
Containment Purge Each Purge Grab Sample Each Purge H-3 1
X 10 c.
Condenser Evacuation System and Gland Seal Exhaust+
W Grab b
Sample M
Par ticulate Sample M
Principal Gamma Emitters e H-3 1
X 10 1
X 10 M
'Iodine Adsorbing/
Media I-131 1X10 d
Continuous Noble Gas Monitor Noble Gases 1
X 10 d.
Auxiliary Building Vent Continuous d W
Iodine Adsorbing/
Media I-131 1X10 d
Continuous W
Particulate Sample Principal Gamma Emitters e 1
X 10 d
Continuous M
Composite Particulate Sample Gross Alpha 1
X 10 d
Continuous M
Composite H-3 1X10 d
Continuous Q
Composite Particulate Sample Sr-89, Sr-90 1X10 d
Continuous Noble Gas'onitor Noble Gases
-6 1X10
+As equipment becomes operational D. C.
COOK - UNIT 2 3/4 11-8 Amendment No.
80.
4
~))
gJ
~
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway
~/
- 1. Airborne
- a. Radioiodine
& Particulates Sam le Locations A1-A6 (Site)
New Buffalo South Bend,
- Dowagiac, and Coloma are
Background
Sampling and Collection'Fre uenc Continuous operation, of sampler with Sample Collection as required by Dust Loading but at least once per 7 days Type 6 Frequency of Anal sis Radioiodine canister Analyze:
Weekly for I-131 Particulate sample Gross Beta Rad-ioactivity following Filter Change composite (by loca-tion) for gamma isotopic quarterly
- 2. Direct Radiation a) Tl-T9 (Site) b)
New Buffalo South Bend Dowagiac Coloma At least once per 92 days Gamma Dose. At least once per 92 days
- 3. Waterborne
- a. Surface c) 10 TLD Monitor Locations in the Five Mile Radius Ll, L2, L3 Composite*
sample over one-mon"h period Gamma Isotopic Analysis monthly.
Composite for tritium analysis-quarterly.
- b. Ground Wl-W7 Quarterly Gamma Isotopic and Tritium analysis quarterly.
- c. Drinking St. Joseph Lake Township Composite sample collected over a period of ~31 days Composite*.sample over a 2-week period if I-131 analysis is performed Gross Beta and Gamma Isotopic Analysis of each composite sample.
Tritium Analysis of composite Quarterly.
I-131 analysis on each composite when the dose calculated for the consumption of the water is greater than 1 mrem per year.
- Composite samples shall be collected by collecting an aliquot at intervals not exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. C.
COOK - UNIT 2 3/4 12-3 Amendment No. 80
3/4.3 INSTRUMENTATZON BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)
INSTRUHENTATZON The OPERABILITY of the protective and ESF instrumentation systems and interlocks ensure that
- 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint,
- 2) the specified coincidence logic is maintained, 3) sufficient redundancy is mairatained to permit a channel to be out of service for testing or maintenance, and
- 4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundancy and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.
The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.
The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards.
The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.
s The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each
'hannel is completed within the time limit assumed in the accident analyses.
No credit was taken in the analyses for those channels with response times indicated as not applicable.
Response
time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined.
Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or
- 2) utilizing replacement sensors with certified response times.
3/4.3.3 MONITORING ZNSTRUMENTATZON 3/4.3.3 1
RADIATION MONI-ORZNG INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and
- 2) the alarm or automatic action is initiated when.the radiation level trip setpoint is exceeded.
D. C.
COOK - UNIT 2 B 3/4 3-1 Amendment No. 80
INSTRUMENTATION BASES Radiation Monitorin Instr'umentation (Continued)
Table 3.3-6 is based on the following Alarm/Trip Setpoints and Measurement Ranges for each instrument listed.
INSTRUMENT 1)
Area Monitor-Upper Containment (VRS 2101/2201)
ALARM/TRIP SETPOINT The monitor trip setpoint is based on 10 CFR 20 limits.
A homogeneous mixture of the containment atmosphere is assumed.
The setpoint value is defined as the monitor reading when the purge is operating at the maximum flow rate.
MEASUREMENT RANGE*
-4 10 R/hr to 10R/hr.
2)
Process Monitor Particulate (ERS 2301/2401)
The monitor trip setpoint based on 10 CPR 20 limits.
The setpoint was determined using the Noble gas setpoint and historical monitor data of the ratio of particulate to Noble gases.
-4 1.5 x 10 uCi to 7.5 uCi.
- 3) 'rocess Monitor Noble Gas (ERS 2305/2405)
-7 The monitor trip setpoint 1 x 10 2 uCi/cc to is based on 10 CPR 20 4 x 10 uCi/cc limits.
A homogeneous mixture of the containment atmosphere is assumed.
The setpoint value is defined as the monitor reading when the purge is operating at the maximum flow rate.
- This is the minimum required sensitivity of the instrument.
Indicated values on these instruments above or below these minimum sensitivity ranges are acceptable and indicate existing conditions not instrument inoperability.
D. C.
COOK - UNIT 2 B 3/4 3-la Amendment No.
INSTRUMENTATION BASES t
Radiation Monitorin Instrumentation (Continued)
INSTRUMENT ALARM/TRIP SETPOINT MEASUREMENT RANGE*
4)
Noble Gas Unit Vent Monitors a)
Low Range (VRS 2505)
See Bases Section 3/4.3.3.10
-7
<<2 1x10 uCi/cc to 4x10 uCi/cc.
5)
Gland Steam Condenser Vent Noble Gas Monitor a)
Low Range (SRA 2805)
See Bases Section 3/4.3.3.10
<<7
-2 lx10 uCi/cc to 4x10 uCi/cc.
6)
Steam Jet Air Ejector Vent Noble Gas Monitor a)
Low Range (SRA 2905)
See Bases Section 3/4.3.3.10
<<7
<<2 lx10 uCi/cc to 4xl0 uCi/cc.
- This is the minimum required sensitivity of the instrument.
Indicated values on these instruments above or below these minimum sensitivity ranges are acceptable and indicate existing conditions not instrument inoperability.
D. C.
COOK - UNIT 2 B 3/4 3-1b Amendment No. 80
INSTRUMENTATION BASES Radiation Monitorin Instrumentation (Continued)
INSTRUMENT 7)
Spent Fuel Storage (RRC-330)
ALAR1/TRIP SETPOINT The monitor setpoint is selected to alarm and trip consistent with 10 CFR 70.24(a) (2) l1EASUREMENT R~GE*
-1 4
lx10 mR/hr to lxl0 mR/h r I
The Radiation Monitoring Instrumentation Surveillance Requirements per Table 4.3-3 are based on the following interpretation:
1)
The CHANNE'UNCTIONAL TEST is successfully accomplished by the
~
injection of a simulated signal into the channel, as close to the detector as practical, to verify the channel's alarm and/or trip function only.
2)
The CHANNEL CALIBRATION as defined in T/S Section 1.9 permits the "known values" generated from radioactive calibration sources to be substituted with "known values" represented by simulated signals for that subset of "known values" required for calibration and not practical to generate using the radioactive calibration sources.
- This is the minimum required sensitivity of the instrument.
Indicated values on these instruments above or below these minimum sensitivity ranges are acceptable and indicate existing conditions not instrument inoperability.
D. C.
COOK - UNIT 2 B 3/4 3-1c Amendment No.
80
3/4. 11 'ADIOACTIVEEFFLUENTS
~ ~
EASES 3/4.11.1 LI UID EFFLUENTS 3/4.11.1.1 CONCENTRATION.
This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix 3, Table II.
This limitation provides additional assurance that the level's of radioactive materials in bodies of water outside the site will not result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the population.
The concentration limit for noble gases is based upon the assumption that Xe>>135 is,the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in the International Commission on Radiological protection (ICRP) Publication 2.
3/4.11.1.2 DOSE.
This specification is provided to implement the requirements of Sections II.A, III.Aand. IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I.
The ACTION statements provide the required operating flexibilityand at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonable achievable."
- Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the opera-tion of the facilitywill not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141.
The dose calculations in the ODCM implement the requirements in Section III.Aof Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, "Revision 1, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
NUREG-0133 provides methods for dose calculations consistent with Regulatory Guide 1.109 and 1.113.
This specification applies to the release of liquid effluents from each reactor at the site.
The liquid effluents from the shared system are proportioned among the units sharing the system.
D. C.
COOK - UNIT B 3/4 11-1 Amendment No.80
~
s
RADIOACTIVE EFFLUENTS BASES 3/4.11.1.3 LIQUID HASTE TREATMENT.
The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid ef 'uents require treatment prior to release to the environment.
The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonable achievable."
This specification implements the requirements cf 10 CFR Part 50.36a, General Design Criteria Section 11.1 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant, and design objective Section ZI.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section IZ.A of Appendix I, 10 CFR Part 50, for liquid effluents.
3/4.11.1.4 LIQUID HOLDUP TANKS.
Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks'ontents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest
'potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE.
This specification is provided to ensure that the dose rate any time at the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS.
The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table ZI.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an UNRESTRICTED AREA, to annual average concentrations exceeding the limits specified in Appendix B, Table IZ of 10 CFR Part 20 (10 CFR Part 20.106(b)).
For individuals who may at times be within the SITE BOUNDARY, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.
The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to 1500 mrem/year for the nearest cow to the Plant.
Zodine adsorbing media refers to silver zeolite cartridges in Table 4.11-2 or the industry standard.
This specification applies to the release of gaseous effluents from all reactors at the site.
The gaseous effluents from the shared system are
.proportioned among the units sharing that system.
D. C.
COOK - UNIT 2 B 3/4 11-2 Amendment No. 80
ADMINISTRATIVECONTROLS 6.11 PADIATION 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 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20,. each high radiation area in which the intensity of radiation is 1000 mrem/hr or less 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 g oup of individuals permitted to enter such areas shall be provided with or accompanied by one or more o 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 facility Health Physicist 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 intensity of radiation is greater than 1000 mrem/hr.
In addition, 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 Supervisor on duty and/or the Plant Health Physicist (Plant Radiation Protection Supervisor).
- 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.
D. C.
COOK - UNIT 2 6-21 Amendment No. 80 "