ML21034A474

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Handouts to Applicants (Folder 3)
ML21034A474
Person / Time
Site: Nine Mile Point Constellation icon.png
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)
v • d • e


Text

3.0 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 4.0 SURVEILLANCE REQUIREMENT (SR} APPLICABILITY AMENDMENT NO. 142,182,207 27

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT

c. 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 Where: = 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.

d. The liquid poison solution temperature shall not be less than the temperature presented in Figure (2) In accordance with the Surveillance Frequency 3.1.2.b. Control Program -
e. If Specifications "a" through "d" are not met, Solution volume shall be checked. In addition, the initiate normal orderly shutdown within one hour. 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.

AMENDMENT NO. 142,166,222,239 45

RADIOACTIVE EFFLUENT INSTRUMENTATION - LIQUID D 3/4.6.14 CONTROLS SURVEILLANCE REQUIREMENT DLCO 3.6.14 RADIOACTIVE EFFLUENT INSTRUMENTATION DSR 4.6.14 RADIOACTIVE EFFLUENT INSTRUMENTATION Applicability: Applicability:

Applies to the functionality of plant instrumentation that Applies to the surveillance of instrumentation that monitors monitors plant effluents. plant effluents.

Objective: Objective:

To assure the functionality of instrumentation to monitor the To verify operation of monitoring instrumentation.

release of radioactive plant effluents.

Specification:

Specification:

a. Liquid Effluent
a. Liquid Effluent Each radioactive liquid effluent monitoring The radioactive liquid effluent monitoring instru- instrumentation channel shall be demonstrated functional mentation channels shown in Table D 3.6.14-1 shall by performance of the sensor check, source check, instrument channel calibration and channel test be functional with their alarm setpoints set to operations at the frequencies shown in Table D 4.6.14-1.

ensure that the limits of Control DLCO 3.6.15.a.1 are not exceeded. The alarm Records - Auditable records shall be maintained, in setpoints of these channels shall be determined and accordance with procedures in Part II, of all radioactive adjusted in accordance with the methodology and liquid effluent monitoring instrumentation alarm parameters in Part II. setpoints. Setpoints and setpoint calculations shall be available for review to ensure that the limits of Control With a radioactive liquid effluent monitoring DLCO 3.6.15.a.1 are met.

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.

CY-NM-170-301 Revision 37 I 3.1-1 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 3.1-2 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 1(c) At all times(b) 1(d) At all times(i)

B. Service Water System Effluent Line

2. Flow Rate Measurement Devices 1(e) At all times A. Liquid Radwaste Effluent Line B. Discharge Canal
3. Tank Level Indicating Devices(g) 1(f) At all times A. Outside Liquid Radwaste Storage Tanks
    • Pumps curves or rated capacity will be utilized to estimate flow.

CY-NM-170-301 Revision 37 I 3.1-3 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 3.1-4 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 Calibration Channel Test

1. Gross Beta or Gamma Radioactivity Monitors
a. Liquid Radwaste Effluent Line Once/day* Once/discharge* Once/3 months(a)* Once/year(b)*

Line Once/day Once/92 days Once/184 days(a) Once/24 months(b)

b. Service Water Effluent Line
2. Flow Rate Measurement Devices Once/day(c) None None Once/24 months*
a. Liquid Radwaste Effluent Line None None None Once/year
b. Discharge Canal(d)
3. Tank Level Indicating Devices(e) Once/day** None Once/3 months Once/18 months
a. Outside Liquid Radwaste Storage Tanks
  • 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 3.1-5 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 3.1-6 January 2020

RADIOACTIVE EFFLUENT INSTRUMENTATION - GASEOUS D 3/4.6.14 CONTROLS SURVEILLANCE REQUIREMENT

b. Gaseous Process and Effluent b. Gaseous Process and Effluent The radioactive gaseous process and effluent Each radioactive gaseous process and monitoring instrumentation channels shown in Table D effluent monitoring instrumentation channel 3.6.14-2 shall be functional. The Offgas process shall be demonstrated functional by monitor alarm setpoint shall be set to ensure that the performance of the sensor check, source limits of Technical Specification 3.6.15 are not check, instrument channel calibration and exceeded. The Effluent monitor alarm setpoints shall instrument channel test operations at the be set to ensure that the limits of Control DLCO frequencies shown in Table D 4.6.14-2.

3.6.15.b.1 are not exceeded. The alarm setpoints of Auditable records shall be maintained of these channels shall be determined and adjusted in the calculations made, in accordance with accordance with the methodology and parameters in procedures in Part II, of radioactive Part II. gaseous process and effluent monitoring instrumentation alarm setpoints. Setpoints With a radioactive gaseous process and effluent and setpoint calculations shall be available monitoring instrumentation channel alarm setpoint less for review to ensure that the limits of conservative than required by the above specification, Control DLCO 3.6.15.b.1 are met.

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.

CY-NM-170-301 Revision 37 I 3.1-7 January 2020

RADIOACTIVE EFFLUENT INSTRUMENTATION - GASEOUS D 3/4.6.14 TABLE D 3.6.14-2 RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION Minimum Instrument Channels Functional Applicability Action

1. Stack Effluent Monitoring
a. Noble Gas Activity Monitors (1) High Range 2 * (a)

(2) Low Range 1 * (i)

b. Iodine Sampler Cartridge 1 * (b)
c. Particulate Sampler Filter 1 * (b)
d. Sampler Flow Rate Measuring Device 1 * (c)
e. Stack Gas Flow Rate Measuring Device 1 * (c), (d)
2. Deleted
  • At all times.
    • Note Deleted.

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 (cont'd)

RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION Minimum Instrument Channels Functional Applicability Action

3. Condenser Air Ejector Process Monitor (Offgas System Recombiner Discharge)
a. Noble Gas Activity Monitor 2 *** (g)
b. Offgas System Flow Rate 1 *** (c)

Measuring Device

4. Emergency Condenser System Effluent (h)
a. Noble Gas Activity Monitor 1 per vent ****
        • 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 3.1-9 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, Attachment 3 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 3.1-10 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 3.1-11 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 Once/day(a) Once/92 days Once/184 days(g) Once/24 months(b)

(High Range and Low Range)

b. Iodine Sampler Cartridge None None None None
c. Particulate Sampler Filter None None None None
d. Sampler Flow Rate Measuring Device Once/day(a) None None Once/24 months
e. Stack Gas Flow Rate Measuring Device Once/day None None Once/24 months
2. Deleted
3. Condenser Air Ejector Process Monitor (Offgas System Recombiner Discharge)
a. Noble Gas Activity Monitor Once/day(f) Once/92 days Once/24 months(c) Once/24 months(b)
b. Offgas System Flow Rate Measuring Once/day(f) None None Once/24 months Device
4. Emergency Condenser System Effluent Once/day(h) Once/92 days Once184 days(g) Once/24 months(b)
a. Noble Gas Activity Monitor CY-NM-170-301 Revision 37 I 3.1-12 January 2020

CY-NM-170-301 Revision 37 I 3.1-13 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.

CY-NM-170-301 Revision 37 I 3.1-14 January 2020

Calculations M Heat Capacity Temperature Limit 200 180 BAD Torus Temperature (°F) 160 170°F @ 53 psig 140 GOOD Torus Water Level 120 10.5 - 11.25 ft 9.0 - 10.5 and 110°F @ 1090 psig Use EOP-1 Att 23 for torus water 11.25 - 13.0 ft 100 levels below 9.0 ft or above 13.0 ft 80 0 100 200 300 400 500 600 700 800 900 1000 1100 RPV Pressure (psig)

Figure 3-11: Heat Capacity Temperature Limit Page 39 NER-1M-095, REV 05.00

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT RG1 1 2 3 4 D Bases: 2-24 RS1 1 2 3 4 D Bases: 2-26 RA1 1 2 3 4 D Bases: 2-28 RU1 1 2 3 4 D Bases: 2-30 MG1 1 2 3 4 D Bases: 2-68 MS1 1 2 3 4 D Bases: 2-70 MA1 1 2 3 4 D Bases: 2-72 MU1 1 2 3 4 D Bases: 2-74 R M Release of gaseous radioactivity resulting in offsite dose Release of gaseous radioactivity resulting in offsite dose Release of gaseous or liquid radioactivity resulting in offsite Release of gaseous or liquid radioactivity greater than 2 times Prolonged loss of all offsite and all onsite AC power to Loss of all offsite and onsite AC power to emergency buses for Loss of all but one AC power source to emergency buses for Loss of all offsite AC power capability to emergency buses for greater than 1,000 mRem TEDE or 5,000 mRem CDE Thyroid. greater than 100 mRem TEDE or 500 mRem CDE Thyroid. dose greater than 10 mRem TEDE or 50 mRem CDE Thyroid. the ODCM limits for 60 minutes or longer. emergency buses. 15 minutes or longer. 15 minutes or longer. 15 minutes or longer.

See Note: A See Note: A See Notes: A, B, C, D See Notes: A, C, E See Note: A See Note: A See Note: A See Note: A

1. Dose assessment using actual meteorology indicates doses at or 1. Dose assessment using actual meteorology indicates doses at or 1. Reading on Stack (RN 10 A/B) Effluent Monitor > 1.5 E+05 cps for 1. Reading on the Rad Waste Discharge effluent monitor 1. Loss of ALL offsite and onsite AC power to 4.16 kV Emergency 1. Loss of ALL offsite and onsite AC Power to 4.16 kV Emergency 1. AC power capability to 4.16 kV Emergency Buses reduced to only Loss of ALL offsite AC power capability to 4.16 kV Emergency Buses beyond the site boundary of EITHER: beyond the site boundary of EITHER: > 15 minutes. > 2x alarm setpoint established by a current radioactive release 1 Buses. Buses. one of the following power sources for > 15 minutes: for > 15 minutes:

Abnormal Radiation Levels \ Radiological Effluents

a. > 1000 mRem TEDE a. > 100 mRem TEDE discharge permit for > 60 minutes. AND AND
  • T-101 N
  • T-101 N OR OR OR 2. Dose assessment using actual meteorology indicates doses at or OR Loss of 2. EITHER of the following: 2. Failure to restore power to at least one 4.16 kV Emergency Bus
  • T-101 S
  • T-101 S
b. > 5000 mRem CDE Thyroid b. > 500 mRem CDE Thyroid beyond the site boundary of EITHER: 2. Reading on Stack (RN 10 A/B) Effluent Monitor > 2.85 E+02 cps AC Power a. Restoration of at least one 4.16 kV Emergency Bus from the time of loss of both offsite and onsite AC power in
a. > 10 mRem TEDE in < 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is not likely.
2. Field survey results at or beyond the site boundary indicate 2. Field survey results at or beyond the site boundary indicate AND EITHER: EITHER: 3. Confirmed sample analyses for gaseous or liquid releases indicate b. RPV water level cannot be restored and
b. > 50 mRem CDE Thyroid 2. ANY additional single power source failure will result in a loss of all concentrations or release rates > 2x ODCM Limit with a release maintained > -109 inches.
a. Gamma (closed window) dose rates > 1000 mR/hr are a. Gamma (closed window) dose rates > 100 mR/hr are OR duration of > 60 minutes. AC power to SAFETY SYSTEMS.

Offsite Rad expected to continue for > 60 minutes. expected to continue for > 60 minutes. 3. Analysis of a liquid effluent sample indicates a concentration or Conditions OR OR release rate that would result in doses greater than EITHER of the MG2 1 2 3 4 D Bases: 2-75 MS2 1 2 3 4 D Bases: 2-77

b. Analyses of field survey samples indicate following at or beyond the site boundary:
b. Analyses of field survey samples indicate Loss of all AC and Vital DC power sources for 15 minutes or Loss of all Vital DC power for 15 minutes or longer.

> 5000 mRem CDE Thyroid for 60 minutes of inhalation. > 500 mRem CDE Thyroid for 60 minutes of inhalation. a. 10 mRem TEDE for 60 minutes of exposure longer.

OR OR

b. 50 mRem CDE Thyroid for 60 minutes of exposure 2 See Note: A
1. Loss of ALL offsite and onsite AC power to 4.16 kV Emergency See Note: A Voltage is < 106 VDC on 125 VDC Battery Boards 11 and 12 for None None Loss of Buses. > 15 minutes.
4. Field survey results at or beyond the site boundary indicate DC Power AND EITHER:
a. Gamma (closed window) dose rates > 10 mR/hr are 2. Voltage is < 106 VDC on 125 VDC Battery Boards 11 and 12.

expected to continue for > 60 minutes. AND OR 3. ALL AC and Vital DC power sources have been lost for

b. Analyses of field survey samples indicate > 50 mRem > 15 minutes.

CDE Thyroid for 60 minutes of inhalation.

MS3 1 2 3 4 D Bases: 2-78 MA3 1 2 3 4 D Bases: 2-80 MU3 1 2 3 4 D Bases: 2-82 RG2 1 2 3 4 D Bases: 2-33 RS2 1 2 3 4 D Bases: 2-34 RA2 1 2 3 4 D Bases: 2-35 RU2 1 2 3 4 D Bases: 2-38 Inability to shutdown the reactor causing a challenge to RPV Automatic or manual scram fails to shutdown the reactor, and Automatic or manual scram fails to shutdown the reactor.

Significant lowering of water level above, or damage to, UNPLANNED loss of water level above irradiated fuel water level or RCS heat removal. subsequent manual actions taken at the Reactor Control Spent fuel pool level cannot be restored to at least 316 feet for Spent fuel pool level at 316 feet.

irradiated fuel. Console are not successful in shutting down the reactor.

60 minutes or longer.

See Note: G See Note: G 2 See Note: A 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 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).

1. Uncovery of irradiated fuel in the REFUELING PATHWAY. 1. a. UNPLANNED water level drop in the REFUELING PATHWAY as indicated by:
1. Automatic scram did not shutdown the reactor as indicated by Reactor Power > 6%.
1. Automatic or manual scram did not shutdown the reactor as indicated by Reactor Power > 6%.
1. a. Automatic scram did not shutdown the reactor as indicated by Reactor Power > 6%.

OR AND AND AND SFP Rad Onsite / (PNL-54-65H) for > 60 minutes.

  • SFP water level < low water level alarm.

System Malfunctions

2. Damage to irradiated fuel resulting in a release of radioactivity from 2. ALL manual / ARI actions to shutdown the reactor have been 2. Manual / ARI actions taken at the Reactor Control Console are not b. Subsequent manual / ARI action taken at the Reactor Refueling Conditions 3

the fuel as indicated by ANY Table R1 Radiation Monitor Alarm. OR unsuccessful as indicated by Reactor Power > 6%. successful in shutting down the reactor as indicated by Reactor Control Console is successful in shutting down the reactor as Pathway

& indicated by Reactor Power < 6%.

Power > 6%.

Level AND Spent Fuel Table R1 OR

  • Indication or report of a drop in water level in the None OR Events REFUELING PATHWAY. 3. EITHER of the following conditions exist:
3. Lowering of spent fuel pool level to 326 feet as indicated on RPS Refuel Floor ARMs Table R3 LI-54-65A or LI-54-65B on SFP monitoring panel (PNL-54-65H). AND Failure
  • RPV water level cannot be restored and
2. a. Manual scram did not shutdown the reactor as indicated by Reactor Power > 6%.

Areas with Entry Related Mode Applicability b. UNPLANNED Area Radiation Monitor reading rise on ANY maintained > -109 inches.

  • ARM 18 (West end of shield wall) AND radiation monitor in Table R1. OR Entry Related
  • ARM 25 (Reactor Building - east wall) Area b. EITHER of the following:

Mode Applicability

  • Heat Capacity Temperature Limit (N1-EOP-4 Figure M)
  • ARM 29 Refuel Bridge (Low Range) RA3 1 2 3 4 D Bases: 2-40 RU3 1 2 3 4 D Bases: 2-43 exceeded. 1. Subsequent manual / ARI action taken at the Reactor Reactor Building Control Console is successful in shutting down the Radiation levels that impede access to equipment necessary for Reactor coolant activity greater than Technical Specification reactor as indicated by Reactor Power < 6%.
  • Refuel Bridge (High Range) 198 Northeast Corner normal plant operations, cooldown or shutdown. allowable limits.

261' North and Shutdown Cooling OR

  • Reactor Building Vent Radiation Monitor Modes 2, 3 3 Room See Note: F 2. Subsequent automatic scram / ARI is successful in and 4 shutting down the reactor as indicated by Reactor 281' North 1. Dose rate > 15 mR/hr in ANY of the areas in Table R2. 1. Offgas radiation monitor RN-12A or RN-12B > UPSCL alarm. Power < 6%.

Turbine Building OR OR CR / CAS Table R2 Radiation 291' North 2. UNPLANNED event results in radiation levels that prohibit or 2. Specific coolant activity > 4.0 µCi/gm I-131 equivalent. MA4 1 2 3 4 D Bases: 2-85 MU4 1 2 3 4 D Bases: 2-87 Areas Requiring Continuous Occupancy significantly impede access to ANY of the areas in Table R3. UNPLANNED loss of Control Room indications for 15 minutes or UNPLANNED loss of Control Room indications for 15 minutes or OR longer with a significant transient in progress. longer.

  • Main Control Room Fuel Clad Degradation
  • Central Alarm Station - (by survey) 4 None None See Note: A See Note: A Control 1. UNPLANNED event results in the inability to monitor ANY Table M1 UNPLANNED event results in the inability to monitor ANY Table M1 Room parameter from within the Control Room for > 15 minutes. parameter from within the Control Room for > 15 minutes.

Ind. AND HS1 1 2 3 4 D Bases: 2-121 HA1 1 2 3 4 D Bases: 2-123 HU1 1 2 3 4 D Bases: 2-126 2. ANY Table M2 transient in progress.

H HOSTILE ACTION within the PROTECTED AREA. HOSTILE ACTION within the OWNER CONTROLLED AREA or Confirmed SECURITY CONDITION or threat.

airborne attack threat within 30 minutes.

MA5 1 2 3 4 D Bases: 2-89 1 None 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.

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.

Table M1 Hazardous event affecting a SAFETY SYSTEM required for the current operating mode.

Hostile OR Control Room Parameters Action OR See Notes: H, J, K

2. Notification by the Security Supervisor that a HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED 2. A validated notification from the NRC providing information of an
  • Reactor Power This EAL is only applicable to SAFETY SYSTEMs having two (2) or AREA. aircraft threat. more trains.
3. Notification by the Security Supervisor of a SECURITY
  • RPV Pressure 1. a. The occurrence of ANY of the following hazardous events:

CONDITION that does not involve a HOSTILE ACTION.

  • Internal or external flooding event
  • Torus Water Level HS2 1 2 3 4 D Bases: 2-128 HA2 1 2 3 4 D Bases: 2-130
  • Torus Water Temperature Inability to control a key safety function from outside the Control Room evacuation resulting in transfer of plant
  • FIRE Table H1 Control Room. control to alternate locations.

5

  • EXPLOSION 2
  • Reactivity Control Safety Functions See Note: A
1. A Control Room evacuation has resulted in plant control being A Control Room evacuation has resulted in plant control being Hazard None
  • Other events with similar hazard characteristics as determined by the Shift Manager None Transfer of (ability to shutdown the reactor and keep it shutdown) transferred from the Control Room to alternate locations transferred from the Control Room to alternate locations None AND Affecting Plant per N1-SOP-21.2, Control Room Evacuation. per N1-SOP-21.2, Control Room Evacuation. Safety b. Event damage has caused indications of degraded Control
  • RPV Water Level (ability to cool the core)

System Table M2 performance to one train of a SAFETY SYSTEM required by AND Significant Transients Technical Specifications for the current operating mode.

  • RCS Heat Removal (ability to maintain a heat sink) 2. Control of ANY Table H1 key safety function is not reestablished in

< 15 minutes. AND

  • Turbine runback > 25% thermal reactor power
c. EITHER of the following:
  • Electric Load rejection > 35% full electric load
  • Event damage has caused indications of degraded HU3 1 2 3 4 D Bases: 2-131
  • Reactor scram performance to a second train of the SAFETY SYSTEM required by Technical Specifications for the current FIRE potentially degrading the level of safety of the plant. operating mode.
  • Thermal power oscillations > 10%

A. The Emergency Director should declare the event promptly upon determining that the Table H2 See Notes: A, L

  • Event damage has resulted in VISIBLE DAMAGE to a second train of the SAFETY SYSTEM required by applicable time has been exceeded, or will likely be exceeded. Areas 1. A FIRE in ANY Table H2 area is not extinguished in < 15 minutes Technical Specifications for the current operating mode.

Hazards & Other Conditions Affecting Plant Safety of ANY of the following FIRE detection indications:

B. If an ongoing release is detected and the release start time is unknown, assume that

  • Reactor Building (when inerted the Drywell is
  • Report from the field (i.e., visual observation) the release duration has exceeded 15 minutes. exempt)

MU6 1 2 3 4 D Bases: 2-92

  • Receipt of multiple (more than 1) fire alarms or indications C. Classification based on effluent monitor readings assumes that a release path to the
  • Control Room RCS leakage for 15 minutes or longer.
  • Field verification of a single fire alarm environment is established. If the effluent flow past an effluent monitor is known to have
  • Screenhouse OR 3 stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.
  • Turbine Building 2. a. Receipt of a single fire alarm in ANY Table H2 area (i.e., no See Note: A Fire 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
  • 11 and 12 Battery Rooms
  • 11 and 12 Battery Board Rooms other indications of a FIRE).

AND 6 None None None

1. RCS unidentified or pressure boundary leakage in the Drywell

> 10 gpm for > 15 minutes.

b. The existence of a FIRE is not verified in < 30 minutes of RCS actual meteorology are available.
  • Cable Spreading Room alarm receipt.

OR

` Leakage E. If an ongoing release is detected and the release start time is unknown, assume that

  • 291' North OR Table M3 2. RCS identified leakage in the Drywell > 25 gpm for > 15 minutes.

the release duration has exceeded 60 minutes.

  • Diesel Generator Engine and Board Rooms
3. A FIRE within the plant PROTECTED AREA not extinguished in Communication Capabilities OR F. If the equipment in the room or area listed in Table R3 was already inoperable, or not < 60 minutes of the initial report, alarm or indication. 3. Leakage from the RCS to a location outside the Primary System Onsite Offsite NRC Containment > 25 gpm for > 15 minutes.

available, before the event occurred, then no emergency classification is warranted. OR Gaitronics X G. A manual action is any operator action, or set of actions, which causes the control rods 4. A FIRE within the plant PROTECTED AREA that requires firefighting support by an offsite fire response agency to extinguish. Hand Held Portable to be rapidly inserted into the core, and does not include manually driving in control rods Radio (Station Radio)

X or implementation of boron injection strategies.

PBX (Conventional MU7 1 2 3 4 D Bases: 2-94 X X X H. If the affected SAFETY SYSTEM train was already inoperable before the hazardous HU4 1 2 3 4 D Bases: 2-135 Telephone Lines) Loss of all onsite or offsite communication capabilities.

event occurred, then this emergency classification is not warranted. Seismic event greater than OBE levels. Control Room installed satellite phone (non X X J. If the hazardous event only resulted in VISIBLE DAMAGE, with no indications of portable) degraded performance to at least one train of a SAFETY SYSTEM, then this emergency classification is not warranted.

See Notes: L, M Seismic event as indicated by:

7 None ENS X X

X None

1. Loss of all Table M3 onsite communication capabilities affecting the ability to perform routine operations.

K. If a hazardous event occurs and it is determined that the conditions of MA5 are not met Comm.

RECS OR

1. Control Room personnel feel an actual or potential seismic event.

then assess the event via HU3, HU4, or HU6.

4 L. Escalation of the emergency classification level would be via IC CA2 or MA5.

2.

AND ANY one of the following confirmed in < 15 minutes of the event:

2. Loss of all Table M3 offsite communication capabilities affecting the ability to perform offsite notifications.

OR Earthquake M. For emergency classification if EAL #2 is not able to be confirmed, then the occurrence None

  • The earthquake resulted in Modified Mercalli Intensity of a seismic event is confirmed in a manner deemed appropriate by the Shift Manager 3. Loss of all Table M3 NRC communication capabilities affecting the (MMI) > VI and occurred < 3.5 miles of the plant.

ability to perform NRC notifications.

or Emergency Director in < 15 minutes of the event.

  • The earthquake was magnitude > 6.0 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. occurred < 125 miles from the plant. Bases: 2-45 Bases: 2-46

  • NMP-2 seismic instrumentation indicates > 0.075g FG1 1 2 3 4 D Bases: 2-44 FS1 1 2 3 4 D FA1 1 2 3 4 D P. EAL #4 does not apply to routine traffic impediments such as fog, snow, ice, or vehicle 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 breakdowns or accidents.
  • If the above bullets are not able to be confirmed, then the None occurrence of a seismic event is confirmed in a manner deemed appropriate by the Shift Manager or Emergency Fission Product Barrier Director. Degradation HA5 1 2 3 4 D Fission Product Barrier Matrix Bases: 2-137 Gaseous release impeding access to equipment necessary for Table H3 normal plant operations, cooldown or shutdown.

5 None Areas with Entry Related Mode Applicability Area Entry Related See Note: N

1. Release of a toxic, corrosive, asphyxiant or flammable gas in None

`

FC - Fuel Clad RC - Reactor Coolant System CT - Containment Toxic Gas Mode Applicability ANY Table H3 area. Loss Potential Loss Loss Potential Loss Loss Potential Loss Reactor Building AND Coolant activity > 300 µCi/gm I-131 198 Northeast Corner 2. Entry into the room or area is prohibited or impeded.

261' North and Shutdown Cooling Room Modes 2, 3 1 equivalent.

None None None None None and 4 HU6 1 2 3 4 D Bases: 2-140 RCS Activity 281' North Bases: 2-47 Hazardous Event Turbine Building 1. SAP entry required. 2. RPV water level cannot be restored 1. RPV water level cannot be restored SAP entry required.

2 291' North and maintained > -84 inches. and maintained > -84 inches.

OR OR None None See Notes: L, P

1. Tornado strike within the PROTECTED AREA. RPV Water Level 3. RPV water level cannot be 2. RPV water level cannot be determined. determined.

OR Bases: 2-48 Bases: 2-48 Bases: 2-52 Bases: 2-60

2. Internal room or area flooding of a magnitude sufficient to require 1. a. Primary Containment 1. UNPLANNED rapid drop in Primary 3. Torus pressure > 35 psig.

manual or automatic electrical isolation of a SAFETY SYSTEM pressure > 3.5 psig. Containment pressure following OR 6 component required by Technical Specifications for the current operating mode.

AND Primary Containment pressure rise.

4. a. Primary Containment hydrogen Hazardous None None None 3.

OR Movement of personnel within the PROTECTED AREA is impeded 3 None None

b. Primary Containment pressure rise is due to RCS leakage.

None 2.

OR Primary Containment pressure response not consistent with LOCA concentration > 6%.

AND Event Primary due to an offsite event involving hazardous materials (e.g., an Containment conditions. b. Primary Containment oxygen offsite chemical spill or toxic gas release). Pressure / concentration > 5%.

OR Conditions OR

4. A hazardous event that results in onsite conditions sufficient to 5. Heat Capacity Temperature Limit prohibit the plant staff from accessing the site via personal vehicles. (N1-EOP-4 Figure M) exceeded.

OR Bases: 2-54 Bases: 2-61 Bases: 2-61

5. Intake water level < 238.8 feet. 1. UNISOLABLE Main Steam line, EC 3. UNISOLABLE primary system leakage steam line, Feedwater, or RWCU line that results in EITHER of the following:

break.

a. ANY area temperature OR 4

> N1-EOP-5 Detail T alarm HG7 1 2 3 4 D Bases: 2-143 HS7 1 2 3 4 D Bases: 2-144 HA7 1 2 3 4 D Bases: 2-145 HU7 1 2 3 4 D Bases: 2-146 None None 2. RPV Blowdown is required. set point. None None Other conditions exist which in the judgment of the Emergency Other conditions exist which in the judgment of the Other conditions exist which in the judgment of the Other conditions exist which in the judgment of the OR Director warrant declaration of a GENERAL EMERGENCY. Emergency Director warrant declaration of a SITE AREA Emergency Director warrant declaration of an ALERT. Emergency Director warrant declaration of an UNUSUAL EVENT. RCS Leak Rate

b. ANY area radiation level EMERGENCY.

7

> N1-EOP-5 Detail R alarm Other conditions exist which in the judgment of the Emergency Director Other conditions exist which in the judgment of the Emergency Director Other conditions exist which, in the judgment of the Emergency Director, Other conditions exist which in the judgment of the Emergency Director set point.

indicate that events are in progress or have occurred which involve indicate that events are in progress or have occurred which involve indicate that events are in progress or have occurred which involve an indicate that events are in progress or have occurred which indicate a Bases: 2-55 Bases: 2-55 actual or IMMINENT substantial core degradation or melting with actual or likely major failures of plant functions needed for protection of actual or potential substantial degradation of the level of safety of the potential degradation of the level of safety of the plant or indicate a 5

Judgment Drywell radiation reading > 1.1 E+03 R/hr Drywell radiation reading > 100 R/hr. Drywell radiation reading > 1.1 E+04 R/hr potential for loss of containment integrity or HOSTILE ACTION that the public or HOSTILE ACTION that results in intentional damage or plant or a security event that involves probable life threatening risk to security threat to facility protection has been initiated. No releases of (1,100 R/hr). (11,000 R/hr).

results in an actual loss of physical control of the facility. Releases can malicious acts, (1) toward site personnel or equipment that could lead to site personnel or damage to site equipment because of HOSTILE radioactive material requiring offsite response or monitoring are None None None be reasonably expected to exceed EPA Protective Action Guideline the likely failure of or, (2) that prevent effective access to equipment ACTION. Any releases are expected to be limited to small fractions of expected unless further degradation of safety systems occurs. Primary exposure levels offsite for more than the immediate site area. needed for the protection of the public. Any releases are not expected the EPA Protective Action Guideline exposure levels. Containment to result in exposure levels which exceed EPA Protective Action Radiation Guideline exposure levels beyond the site boundary. Bases: 2-50 Bases: 2-58 Bases: 2-63

1. UNISOLABLE direct downstream pathway to the environment exists E-HU1 1 2 3 4 D Bases: 2-147 following automatic or manual isolation E

signal.

Table E1 Damage to a loaded cask CONFINEMENT BOUNDARY.

Radiation Readings OR

2. Intentional Primary Containment Cask Type Amendment 10

> 800 mrem/hr 3 feet from the HSM surface Amendment 14 - HSM Amendment 14 - HSM-H Damage to a loaded cask CONFINEMENT BOUNDARY as indicated by exceeding ANY Table E1 radiation reading.

6 None None None None venting/purging per EOPs or SAPs due to accident conditions.

OR None Primary OR Containment 3. UNISOLABLE primary system leakage Isolation Failure that results in EITHER of the following:

Labeled 61BT * > 200 mrem/hr outside the HSM door on centerline of DSC None None a. Maximum safe general area OR temperature > 135 ºF.

None

  • > 40 mrem/hr end of shield wall exterior OR ISFSI
b. Maximum safe area radiation
  • > 1400 mrem/hr on the HSM or HSM-H * > 400 mrem/hr on the HSM front surface * > 1350 mrem/hr on the HSM-H front level > 8 R/hr.

front surface surface OR Bases: 2-64 OR OR

  • > 200 mrem/hr on the HSM door
1. ANY condition in the opinion of the 2. ANY condition in the opinion of the 1. ANY condition in the opinion of the 2. ANY condition in the opinion of the 1. ANY condition in the opinion of the 2. ANY condition in the opinion of the 7

Labeled 61BTH - Type 1 * > 200 mrem/hr on the HSM or HSM-H door * > 4 mrem/hr on the HSM-H door OR Emergency Director that indicates Emergency Director that indicates Emergency Director that indicates Emergency Director that indicates Emergency Director that indicates Loss Emergency Director that indicates centerline OR Loss of the Fuel Clad barrier. Potential Loss of the Fuel Clad barrier. Loss of the RCS barrier. Potential Loss of the RCS barrier. of the Containment barrier Potential Loss of the Containment

  • > 30 mrem/hr on the end shield wall OR Emergency barrier.

exterior * > 40 mrem/hr on the end shield wall

  • > 40 mrem/hr on the end shield wall exterior Director exterior Judgement Bases: 2-51 Bases: 2-51 Bases: 2-59 Bases: 2-59 Bases: 2-67 Bases: 2-67 MODE 1 or 2 EP-AA-1013 Addendum 3, Appendix 1 HOT MATRIX Nine Mile Point Nuclear Station Modes: 1 Power Operation 2

Hot Shutdown 3

Cold Shutdown 4

Refuel D

Defueled Unit 1 Revision 01 NMP Unit 1 EAL Wallboard Page 1 of 2

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