ML21034A474
| ML21034A474 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/03/2021 |
| From: | Brian Fuller Operations Branch I |
| To: | Isham P Exelon Nuclear Generation Corp |
| Fuller B | |
| Shared Package | |
| ML19309G108 | List: |
| References | |
| CAC 00500 | |
| Download: ML21034A474 (28) | |
Text
3.0 4.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 3.0.1 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered operable for the purpose of satisfying the requirements of its applicable LCO, provided: (1) its corresponding normal or emergency power source is operable; and (2) all of its redundant system(s), subsystem(s), train(s), component(s) and device(s) are operable, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied, the unit shall be placed in a condition stated in the individual specification.
In the event LCO requirements cannot be satisfied because of circumstances in excess of those addressed in the specification, the unit shall be placed in a condition consistent with the individual specification unless corrective measures are completed that permit operation for the specified time interval as measured from initial discovery or until the reactor is placed in an operational condition in which the specification is not applicable.
3.0.2 through 3.0.7 - Reserved for Future Use SURVEILLANCE REQUIREMENT (SR} APPLICABILITY AMENDMENT NO. 142,182,207 27
LIMITING CONDITION FOR OPERATION
- c.
Where:
- d.
- e.
=
=
=
=
The liquid poison solution temperature shall not be less than the temperature presented in Figure 3.1.2.b.
If Specifications "a" through "d" are not met, initiate normal orderly shutdown within one hour.
AMENDMENT NO. 142, 166,222,239 SURVEILLANCE REQUIREMENT Remove the squibs from the valves and verify that no deterioration has occurred by actual field firing of the removed squibs. In addition, field fire one squib from the batch of replacements.
Disassemble and inspect the squib-operated valves to verify that valve deterioration has not occurred.
(2) In accordance with the Surveillance Frequency Control Program -
Demineralized water shall be recycled to the test tank. Pump discharge pressure and minimum flow rate shall be verified.
b.
Boron Solution Checks:
(1) In accordance with the Surveillance Frequency Control Program Boron concentration shall be determined.
(2) In accordance with the Surveillance Frequency Control Program -
Solution volume shall be checked. In addition, the sodium pentaborate concentration shall be determined and conformance with the requirements of the equivalency equation shall be checked any time water or boron are added or if the solution temperature drops below the limits specified by Figure 3.1.2.b.
45
CY-NM-170-301 Revision 37 I 3.1-1 January 2020 RADIOACTIVE EFFLUENT INSTRUMENTATION - LIQUID D 3/4.6.14 CONTROLS SURVEILLANCE REQUIREMENT DLCO 3.6.14 RADIOACTIVE EFFLUENT INSTRUMENTATION Applicability:
Applies to the functionality of plant instrumentation that monitors plant effluents.
Objective:
To assure the functionality of instrumentation to monitor the release of radioactive plant effluents.
Specification:
a.
Liquid Effluent The radioactive liquid effluent monitoring instru-mentation channels shown in Table D 3.6.14-1 shall be functional with their alarm setpoints set to ensure that the limits of Control DLCO 3.6.15.a.1 are not exceeded. The alarm setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Part II.
With a radioactive liquid effluent monitoring instrumentation channel alarm setpoint less conservative than a value which will ensure that the limits of DLCO 3.6.15.a.1 are met, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel nonfunctional, or change the setpoint so it is acceptably conservative.
DSR 4.6.14 RADIOACTIVE EFFLUENT INSTRUMENTATION Applicability:
Applies to the surveillance of instrumentation that monitors plant effluents.
Objective:
To verify operation of monitoring instrumentation.
Specification:
a.
Liquid Effluent Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated functional by performance of the sensor check, source check, instrument channel calibration and channel test operations at the frequencies shown in Table D 4.6.14-1.
Records - Auditable records shall be maintained, in accordance with procedures in Part II, of all radioactive liquid effluent monitoring instrumentation alarm setpoints. Setpoints and setpoint calculations shall be available for review to ensure that the limits of Control DLCO 3.6.15.a.1 are met.
CY-NM-170-301 Revision 37 I 3.1-2 January 2020 RADIOACTIVE EFFLUENT INSTRUMENTATION - LIQUID D 3/4.6.14 CONTROLS SURVEILLANCE REQUIREMENT With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels functional, take the action shown in Table D 3.6.14-
- 1. Restore the instruments to functional status within 30 days, or outline in the next Radioactive Effluent Release Report the cause of the nonfunctionality and how the instruments were or will be restored to functional status.
CY-NM-170-301 Revision 37 I 3.1-3 January 2020 RADIOACTIVE EFFLUENT INSTRUMENTATION - LIQUID D 3/4.6.14 TABLE D 3.6.14-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Instrument Minimum Channels Functional Applicability 1.
Gross Radioactivity Monitors(a)
A. Liquid Radwaste Effluent Line B. Service Water System Effluent Line 2.
Flow Rate Measurement Devices A. Liquid Radwaste Effluent Line B. Discharge Canal 3.
Tank Level Indicating Devices(g)
A. Outside Liquid Radwaste Storage Tanks 1(c) 1(d) 1(e) 1(f)
At all times(b)
At all times(i)
At all times At all times
- Pumps curves or rated capacity will be utilized to estimate flow.
CY-NM-170-301 Revision 37 I 3.1-4 January 2020 RADIOACTIVE EFFLUENT INSTRUMENTATION - LIQUID D 3/4.6.14 NOTES FOR TABLE D 3.6.14-1 (a)
Provide alarm, but do not provide automatic termination of release.
(b)
An operator shall be present in the Radwaste Control Room at all times during a release.
(c)
With the number of channels functional less than required by the minimum channels functional requirement, effluent releases may continue provided that prior to initiating a release:
1.
At least two independent samples are analyzed in accordance with Specification DSR 4.6.15.a, and 2.
At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving.
Otherwise suspend release of radioactive effluents via this pathway.
(d)
With the number of channels functional less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for gamma radioactivity at a lower limit of detection of at least 5x10-7 microcurie/ml.
(e)
During discharge, with the number of channels functional less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
(f)
With the number of channels functional less than required by the minimum channels functional requirement, liquid additions to this tank may continue provided the tank liquid level is estimated during liquid additions to the tank.
(g)
Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes or walls capable of holding the tank contents.
(h)
Deleted.
(i)
Monitoring will be conducted continuously by alternately sampling the reactor building and turbine building service water return lines for approximately 15-minute intervals.
CY-NM-170-301 Revision 37 I 3.1-5 January 2020 RADIOACTIVE EFFLUENT INSTRUMENTATION - LIQUID D 3/4.6.14 TABLE D 4.6.14-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Surveillance Requirement Instrument Sensor Check Source Check(f)
Channel Test Channel Test Channel Calibration 1.
Gross Beta or Gamma Radioactivity Monitors a.
Liquid Radwaste Effluent Line Line b.
Service Water Effluent Line 2.
Flow Rate Measurement Devices a.
Liquid Radwaste Effluent Line b.
Discharge Canal(d) 3.
Tank Level Indicating Devices(e) a.
Outside Liquid Radwaste Storage Tanks Once/day*
Once/day Once/day(c)
None Once/day**
Once/discharge*
Once/92 days None None None Once/3 months(a)*
Once/184 days(a)
None None Once/3 months Once/year(b)*
Once/24 months(b)
Once/24 months*
Once/year Once/18 months Required prior to removal of blank flange in discharge line and until blank flange is replaced.
- During liquid addition to the tank.
CY-NM-170-301 Revision 37 I 3.1-6 January 2020 RADIOACTIVE EFFLUENT INSTRUMENTATION - LIQUID D 3/4.6.14 NOTES FOR TABLE D 4.6.14-1 (a)
The channel test shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
1.
Instrumentation indicates measured levels above the alarm setpoint.
2.
Instrument indicates a downscale failure.
3.
Instrument controls not set in operate mode.
(b)
The channel calibration shall be performed using one or more reference standards certified by the National Institute of Standards and Technology (NIST), or using standards that are traceable to the NIST or using actual samples of liquid waste that have been analyzed on a system that has been calibrated with NIST traceable sources. These standards shall permit calibrating the system over its intended range of energy and measurement.
(c)
Sensor check shall consist of verifying indication of flow during periods of release. Sensor check shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic or batch releases are made.
(d)
Pump performance curves or rated data may be used to estimate flow.
(e)
Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes or walls capable of holding the tank contents.
(f)
Source check may consist of an installed check source, response to an external source, or (for liquid radwaste monitors) verification within 30 minutes of commencing discharge of monitor response to effluent.
CY-NM-170-301 Revision 37 I 3.1-7 January 2020 RADIOACTIVE EFFLUENT INSTRUMENTATION - GASEOUS D 3/4.6.14 CONTROLS SURVEILLANCE REQUIREMENT b.
Gaseous Process and Effluent The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table D 3.6.14-2 shall be functional. The Offgas process monitor alarm setpoint shall be set to ensure that the limits of Technical Specification 3.6.15 are not exceeded. The Effluent monitor alarm setpoints shall be set to ensure that the limits of Control DLCO 3.6.15.b.1 are not exceeded. The alarm setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Part II.
With a radioactive gaseous process and effluent monitoring instrumentation channel alarm setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel nonfunctional, or change the setpoint so it is acceptably conservative.
With less than the minimum number of radioactive gaseous process and effluent monitoring instrumentation channels functional, take the action shown in Table D 3.6.14-2. Restore the instruments to functional status within 30 days or outline in the next Radioactive Effluent Release Report the cause of the nonfunctionality and how the instruments were or will be restored to functional status.
b.
Gaseous Process and Effluent Each radioactive gaseous process and effluent monitoring instrumentation channel shall be demonstrated functional by performance of the sensor check, source check, instrument channel calibration and instrument channel test operations at the frequencies shown in Table D 4.6.14-2.
Auditable records shall be maintained of the calculations made, in accordance with procedures in Part II, of radioactive gaseous process and effluent monitoring instrumentation alarm setpoints. Setpoints and setpoint calculations shall be available for review to ensure that the limits of Control DLCO 3.6.15.b.1 are met.
CY-NM-170-301 Revision 37 I 3.1-8 January 2020 RADIOACTIVE EFFLUENT INSTRUMENTATION - GASEOUS D 3/4.6.14 TABLE D 3.6.14-2 RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION Instrument Minimum Channels Functional Applicability Action 1.
Stack Effluent Monitoring a.
Noble Gas Activity Monitors (1) High Range (2) Low Range b.
Iodine Sampler Cartridge c.
Particulate Sampler Filter d.
Sampler Flow Rate Measuring Device e.
Stack Gas Flow Rate Measuring Device 2.
Deleted 2
1 1
1 1
1 (a)
(i)
(b)
(b)
(c)
(c), (d)
At all times.
Note Deleted.
CY-NM-170-301 Revision 37 I 3.1-9 January 2020 RADIOACTIVE EFFLUENT INSTRUMENTATION - GASEOUS D 3/4.6.14 TABLE D 3.6.14-2 (cont'd)
RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION Instrument Minimum Channels Functional Applicability Action 3.
Condenser Air Ejector Process Monitor (Offgas System Recombiner Discharge) a.
Noble Gas Activity Monitor b.
Offgas System Flow Rate Measuring Device 4.
Emergency Condenser System Effluent a.
Noble Gas Activity Monitor 2
1 1 per vent (g)
(c)
(h)
During operation of the main condenser air ejector During power operating conditions and whenever the reactor coolant temperature is greater than 212qF except for hydrostatic testing with the reactor not critical.
CY-NM-170-301 Revision 37 I 3.1-10 January 2020 RADIOACTIVE EFFLUENT INSTRUMENTATION - GASEOUS D 3/4.6.14 NOTES FOR TABLE D 3.6.14-2 (a)
(1) With the number of channels functional 1 less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided:
(a) The nonfunctional channel is placed in the tripped condition, OR (b) Vent and Purge valves are closed and administratively controlled, OR (c) Primary containment integrity is not required.
(2) With the number of channels functional 2 less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided:
(a) Gross activity is recorded every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when both Noble Gas Activity Radiation Monitor indications are functional.
OR (b) Grab samples are taken once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(b)
With the number of channels functional less than required by the minimum channels functional requirements, effluent releases via this pathway may continue provided that samples are continuously collected with auxiliary sampling equipment starting within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of discovery in accordance with the requirements of Table D 4.6.15-2. When OGESMS and the auxiliary sampling equipment are both non-functional, of Chemistry procedure N1-CSP-V304 may be used for obtaining continuous particulate and iodine samples.
(c)
With the number of channels functional less than required by the minimum channels functional requirements, effluent releases via this pathway may continue provided the flow rate is estimated once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
(d)
Stack gas flow rate may be estimated by exhaust fan operating configuration.
(e)
Deleted (f)
Deleted
CY-NM-170-301 Revision 37 I 3.1-11 January 2020 RADIOACTIVE EFFLUENT INSTRUMENTATION - GASEOUS D 3/4.6.14 NOTES FOR TABLE D 3.6.14-2 (contd)
(g)
With one or more channels nonfunctional, perform one of the following AND restore the nonfunctional channel(s) to functional status within 30 days (j):
(1) With one or more channel nonfunctional due to alarm function only, every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> record gross activity of both channels as read on the meters in the control room and verify within limits OR (2) Take grab samples within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND analyze samples for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sampling completion.
OR (3) Place the nonfunctional channel in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (h)
With the number of channels functional less than required by the minimum channels functional requirements, steam release via this pathway may commence or continue provided vent pipe radiation dose rates are monitored once per four hours.
(i)
With the number of channels functional less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided:
(1) Gross activity is recorded every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when both Noble Gas Activity Radiation Monitor indications are functional.
OR (2) Grab samples are taken once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(j)
If nonfunctional channel(s) not restored within specified time, explain why the inoperability was not corrected in a timely manner in the next Radioactive Effluent Release Report.
CY-NM-170-301 Revision 37 I 3.1-12 January 2020 RADIOACTIVE EFFLUENT INSTRUMENTATION - GASEOUS D 3/4.6.14 TABLE D 4.6.14-2 RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION Surveillance Requirements Instrument Sensor Check Source Check Channel Test Channel Calibration 1.
Stack Effluent Monitoring System a.
Noble Gas Activity Monitors (High Range and Low Range) b.
Iodine Sampler Cartridge c.
Particulate Sampler Filter
- d. Sampler Flow Rate Measuring Device e.
Stack Gas Flow Rate Measuring Device
- 2.
Deleted 3.
Condenser Air Ejector Process Monitor (Offgas System Recombiner Discharge) a.
Noble Gas Activity Monitor
- b. Offgas System Flow Rate Measuring Device 4.
Emergency Condenser System Effluent a.
Noble Gas Activity Monitor Once/day(a)
None None Once/day(a)
Once/day Once/day(f)
Once/day(f)
Once/day(h)
Once/92 days None None None None Once/92 days None Once/92 days Once/184 days(g)
None None None None Once/24 months(c)
None Once184 days(g)
Once/24 months(b)
None None Once/24 months Once/24 months Once/24 months(b)
Once/24 months Once/24 months(b)
CY-NM-170-301 Revision 37 I 3.1-13 January 2020
CY-NM-170-301 Revision 37 I 3.1-14 January 2020 RADIOACTIVE EFFLUENT INSTRUMENTATION - GASEOUS D 3/4.6.14 NOTES FOR TABLE D 4.6.14-2 (a)
At all times.
(b)
The channel calibration shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST), standards that are traceable to the NIST or using actual samples of gaseous effluent that have been analyzed on a system that has been calibrated with NIST traceable sources. These standards shall permit calibrating the system over its intended range of energy and measurement.
(c)
The channel function test shall demonstrate that control room alarm annunciation occurs if either of the following conditions exist:
- 1) Instrument indicates measured levels above the Hi or Hi Hi alarm setpoint.
- 2) Instrument indicates a downscale failure.
The channel function test shall also demonstrate that automatic isolation of this pathway occurs if either of the following conditions exist:
- 1) Instruments indicate two channels above Hi Hi alarm setpoint.
- 2) Instruments indicate one channel above Hi Hi alarm setpoint and one channel downscale.
(d)
Deleted (e)
Deleted (f)
During operation of the main condenser air ejector.
(g)
The channel test shall produce upscale and downscale annunciation.
(h)
During power operating conditions and whenever the reactor coolant temperature is greater than 212qF except for hydrostatic testing with the reactor not critical.
Calculations Page 39 NER-1M-095, REV 05.00 Figure 3-11: Heat Capacity Temperature Limit 0
RPV Pressure (psig) 80 Torus Temperature (°F)
Heat Capacity Temperature Limit M
100 200 300 400 500 600 700 800 900 1000 1100 100 120 140 160 180 200 GOOD BAD Use EOP-1 Att 23 for torus water levels below 9.0 ft or above 13.0 ft 170°F @ 53 psig 110°F @ 1090 psig 10.5 - 11.25 ft Torus Water Level 9.0 - 10.5 and 11.25 - 13.0 ft
CT - Containment FC - Fuel Clad RC - Reactor Coolant System Loss Potential Loss 1
RCS Activity 2
RPV Water Level Coolant activity > 300 µCi/gm I-131 equivalent.
Loss Potential Loss Loss Potential Loss
- 1. SAP entry required.
None 2.
RPV water level cannot be restored and maintained > -84 inches.
OR 3.
RPV water level cannot be determined.
1.
RPV water level cannot be restored and maintained > -84 inches.
OR 2.
RPV water level cannot be determined.
SAP entry required.
3 Primary Containment Pressure /
Conditions 1.
a.
Primary Containment pressure > 3.5 psig.
AND b.
Primary Containment pressure rise is due to RCS leakage.
1.
UNPLANNED rapid drop in Primary Containment pressure following Primary Containment pressure rise.
OR 2.
Primary Containment pressure response not consistent with LOCA conditions.
3.
Torus pressure > 35 psig.
OR 4.
a.
Primary Containment hydrogen concentration > 6%.
AND b.
Primary Containment oxygen concentration > 5%.
OR 5.
Heat Capacity Temperature Limit (N1-EOP-4 Figure M) exceeded.
`
4 RCS Leak Rate 5
Primary Containment Radiation 6
Primary Containment Isolation Failure 7
Emergency Director Judgement 1.
UNISOLABLE Main Steam line, EC steam line, Feedwater, or RWCU line break.
OR 2.
RPV Blowdown is required.
3.
UNISOLABLE primary system leakage that results in EITHER of the following:
a.
ANY area temperature
> N1-EOP-5 Detail T alarm set point.
OR b.
ANY area radiation level
> N1-EOP-5 Detail R alarm set point.
Drywell radiation reading > 1.1 E+03 R/hr (1,100 R/hr).
Drywell radiation reading > 100 R/hr.
Drywell radiation reading > 1.1 E+04 R/hr (11,000 R/hr).
1.
UNISOLABLE direct downstream pathway to the environment exists following automatic or manual isolation signal.
OR 2.
Intentional Primary Containment venting/purging per EOPs or SAPs due to accident conditions.
OR 3.
UNISOLABLE primary system leakage that results in EITHER of the following:
a.
Maximum safe general area temperature > 135 ºF.
OR b.
Maximum safe area radiation level > 8 R/hr.
1.
ANY condition in the opinion of the Emergency Director that indicates Loss of the Fuel Clad barrier.
2.
ANY condition in the opinion of the Emergency Director that indicates Potential Loss of the Fuel Clad barrier.
1.
ANY condition in the opinion of the Emergency Director that indicates Loss of the RCS barrier.
2.
ANY condition in the opinion of the Emergency Director that indicates Potential Loss of the RCS barrier.
1.
ANY condition in the opinion of the Emergency Director that indicates Loss of the Containment barrier 2.
ANY condition in the opinion of the Emergency Director that indicates Potential Loss of the Containment barrier.
Bases: 2-48 Bases: 2-48 Bases: 2-47 Bases: 2-52 Bases: 2-61 Bases: 2-54 Bases: 2-61 Bases: 2-55 Bases: 2-55 Bases: 2-63 Bases: 2-58 Bases: 2-50 Bases: 2-64 Bases: 2-67 Bases: 2-67 Bases: 2-59 Bases: 2-59 Bases: 2-51 Bases: 2-51 Bases: 2-60 None None None None None None None None None None None None None None None None None None None None None Fission Product Barrier Matrix Onsite Rad Conditions Spent Fuel Events Abnormal Radiation Levels \\ Radiological Effluents R
2 Offsite Rad Conditions 1
Hazards & Other Conditions Affecting Plant Safety H
Hostile Action Fire Toxic Gas Earthquake Judgment 1
2 3
4 5
6 CR / CAS Radiation OR Fuel Clad Degradation 3
1.
Dose assessment using actual meteorology indicates doses at or beyond the site boundary of EITHER:
Field survey results at or beyond the site boundary indicate EITHER:
- a. Gamma (closed window) dose rates > 1000 mR/hr are expected to continue for > 60 minutes.
- b. Analyses of field survey samples indicate
> 5000 mRem CDE Thyroid for 60 minutes of inhalation.
1.
Reading on the Rad Waste Discharge effluent monitor
> 2x alarm setpoint established by a current radioactive release discharge permit for > 60 minutes.
OR 2.
Reading on Stack (RN 10 A/B) Effluent Monitor > 2.85 E+02 cps (285 cps) for > 60 minutes.
OR 3.
Confirmed sample analyses for gaseous or liquid releases indicate concentrations or release rates > 2x ODCM Limit with a release duration of > 60 minutes.
1.
Reading on Stack (RN 10 A/B) Effluent Monitor > 1.5 E+05 cps for
> 15 minutes.
OR 2.
Dose assessment using actual meteorology indicates doses at or beyond the site boundary of EITHER:
Analysis of a liquid effluent sample indicates a concentration or release rate that would result in doses greater than EITHER of the following at or beyond the site boundary:
Field survey results at or beyond the site boundary indicate EITHER:
- a. Gamma (closed window) dose rates > 10 mR/hr are expected to continue for > 60 minutes.
- b. Analyses of field survey samples indicate > 50 mRem CDE Thyroid for 60 minutes of inhalation.
1.
a.
UNPLANNED water level drop in the REFUELING PATHWAY as indicated by:
SFP water level < low water level alarm.
OR Indication or report of a drop in water level in the REFUELING PATHWAY.
AND b.
UNPLANNED Area Radiation Monitor reading rise on ANY radiation monitor in Table R1.
1.
Uncovery of irradiated fuel in the REFUELING PATHWAY.
OR 2.
Damage to irradiated fuel resulting in a release of radioactivity from the fuel as indicated by ANY Table R1 Radiation Monitor Alarm.
OR 3.
Lowering of spent fuel pool level to 326 feet as indicated on LI-54-65A or LI-54-65B on SFP monitoring panel (PNL-54-65H).
Lowering of spent fuel pool level to 316 feet as indicated on LI-54-65A or LI-54-65B on SFP monitoring panel (PNL-54-65H).
Spent fuel pool level cannot be restored to at least 316 feet as indicated on LI-54-65A or LI-54-65B on SFP monitoring panel (PNL-54-65H) for > 60 minutes.
1.
Dose rate > 15 mR/hr in ANY of the areas in Table R2.
OR 2.
UNPLANNED event results in radiation levels that prohibit or significantly impede access to ANY of the areas in Table R3.
A notification from the Security Supervisor that a HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA.
1.
A validated notification from NRC of an aircraft attack threat
< 30 minutes from the site.
OR 2.
Notification by the Security Supervisor that a HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA.
1.
Notification of a credible security threat directed at the site as determined per SY-AA-101-132, Security Assessment and Response to Unusual Activities.
OR 2.
A validated notification from the NRC providing information of an aircraft threat.
OR 3.
Notification by the Security Supervisor of a SECURITY CONDITION that does not involve a HOSTILE ACTION.
A Control Room evacuation has resulted in plant control being transferred from the Control Room to alternate locations per N1-SOP-21.2, Control Room Evacuation.
1.
A Control Room evacuation has resulted in plant control being transferred from the Control Room to alternate locations per N1-SOP-21.2, Control Room Evacuation.
AND 2.
Control of ANY Table H1 key safety function is not reestablished in
< 15 minutes.
Transfer of Plant Control 1.
A FIRE in ANY Table H2 area is not extinguished in < 15 minutes of ANY of the following FIRE detection indications:
Report from the field (i.e., visual observation)
Receipt of multiple (more than 1) fire alarms or indications Field verification of a single fire alarm OR 2.
a.
Receipt of a single fire alarm in ANY Table H2 area (i.e., no other indications of a FIRE).
AND b.
The existence of a FIRE is not verified in < 30 minutes of alarm receipt.
OR 3.
A FIRE within the plant PROTECTED AREA not extinguished in
< 60 minutes of the initial report, alarm or indication.
OR 4.
A FIRE within the plant PROTECTED AREA that requires firefighting support by an offsite fire response agency to extinguish.
Seismic event as indicated by:
1.
Control Room personnel feel an actual or potential seismic event.
AND 2.
ANY one of the following confirmed in < 15 minutes of the event:
The earthquake resulted in Modified Mercalli Intensity (MMI) > VI and occurred < 3.5 miles of the plant.
The earthquake was magnitude > 6.0 The earthquake was magnitude > 5.0 and occurred < 125 miles from the plant.
NMP-2 seismic instrumentation indicates > 0.075g If the above bullets are not able to be confirmed, then the occurrence of a seismic event is confirmed in a manner deemed appropriate by the Shift Manager or Emergency Director.
1.
Release of a toxic, corrosive, asphyxiant or flammable gas in ANY Table H3 area.
AND 2.
Entry into the room or area is prohibited or impeded.
7 Hazardous Event 1.
Tornado strike within the PROTECTED AREA.
OR 2.
Internal room or area flooding of a magnitude sufficient to require manual or automatic electrical isolation of a SAFETY SYSTEM component required by Technical Specifications for the current operating mode.
OR 3.
Movement of personnel within the PROTECTED AREA is impeded due to an offsite event involving hazardous materials (e.g., an offsite chemical spill or toxic gas release).
OR 4.
A hazardous event that results in onsite conditions sufficient to prohibit the plant staff from accessing the site via personal vehicles.
OR 5.
Intake water level < 238.8 feet.
Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or IMMINENT substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.
Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts, (1) toward site personnel or equipment that could lead to the likely failure of or, (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary.
Other conditions exist which, in the judgment of the Emergency Director, indicate that events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.
Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
System Malfunctions Loss of AC Power RPS Failure Control Room Ind.
Hazard Affecting Safety System M
3 4
5 6
1 Loss of DC Power 2
GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT 1.
Loss of ALL offsite and onsite AC power to 4.16 kV Emergency Buses.
AND 2.
EITHER of the following:
a.
Restoration of at least one 4.16 kV Emergency Bus in < 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is not likely.
OR b.
RPV water level cannot be restored and maintained > -109 inches.
MU1 Bases: 2-74 1
2 3
4 D
1.
Loss of ALL offsite and onsite AC Power to 4.16 kV Emergency Buses.
AND 2.
Failure to restore power to at least one 4.16 kV Emergency Bus from the time of loss of both offsite and onsite AC power in
< 15 minutes.
1.
AC power capability to 4.16 kV Emergency Buses reduced to only one of the following power sources for > 15 minutes:
T-101 N T-101 S DG-102 Emergency Diesel Generator DG-103 Emergency Diesel Generator AND 2.
ANY additional single power source failure will result in a loss of all AC power to SAFETY SYSTEMS.
Loss of ALL offsite AC power capability to 4.16 kV Emergency Buses for > 15 minutes:
T-101 N T-101 S Voltage is < 106 VDC on 125 VDC Battery Boards 11 and 12 for
> 15 minutes.
1.
Loss of ALL offsite and onsite AC power to 4.16 kV Emergency Buses.
AND 2.
Voltage is < 106 VDC on 125 VDC Battery Boards 11 and 12.
AND 3.
ALL AC and Vital DC power sources have been lost for
> 15 minutes.
1.
Automatic scram did not shutdown the reactor as indicated by Reactor Power > 6%.
AND 2.
ALL manual / ARI actions to shutdown the reactor have been unsuccessful as indicated by Reactor Power > 6%.
AND 3.
EITHER of the following conditions exist:
RPV water level cannot be restored and maintained > -109 inches.
OR Heat Capacity Temperature Limit (N1-EOP-4 Figure M) exceeded.
1.
Automatic or manual scram did not shutdown the reactor as indicated by Reactor Power > 6%.
AND 2.
Manual / ARI actions taken at the Reactor Control Console are not successful in shutting down the reactor as indicated by Reactor Power > 6%.
1.
a.
Automatic scram did not shutdown the reactor as indicated by Reactor Power > 6%.
AND b.
Subsequent manual / ARI action taken at the Reactor Control Console is successful in shutting down the reactor as indicated by Reactor Power < 6%.
OR 2.
a.
Manual scram did not shutdown the reactor as indicated by Reactor Power > 6%.
AND b.
EITHER of the following:
- 1. Subsequent manual / ARI action taken at the Reactor Control Console is successful in shutting down the reactor as indicated by Reactor Power < 6%.
- 2. Subsequent automatic scram / ARI is successful in shutting down the reactor as indicated by Reactor Power < 6%.
1.
UNPLANNED event results in the inability to monitor ANY Table M1 parameter from within the Control Room for > 15 minutes.
AND 2.
ANY Table M2 transient in progress.
UNPLANNED event results in the inability to monitor ANY Table M1 parameter from within the Control Room for > 15 minutes.
1.
Dose assessment using actual meteorology indicates doses at or beyond the site boundary of EITHER:
Field survey results at or beyond the site boundary indicate EITHER:
- a. Gamma (closed window) dose rates > 100 mR/hr are expected to continue for > 60 minutes.
- b. Analyses of field survey samples indicate
> 500 mRem CDE Thyroid for 60 minutes of inhalation.
Damage to a loaded cask CONFINEMENT BOUNDARY as indicated by exceeding ANY Table E1 radiation reading.
ISFSI E
This EAL is only applicable to SAFETY SYSTEMs having two (2) or more trains.
1.
a.
The occurrence of ANY of the following hazardous events:
Seismic event (earthquake)
Internal or external flooding event High winds or tornado strike FIRE EXPLOSION Other events with similar hazard characteristics as determined by the Shift Manager AND b.
Event damage has caused indications of degraded performance to one train of a SAFETY SYSTEM required by Technical Specifications for the current operating mode.
AND c.
EITHER of the following:
Event damage has caused indications of degraded performance to a second train of the SAFETY SYSTEM required by Technical Specifications for the current operating mode.
OR Event damage has resulted in VISIBLE DAMAGE to a second train of the SAFETY SYSTEM required by Technical Specifications for the current operating mode.
RCS Leakage 1.
RCS unidentified or pressure boundary leakage in the Drywell
> 10 gpm for > 15 minutes.
OR 2.
RCS identified leakage in the Drywell > 25 gpm for > 15 minutes.
OR 3.
Leakage from the RCS to a location outside the Primary Containment > 25 gpm for > 15 minutes.
7 Comm.
1.
Loss of all Table M3 onsite communication capabilities affecting the ability to perform routine operations.
OR 2.
Loss of all Table M3 offsite communication capabilities affecting the ability to perform offsite notifications.
OR 3.
Loss of all Table M3 NRC communication capabilities affecting the ability to perform NRC notifications.
MA1 Bases: 2-72 1
2 3
4 D
MS1 Bases: 2-70 1
2 3
4 D
MG1 Bases: 2-68 1
2 3
4 D
RU1 Bases: 2-30 1
2 3
4 D
RA1 Bases: 2-28 1
2 3
4 D
RS1 Bases: 2-26 1
2 3
4 D
RG1 Bases: 2-24 1
2 3
4 D
RG2 Bases: 2-33 1
2 3
4 D
RS2 Bases: 2-34 1
2 3
4 D
RA2 Bases: 2-35 1
2 3
4 D
RU2 Bases: 2-38 1
2 3
4 D
RA3 Bases: 2-40 1
2 3
4 D
SFP /
Refueling Pathway Level HS1 Bases: 2-121 1
2 3
4 D
HA1 Bases: 2-123 1
2 3
4 D
HU1 Bases: 2-126 1
2 3
4 D
HA2 Bases: 2-130 1
2 3
4 D
HS2 Bases: 2-128 1
2 3
4 D
HU3 Bases: 2-131 1
2 3
4 D
HU4 Bases: 2-135 1
2 3
4 D
HA5 Bases: 2-137 1
2 3
4 D
HU6 Bases: 2-140 1
2 3
4 D
HG7 Bases: 2-143 1
2 3
4 D
HS7 Bases: 2-144 1
2 3
4 D
HA7 Bases: 2-145 1
2 3
4 D
HU7 Bases: 2-146 1
2 3
4 D
E-HU1 Bases: 2-147 1
2 3
4 D
MS2 Bases: 2-77 1
2 3
4 D
MG2 Bases: 2-75 1
2 3
4 D
MS3 Bases: 2-78 MA3 Bases: 2-80 MU3 Bases: 2-82 1
2 3
4 D
MA5 Bases: 2-89 MA4 Bases: 2-85 1
2 3
4 D
MU4 Bases: 2-87 1
2 3
4 D
MU7 Bases: 2-94 1
2 3
4 D
MU6 Bases: 2-92 1
2 3
4 D
- Turbine runback > 25% thermal reactor power
- Electric Load rejection > 35% full electric load
- Reactor scram
- ADS or Core Spray actuation
- Thermal power oscillations > 10%
Table M2 Significant Transients None None None None RU3 Bases: 2-43 1
2 3
4 D
1.
Offgas radiation monitor RN-12A or RN-12B > UPSCL alarm.
OR 2.
Specific coolant activity > 4.0 µCi/gm I-131 equivalent.
- Reactor Power
- RPV Water Level
- RPV Pressure
- Primary Containment Pressure
- Torus Water Level
- Torus Water Temperature Table M1 Control Room Parameters Table M3 Communication Capabilities System Offsite Onsite NRC X
Gaitronics Hand Held Portable Radio (Station Radio)
X PBX (Conventional Telephone Lines)
Control Room installed satellite phone (non portable)
X X
X X
X X
X Release of gaseous radioactivity resulting in offsite dose greater than 1,000 mRem TEDE or 5,000 mRem CDE Thyroid.
Release of gaseous radioactivity resulting in offsite dose greater than 100 mRem TEDE or 500 mRem CDE Thyroid.
Release of gaseous or liquid radioactivity resulting in offsite dose greater than 10 mRem TEDE or 50 mRem CDE Thyroid.
Release of gaseous or liquid radioactivity greater than 2 times the ODCM limits for 60 minutes or longer.
Spent fuel pool level cannot be restored to at least 316 feet for 60 minutes or longer.
Spent fuel pool level at 316 feet.
Significant lowering of water level above, or damage to, irradiated fuel.
UNPLANNED loss of water level above irradiated fuel Table R3 Areas with Entry Related Mode Applicability Area Entry Related Mode Applicability Reactor Building 198 Northeast Corner 261' North and Shutdown Cooling Room 281' North Turbine Building 291' North Modes 2, 3 and 4 Radiation levels that impede access to equipment necessary for normal plant operations, cooldown or shutdown.
Reactor coolant activity greater than Technical Specification allowable limits.
HOSTILE ACTION within the PROTECTED AREA.
HOSTILE ACTION within the OWNER CONTROLLED AREA or airborne attack threat within 30 minutes.
Confirmed SECURITY CONDITION or threat.
Inability to control a key safety function from outside the Control Room.
Control Room evacuation resulting in transfer of plant control to alternate locations.
Other conditions exist which in the judgment of the Emergency Director warrant declaration of a GENERAL EMERGENCY.
Other conditions exist which in the judgment of the Emergency Director warrant declaration of a SITE AREA EMERGENCY.
Other conditions exist which in the judgment of the Emergency Director warrant declaration of an ALERT.
Other conditions exist which in the judgment of the Emergency Director warrant declaration of an UNUSUAL EVENT.
Gaseous release impeding access to equipment necessary for normal plant operations, cooldown or shutdown.
Hazardous Event Seismic event greater than OBE levels.
FIRE potentially degrading the level of safety of the plant.
Damage to a loaded cask CONFINEMENT BOUNDARY.
Prolonged loss of all offsite and all onsite AC power to emergency buses.
Loss of all offsite and onsite AC power to emergency buses for 15 minutes or longer.
Loss of all but one AC power source to emergency buses for 15 minutes or longer.
Loss of all offsite AC power capability to emergency buses for 15 minutes or longer.
MODE 1 or 2 F
Fission Product Barrier Degradation Loss of ANY two barriers AND Loss or Potential Loss of third barrier.
Loss or Potential Loss of ANY two barriers.
ANY Loss or ANY Potential Loss of either Fuel Clad or RCS None FG1 1
2 3
4 D
FA1 1
2 3
4 D
FS1 1
2 3
4 D
Bases: 2-44 Bases: 2-45 Bases: 2-46 Loss of all AC and Vital DC power sources for 15 minutes or longer.
Loss of all Vital DC power for 15 minutes or longer.
Inability to shutdown the reactor causing a challenge to RPV water level or RCS heat removal.
Automatic or manual scram fails to shutdown the reactor, and subsequent manual actions taken at the Reactor Control Console are not successful in shutting down the reactor.
Automatic or manual scram fails to shutdown the reactor.
UNPLANNED loss of Control Room indications for 15 minutes or longer with a significant transient in progress.
UNPLANNED loss of Control Room indications for 15 minutes or longer.
Hazardous event affecting a SAFETY SYSTEM required for the current operating mode.
RCS leakage for 15 minutes or longer.
Loss of all onsite or offsite communication capabilities.
See Note: A See Note: A See Notes: A, B, C, D See Notes: A, C, E See Note: A See Note: F See Note: A See Note: G See Note: G See Notes: A, L See Notes: L, M See Note: N See Notes: L, P See Note: A See Note: A See Note: A See Note: A See Note: A See Note: A See Note: A See Note: A See Notes: H, J, K See Note: A None None None None None
- Reactivity Control (ability to shutdown the reactor and keep it shutdown)
- RPV Water Level (ability to cool the core)
- RCS Heat Removal (ability to maintain a heat sink)
Table H1 Safety Functions Reactor Building (when inerted the Drywell is exempt)
Control Room Screenhouse Turbine Building
- 11 and 12 Battery Rooms
- 11 and 12 Battery Board Rooms
- Cable Spreading Room
- 291' North
- Diesel Generator Engine and Board Rooms Table H2 Areas Table R1 Refuel Floor ARMs
- ARM 18 (West end of shield wall)
- ARM 25 (Reactor Building - east wall)
- ARM 29 Refuel Bridge (Low Range)
- Refuel Bridge (High Range)
- Reactor Building Vent Radiation Monitor
- Main Control Room
- Central Alarm Station - (by survey)
Table R2 Areas Requiring Continuous Occupancy 1
2 3
4 D
1 2
3 4
D Table H3 Areas with Entry Related Mode Applicability Area Entry Related Mode Applicability Reactor Building 198 Northeast Corner 261' North and Shutdown Cooling Room 281' North Turbine Building 291' North Modes 2, 3 and 4 None
`
Notes A.
The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.
B.
If an ongoing release is detected and the release start time is unknown, assume that the release duration has exceeded 15 minutes.
C.
Classification based on effluent monitor readings assumes that a release path to the environment is established. If the effluent flow past an effluent monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.
D.
The pre-calculated effluent monitor values presented in EAL #1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.
E.
If an ongoing release is detected and the release start time is unknown, assume that the release duration has exceeded 60 minutes.
F.
If the equipment in the room or area listed in Table R3 was already inoperable, or not available, before the event occurred, then no emergency classification is warranted.
G.
A manual action is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core, and does not include manually driving in control rods or implementation of boron injection strategies.
H.
If the affected SAFETY SYSTEM train was already inoperable before the hazardous event occurred, then this emergency classification is not warranted.
J.
If the hazardous event only resulted in VISIBLE DAMAGE, with no indications of degraded performance to at least one train of a SAFETY SYSTEM, then this emergency classification is not warranted.
K.
If a hazardous event occurs and it is determined that the conditions of MA5 are not met then assess the event via HU3, HU4, or HU6.
L.
Escalation of the emergency classification level would be via IC CA2 or MA5.
M. For emergency classification if EAL #2 is not able to be confirmed, then the occurrence of a seismic event is confirmed in a manner deemed appropriate by the Shift Manager or Emergency Director in < 15 minutes of the event.
N.
If the equipment in the listed room or area was already inoperable, or not available, before the event occurred, then no emergency classification is warranted.
P.
EAL #4 does not apply to routine traffic impediments such as fog, snow, ice, or vehicle breakdowns or accidents.
None None None Nine Mile Point Nuclear Station Unit 1 Modes:
1 Power Operation 2
Hot Shutdown Defueled D
4 Refuel Cold Shutdown 3
EP-AA-1013 Addendum 3, Appendix 1 Revision 01 NMP Unit 1 EAL Wallboard Page 1 of 2 HOT MATRIX 1
2 3
4 D
None None Table E1 Radiation Readings Cask Type Amendment 10 Amendment 14 - HSM Amendment 14 - HSM-H Labeled 61BT Labeled 61BTH - Type 1
> 800 mrem/hr 3 feet from the HSM surface OR
> 200 mrem/hr outside the HSM door on centerline of DSC OR
> 40 mrem/hr end of shield wall exterior
> 1400 mrem/hr on the HSM or HSM-H front surface OR
> 200 mrem/hr on the HSM or HSM-H door centerline OR
> 40 mrem/hr on the end shield wall exterior
> 400 mrem/hr on the HSM front surface OR
> 200 mrem/hr on the HSM door OR
> 30 mrem/hr on the end shield wall exterior
> 1350 mrem/hr on the HSM-H front surface OR
> 4 mrem/hr on the HSM-H door OR
> 40 mrem/hr on the end shield wall exterior None None