Text

Official Exhibit - ENT000692-00-BD01 - Entergy, 0-CY-2310, Rev. 24, Reactor Coolant System Specification and Frequencies (Jan. 16, 2015)
	ML15334A286
Person / Time
Site:	Indian Point
Issue date:	01/15/2015
From:	; Entergy Nuclear Operations
To:	; Atomic Safety and Licensing Board Panel
	SECY RAS
References
	RAS 28138, ASLBP 07-858-03-LR-BD01, 50-247-LR, 50-286-LR
	Download: ML15334A286 (19)
	v • d • e

United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. ENT000692 (Indian Point Nuclear Generating Units 2 and 3) Submitted: August 10, 2015 ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Exhibit #: ENT000692-00-BD01 Identified: 11/5/2015 Admitted: 11/5/2015 Withdrawn:

Rejected: Stricken:

Other:

Procedure Use Is:

Control Copy:_ __

0 Continuous 0 Reference Effective Date: f-1 "-f~

ltrl nformation Page 1 of 19 1-------- - -NON-QUALITY - -- __.............._ RELATED

_ _ ,_ _ _ ______ _____________ __ _ _ -f 0-CY-2310 Revision -24 REACTO COOLANT SY TEM SPECIFICAT ONS AND FREQUENCIES India" Point APPROVED BY:

~ j0 Jim Peters 7/8/14 L

!1)1 Procedure Writer I Date rk ~ i Chemistry PARTIAL REVISION

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev:24 SPECIFICATIONS AND FREQUENCIES Page 2 of 19 REVISION

SUMMARY

1.0 REASON FOR REVISION 1.1 Revised to meet Rev. 7 of Primary Water Guidelines.

2.0

SUMMARY

OF CHANGES 2.1 Revised RCS at-temperature pH to> 7.0 (2. 1.5 and Attachment 7).

2.2 Updated Commitment Document 5.1 .7 to Rev. 7.

2.3 Revised Attachment 2.

2.4 Attachment 4: Added RCS diagnostic parameters for ammonia and revised zinc parameters.

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 3 of 19 TABLE OF CONTENTS Section 1.0 PURPOSE .......................................................................................................4 2.0 PRECAUTIONS AND LIMITATIONS .............................................................. .4 3.0 PREREQUISITES ............................................................................................ 6 4.0 PROCEDURE ..................................................................................................?

5.0 REFERENCES

................................................................................................ 8 6.0 RECORDS AND DOCUMENTATION .............................................................. 9 Attachments ATTACHMENT 1 - Deleted ATTACHMENT 2 - RCS Control Parameter Specifications ATTACHMENT 3 - RCS Control Parameter Sampling & Analysis Frequency ATTACHMENT 4 - RCS Diagnostic Parameters ATTACHMENT 5 - Primary Plant Action Levels ATTACHMENT 6 - Primary Plant Corrective Actions ATTACHMENT 7 - Reactor Coolant Boron/Lithium Specifications

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 4 of 19 1.0 PURPOSE 1.1 This procedure establishes the requirements for the sampling, analysis and control of the Reactor Coolant System. It implements both the EPRI PWR Primary Water Chemistry Guidelines and the IPEC Primary Strategic Water Chemistry Plan.

1.2 This procedure applies to the Chemistry control of the Reactor Coolant and Residual Heat Removal Systems.

1.3 As part of license renewal, Entergy credited implementation of the EPRI Chemistry Guidelines as a method for mitigating age related degradation mechanisms for some primary system components. {Refs 5.1.5 and 5.1.6}

2.0 PRECAUTIONS AND LIMITATIONS 2.1 Precautions and Limitations 2.1.1 The frequency and specifications for tests other than those required by Technical Specifications or the SPDES permit are recommended by Chemistry Management. The frequency of these tests may be altered at the discretion of Chemistry Management. Analyses with associated NSSS vendor requirements shall be evaluated prior to being altered.

2.1.2 For parameters that do not have a defined frequency or specification Chemistry Management will assign a frequency as dictated by plant conditions or historical trend.

2.1.3 Initially, laboratory analytical results are interpreted by the Watch Chemist or by the Watch Nuclear Plant Operator during their tours.

Abnormal trends in the chemistry data either obtained or observed are evaluated by the Chemistry Technician given the status of that system at that time. Any significant abnormality or trend, as well as, out of specification or out of control band chemistry parameter shall be brought to the attention of the Shift Manager, Control Room Supervisor, and Chemistry Management.

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev:24 SPECIFICATIONS AND FREQUENCIES Page 5 of 19 2.1.4 Refer to Reference 5.3.4 for Dose Equivalent Iodine (DEl) and Dose Equivalent Xenon (DEX) and associated required actions for radiochemical analyses of RCS.

2.1.5 Prior to entering Mode 1, RCS at-temperature pH shall be greater than 7.0.

2.1.6 Deleted.

2.1. 7 Attachment 7, Reactor Coolant Boron/Lithium Specifications, provides the input parameters for calculating the lithium limits based on the boron concentration. These limits are implemented in the chemistry data management system and chemistry technician aids with hardcopy outputs are provided in the event the electronic system is down.

2.1.8 The critical procedures and sample points for monitoring the inhibition of steam generator degradation, as required by Plant Technical Specifications, are located in the Primary Strategic Water Chemistry Plan.

2.1.9 Data consistency checks may be performed using Chemworks Primary pH Calculator OR Smart Chemworks ensuring that the data set has been uploaded at the time of verification.

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev:24 SPECIFICATIONS AND FREQUENCIES Page 6 of 19 2.2 General Information 2.2.1 Plant Modes MODE TITLE REACTIVITY %POWER Tave 1 PowerOps ~0.99 >5 NA 2 Startup ~0.99 :o;5 NA 3 Hot Standby <0.99 NA ~350 4 Hot Shutdown <0.99 NA 350 > Tave >200 5 Cold Shutdown <0.99 NA :o;200 6 Refueling NA NA NA 2.2.2 The Out-Of-Specification Action Guidelines presented in Attachments 5 and 6 are not all-inclusive. Other actions may be appropriate for evaluation in some cases.

2.2.3 Boron/Lithium program is based on a target pH of7.10 calculated at each unit's Tave at 100% power with a minimum pH of 6.9 during plant startups.

2.2.4 Tave at 0 and 100% power are as follows:

Unit 2 0% Power T ave = 545° 100% Power T ave = 565°

Unit 3 0% Power Tave = 550° 100% Power T ave = 570° 3.0 PREREQUISITES NONE

REACTOR COOLANT SYSTEM No: 0-CY-231 0 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 7 of 19 4.0 PROCEDURE {Reference 5.1.5 & 5.1.6}

4.1 Reactor Coolant Chemistry Sampling and Analysis 4.1.1 Reactor Coolant chemistry shall be maintained within specifications in accordance with Attachment 2, RCS Control Parameter Specifications.

4.1.2 Reactor Coolant shall be sampled in accordance with Attachment 3, RCS Control Parameter Sampling & Analysis Frequency, and Attachment 4, RCS Diagnostic Parameter Sampling & Analysis Frequency.

4.2 Chemistry Parameters Out Of Specification 4.2.1 IF a parameter is out of specification, THEN PERFORM the following:

INFORM the Control Room Supervisor (CRS).

REFER TO Attachment 5, Primary Plant Action Levels, for required action.

4.2.2 lE ANY chemistry parameter listed in this procedure can NOT be maintained within chemistry specifications, THEN INITIATE corrective action as soon as possible per Attachment 6, Primary Plant Corrective Actions.

4.2.3 Per reference 5.1.5 & 5.1.6, RCS Chemistry is required to be returned to within specification in the time specified in reference 5.1.7.

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 8 of 19

5.0 REFERENCES

5.1 Commitment Documents 5.1.1 Technical Specifications 5.1.2 Technical Requirements Manual 5.1.3 Westinghouse Primary Chemistry Criteria and Specifications WCAP (5-1) 5.1.4 CR-IP3-2005-05471 concerning Crud-Induced Power Shift (CIPS) 5.1.5 IPEC license renewal implementation document NL-07-039, LRS A-3239 for unit 2. LRA Sections A.2.1.40 and 8.1.41. (LO-LAR-2011-0174, CA 22).

5.1.6 IPEC license renewal implementation document NL-07-039, LRA Section 8.1.31. (LO-LAR-2011-0174, CA40) 5.1.7 Pressurized Water Reactor Primary Water Chemistry Guidelines:

Volume 1 & 2, Revision 7. EPRI, Palo Alto, CA: 2014.

5.1.8 Interim Guidance Regarding PWR Primary Water Chemistry Guidelines

-Volume 1, Revision 7. EPRI, Palo Alto, CA: 20014. 1014986. EPRI SGMP IG-09-01, April 2, 2009 5.2 Development Documents 5.2.1 NEI 97-06, Primary-Side Water Chemistry, December 1997 5.2.2 IPEC Strategic Primary Water Chemistry Plan 5.2.3 EN-NF-102, Corporate Fuel Reliability 5.2.4 EPRI1015448, Fuel Reliability Guidelines: PWR Cladding Corrosion and Crud, March 2008 5.2.5 MTLS-06-131 rev. 4,Westinghouse supplement to the EPRI PWR Primary Water Guidelines Revision 6

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 9 of 19 5.2.6 Westinghouse PWR Zinc Addition Guidelines, PE-07-42, Rev. 12, March April 2012 5.2.7 Pressurized Water Reactor Primary Water Chemistry Guidelines:

Volume 1, Revision 7. EPRI, Palo Alto, CA: 20014.

5.2.8 Westinghouse Letter to Entergy, NF-ECH-12-34 dated May 9, 2012, Entergy AN0-2, Indian Point Unit 2, Indian Point Unit 3 and WESE-3 Westinghouse Position on EPRI PWR Primary Water Chemistry Guidelines Revised Guidance with Regard to Dissolved Hydrogen Concentration.

5.2.9 EC 44828, "Option to Remove Secondary Sources from Core Design".

5.3 Interface Documents 5.3.1 Technical Specifications 5.3.2 Technical Requirements Manual 5.3.3 Pressurized Water Reactor Primary Water Chemistry Guidelines:

Volume 1, Revision 7. EPRI, Palo Alto, CA: 2014.

5.3.4 0-CY-2765, Coolant Activity Limits- Dose Equivalent Iodine/Xenon 6.0 RECORDS AND DOCUMENTATION NONE

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 10 of 19 ATTACHMENT 1 Page 1 of 1 Attachment deleted

REACTOR COOLANT SYSTEM SPECIFICATIONS AND No: 0-CY-2310 Rev: 24 FREQUENCIES Page 11 of 19 ATTACHMENT 2 Page 1 of 1 RCS CONTROL PARAMETER SPECIFICATIONS Refer to Attachment 6 for guidance while trying to maintain in specification RCS HOLD POINT REACTOR HOLD POINT POWER TEMPERATURE PRIOR TO SUBCRITICAL & PRIOR TO OPERATION PARAMETER AL1 AL2 AL3

~ 250°F EXCEEDING RCS > 250°F CRITICALITY or STARTUP (MODES 4, 5 & 6) 250°F (MODE 4) (MODES 3 and 4) (MODE 3) (MODES 1 and 2)

As required for As required for As required for As required for As required for None Boron, ppm None None reactivity control reactivity control reactivity control reactivity control reactivity control .

<150 111 5

Chloride, ppb " 150 <150 <150 S15 >15 >150 >1500

Fluoride, ppb "150 <150 111 <150 <150 S15 >15 >150 >15005

<150 111 5

Sulfate, ppb None <150 <150 S15 >15 >150 >1500 Dissolved Oxygen 5 (DO), ppb None <100 <100 <100 S5 >5 >100 >1000 Pressurizer DO, None <100 None None None None None None ppb Hydrogen, cc 141 <300R (STP)/kg H2 0 None None None >15 " 30 AND s 50 >50

<15 <5 Variable - Based on Boron Puts ide Lithium, ppm None None None None Concentration (Refer to rontrol None rand None Attachments 7)

Silica ppm 121 None None None None <3 None None None 131 < 7.0 None None

@Temp pH None None None None ?_ 7.0 (1) Pressurizer liquid sample must also meet these values prior to exceeding 250".

(2) Westinghouse guideline specification, !E specification is not met THEN a fuels examination may be required.

(3) Calculated from RCS Boron, Lithium, Ammonia and RCS Tave at the time of sample.

(4) RCS dissolved hydrogen should be maintained 540 cc/kg on a cycle average basis as recommended by Westinghouse fuels. [Ref 5.2.8]

(5) If during startup AL3 levels exceeded immediately reduce temperature to <250°F

REACTOR COOLANT SYSTEM SPECIFICATIONS AND No: 0-CY-2310 Rev:24 FREQUENCIES Page 12 of 19 ATTACHMENT 3 Page 1 of 1 RCS CONTROL PARAMETER SAMPLING & ANALYSIS FREQUENCY REACTOR SUBCRITICAL &

RCS TEMPERATURE ~ 250°F RCS>250°F POWER OPERATION/STARTUP PARAMETER (MODES 4 and S, 6) (MODES 1 and 2)

(MODES 3 and 4)

Boron, ppm 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s\'! Daily Daily Chloride, ppb 3/7 days \ZI AND 3 days max Three /Week Three/Week Fluoride, ppb 1/7 days 1"1 AND 10 days max Three I Week Three /Week Sulfate, ppb 1/7 days 1" 1 Three/Week Three I Week ,.,

Dissolved Oxygen (DO), ppb 317 days AND 3 days max Daily Three I Week Pressurizer DO, ppb Daily"' Not Required Not Required 1

Hydrogen, cc (STP)Ikg H20 Not Required Three I Week Three I Week "'

1 Lithium, ppm Not Required Not Required Daily "'

Silica, ppm 1/7 days"' 1/7 days 117 days171 (1) Boron frequency is based on the following critena:

a_ Every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when in Mode 5 or 6 at Unit 2 based on EC44828, "Option to remove Secondary Source from Core Design"_

b. Daily at Unit 3

c. WHEN the RCSIRHR, the Reactor Cavity, AND Refueling Canal are connected, THEN:

AT UNIT 2, sample the Reactor Cavity AND the Refueling Canal once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

AT UNIT 3, sample the Reactor Cavity once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (2) Frequency should be increased during activities, such as refueling, when the likelihood of contamination is increased_

(3) Initiated during heatup. Pressurizer sampling is terminated when DO < 100 ppb.

(4) Frequency should be increased if evidence of resin ingress is noted (e.g., increasing sulfate concentrations).

(5) Frequency of sampling should be increased during operations that may significantly impact hydrogen concentration (e.g., feed and bleed, purging of pressurizer vapor space) or known periods of hydrogen instability.

(6) Frequency should be increased during operations that may significantly impact lithium concentration (e.g., feed and bleed).

(7) Initiated during heatup_ At Unit 2 ONLY, sample daily from RCS >200°F until limit is achieved

REACTOR COOLANT SYSTEM No: 0-CY-231 0 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 13 of 19 ATTACHMENT 4 Page 1 of 3 RCS DIAGNOSTIC PARAMETERS RCS DIAGNOSTIC PARAMETERS DURING STARTUP REACTOR SUBCRmCAL &

PARAMETER Frequency RCS > 25011F c ODES 3 lnd4)

(a) l1th um. ppm as li 1/8 HouFS Am mom a Daly Vanable smca OaJiy V riable I

I Aluminum, ppb Once pnor to secunng, RHR (<2S<ff) s BO ad Calcium+ Magnes*um. ppb 580

- once pnor to crtttcabty.

Magnes1um. ppb -300..F fDIIawtng RFOs S40 NOTE (a): <1 ppm while on RHR and 2: 2 ppm when >350°F.

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 14 of 19 ATIACHMENT4 Page 2 of3 RCS DIAGNOSTIC PARAMETERS Power Operation RADIOCHEMICAL DIAGNOSTIC PARAMETERS PARAMETER REQUI~ED ! NORMAL FREQUENCY FREQUENCY Gamma Isotopic with Simplified N/A 41 Week Dose Equivalent Iodine Dose Equivalent Iodine (DEl) 1 /14 Days <1> 1!7 Days 1

Dose Equivalent Xenon (DEX) 1n days < > 1!7 Days 24 hr decay (1-131)

Decayed Isotopic N/A 2 Others 1f7 Days <>

Dissolved Radiogas N/A 1!7 Days Decayed Suspended Solids N/A 1!7 Days 3

Tritium 1n days < > 1!7 Days Total RCS Activity Summary N/A 1f7 Days (NucleariQ)

(1) Tech Spec 3.4.16 and Reference 5.3.4 (2) Various RCS decay counts may be prescribed by Chemistry Management (3) Required by UFSAR CHEMICAL DIAGNOSTIC PARAMETERS PARAMETER FREQUENCY Conductivity Daily <4>

4 Total Suspended Solids 1!7 Days < >

4 5 Silica 1f7 Days < >< >

Every 60 Days, Following Trips, Boron-10 and Prior to Startup from Refueling Iron 1/31 Days <6 ><7>

Nickel 1/31 Days <6 ><7>

Ammonia 1/31 Days (4) EPRI Guidelines (5) Weekly until < 1ppm, then monthly.

(6) Frequency increases to weekly 3 months prior to start of refueling outage.

(7) Required per Reference 5.1.4.

REACTOR COOLANT SYSTEM No: 0-CY-231 0 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 15 of 19 ATTACHMENT 4 Page 3 of3 RCS DIAGNOSTIC PARAMETERS RCS Sampling Prior To Initiating Zinc Addition Parameter Frequency Ex -..o. -.... Value 'lJ

< 2' ppb. first zinc cycle Total Nickel 1n Days s 6 ~Rb . subsequent: .zinc cycles _

1n- Days f-o-Silica S2JJR_m RCS Sampling During Zinc Addition Ta et Control Rlln

Action Level 1fday until target reached and < 10 ppb Zinc 10 to 20 ppb or stable then weekly >20 b ll J Total

-----~------------------~---~~~----~

Nickel -;._____,_n Days -----:------ - s 6 ppb_ l =- e ppb _*,...--

Sllica 1f7Da .s2 . m - f - >2 m (1) Average of 2 consecutive samples, taken at least two days apart.

(2) Increased sample frequency to daily during at-power plant or zinc transients. Westinghouse should be notified if zinc samples averaged over 2 days exceed 80 ppb.

(3) The zinc injection rate (grams/hr) should be adjusted to restore zinc within target control range. If zinc samples averaged over 2 days exceed 80 ppb, contact Westinghouse for re-evaluation and to define any additional actions.

(4) If average of 2 successive samples results in >6 ppb nickel, evaluate for possible CIPS by evaluating flux map. Contact the fuel vendor to determine if additional actions are required.

(5) If average of monthly samples results in >2 ppm silica, suspend zinc addition and contact the fuel vendor to determine if additional actions are required.

RCS I RHR Following Fill & Vent to Reactor Critical Parametar Frequency

=-_j 161 1-Corros1on Products } Da*ty Mixed Bed OF en ~-- Daity Hydrazine. ppb As required

Ammonia. ppb 1 per 3 days (6) Analyze for elemental Fe and Ni from ~150°F until 500°F. Sample may be drawn on a predetermined schedule and preserved for analysis at a later time. Analyze for isotopic Co-58, Co-60, Mn-54 and Cr-51.

(7) Sample mixed bed effluent chloride and sulfate Calculate DF from daily RCS/RHR sample.

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 16 of 19 ATTACHMENT 5 Page 1 of 1 PRIMARY PLANT ACTION LEVELS Action Level 1 a) Efforts should be made to bring the parameter within the appropriate limit within seven days.

b) If the parameter has not been restored to below the Action Level 1 value within seven days, a technical review shall be performed and a program for implementing corrective measures instituted. Such a program may require equipment additions or modifications over the long term.

Action Level 2 a) Efforts should be made to bring the parameter within the appropriate Action Level 2 value within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

NOTE IF the chemistry is improved to within the requirements of Action Level 2 prior to plant shutdown, THEN full power operation may be resumed.

b) If the parameter has not been restored to below the Action Level 2 value within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , an orderly shutdown shall be initiated and the plant shall be brought to a coolant temperature

< 250°F (121oC) as quickly as permitted by other plant constraints.

c) Following a unit shutdown caused by exceeding the time limit on an Action Level 2 value, a technical review of the incident should be performed and appropriate corrective measures taken before the unit is restarted.

Action Level 3 a) Rapid shutdown shall be initiated with the unit in Mode 3 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , then cool RCS to less than 250°F as rapidly as plant conditions permit.

b) Following a unit shutdown caused by entering an Action Level 3 condition, a formal technical review of the incident shall be performed and appropriate corrective measures taken before the unit is restarted.

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 17 of 19 ATTACHMENT 6 Page 1 of2 PRIMARY PLANT CORRECTIVE ACTIONS REACTOR COOLANT SYSTEM Parameter Out of Ranqe Corrective Actions Chloride/Fluoride 1. CHECK ion exchange beds in purification system for flow and removal efficiencies.

2. IF indicated, THEN request Operations place the standby mixed bed Demineralizer in service.

3. Request Operations to INCREASE letdown and charging flow.

4. CHECK for high RCS ammonia or conductivity that may cause chloride or fluoride release from resin.

5. CHECK makeup water purity.

6. ISOLATE makeup water source or change to alternate source if required.

7. SEEK other potential sources of fluoride.

Sulfate 1. CHECK for indications of resin released from the purification system.

2. CHECK ion exchanger removal efficiency and isolate if necessary.

3. CHECK makeup water purity.

Lithium 1. CHECK to ensure reactor coolant dilution OR boration is NOT in progress.

2. ENSURE that a lithiated mixed bed is in service.

3. VERIFY flow through cation OR other purification ion exchangers.

4. ADJUST lithium as required to bring within station control program.

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 18 of 19 ATIACHMENT6 Page 2 of2 PRIMARY PLANT CORRECTIVE ACTIONS REACTOR COOLANT SYSTEM -"~

Parameter Out of Ranqe Corrective Actions Hydrogen 1. !E RCS hydrogen is low THEN INCREASE hydrogen pressure in the VCT AND/OR INCREASE hydrogen purity in the VCT INCREASE sample frequency to assess adequacy of actions.

2. Ensure letdown flow rate is sufficient to increase hydrogen concentration in the RCS. 120 gpm is recommended especially during large manual dilutions.

3. CHECK for indications of leaking valves or check for air ingress to the charging system.

4. !E RCS hydrogen is high, THEN DECREASE hydrogen pressure in the VCT. CONSIDER venting pressurizer gas space via sample line.

INCREASE sample frequency to assess adequacy of actions.

Dissolved Oxygen 1. VERIFY hydrogen concentration.

2. CHECK for air leaks into CVCS.

3. IF hydrogen regulator to VCT is in service, THEN request Operations to INCREASE VCT hydrogen pressure.

4. IF nitrogen regulator to the VCT is in service, AND RCS temperature is less than 180°F, THEN consider hydrazine addition to reduce oxygen concentration.

(1) Following startup or power changes restore lithium to specifications by xenon equilibration.

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev:24 SPECIFICATIONS AND FREQUENCIES Page 19 of 19 ATIACHMENT 7 Page 1 of 1 REACTOR COOLANT BORON I LITHIUM SPECIFICATIONS NOTE Prior to 100% power and xenon equalization, Chemistry Management will calculate the lithium necessary to maintain at least a 7.0 at-temperature pH.

During full power operations the reactor coolant system (RCS) pH(t) will be coordinated at a target value of 7.10 pH units with a maximum target lithium value of 3.5 ppm. The RCS pH(t) will be calculated using the RCS average temperature for each unit and the methodology specified by EPRI SGMP interim guidance [Ref 5.1.8]. This can be satisfied using the pH calculator in EPRI's Chemworks Tools version 3.3 or later. Chemistry Technician Aids for each unit are available in the event that computerized limits are not available. During plant startups, the RCS pH(t) will be maintained greater than 6.9 units and lithium will not exceed 5 ppm.

The lithium limits will be established consistent with the EPRI guidelines as follows: For [Li] >

3.0 ppm, maintain lithium at the target value within+/- 5% of lithium concentration until lithium reaches 3.0 ppm, and then at+/- 0.15 ppm until [Li] decreases to 1.25 ppm. For [Li] < 1.25 ppm until the end of the operating cycle, maintain lithium at the target value within +/- 12% of lithium concentration.

The lithium administrative control band will be established as follows: For [Li] > 3.0 ppm, maintain lithium at the target value within +/- 3.33% of lithium concentration until lithium reaches 3.0 ppm, and then at +/- 0.10 ppm until [Li] decreases to 1.25 ppm. For [Li] < 1.25 ppm until the end of the operating cycle, maintain lithium at the target value within +/- 8% of lithium concentration.

United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. ENT000692 (Indian Point Nuclear Generating Units 2 and 3) Submitted: August 10, 2015 ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Exhibit #: ENT000692-00-BD01 Identified: 11/5/2015 Admitted: 11/5/2015 Withdrawn:

Rejected: Stricken:

Other:

Procedure Use Is:

Control Copy:_ __

0 Continuous 0 Reference Effective Date: f-1 "-f~

ltrl nformation Page 1 of 19 1-------- - -NON-QUALITY - -- __.............._ RELATED

_ _ ,_ _ _ ______ _____________ __ _ _ -f 0-CY-2310 Revision -24 REACTO COOLANT SY TEM SPECIFICAT ONS AND FREQUENCIES India" Point APPROVED BY:

~ j0 Jim Peters 7/8/14 L

!1)1 Procedure Writer I Date rk ~ i Chemistry PARTIAL REVISION

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev:24 SPECIFICATIONS AND FREQUENCIES Page 2 of 19 REVISION

SUMMARY

1.0 REASON FOR REVISION 1.1 Revised to meet Rev. 7 of Primary Water Guidelines.

2.0

SUMMARY

OF CHANGES 2.1 Revised RCS at-temperature pH to> 7.0 (2. 1.5 and Attachment 7).

2.2 Updated Commitment Document 5.1 .7 to Rev. 7.

2.3 Revised Attachment 2.

2.4 Attachment 4: Added RCS diagnostic parameters for ammonia and revised zinc parameters.

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 3 of 19 TABLE OF CONTENTS Section 1.0 PURPOSE .......................................................................................................4 2.0 PRECAUTIONS AND LIMITATIONS .............................................................. .4 3.0 PREREQUISITES ............................................................................................ 6 4.0 PROCEDURE ..................................................................................................?

5.0 REFERENCES

................................................................................................ 8 6.0 RECORDS AND DOCUMENTATION .............................................................. 9 Attachments ATTACHMENT 1 - Deleted ATTACHMENT 2 - RCS Control Parameter Specifications ATTACHMENT 3 - RCS Control Parameter Sampling & Analysis Frequency ATTACHMENT 4 - RCS Diagnostic Parameters ATTACHMENT 5 - Primary Plant Action Levels ATTACHMENT 6 - Primary Plant Corrective Actions ATTACHMENT 7 - Reactor Coolant Boron/Lithium Specifications

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 4 of 19 1.0 PURPOSE 1.1 This procedure establishes the requirements for the sampling, analysis and control of the Reactor Coolant System. It implements both the EPRI PWR Primary Water Chemistry Guidelines and the IPEC Primary Strategic Water Chemistry Plan.

1.2 This procedure applies to the Chemistry control of the Reactor Coolant and Residual Heat Removal Systems.

1.3 As part of license renewal, Entergy credited implementation of the EPRI Chemistry Guidelines as a method for mitigating age related degradation mechanisms for some primary system components. {Refs 5.1.5 and 5.1.6}

2.0 PRECAUTIONS AND LIMITATIONS 2.1 Precautions and Limitations 2.1.1 The frequency and specifications for tests other than those required by Technical Specifications or the SPDES permit are recommended by Chemistry Management. The frequency of these tests may be altered at the discretion of Chemistry Management. Analyses with associated NSSS vendor requirements shall be evaluated prior to being altered.

2.1.2 For parameters that do not have a defined frequency or specification Chemistry Management will assign a frequency as dictated by plant conditions or historical trend.

2.1.3 Initially, laboratory analytical results are interpreted by the Watch Chemist or by the Watch Nuclear Plant Operator during their tours.

Abnormal trends in the chemistry data either obtained or observed are evaluated by the Chemistry Technician given the status of that system at that time. Any significant abnormality or trend, as well as, out of specification or out of control band chemistry parameter shall be brought to the attention of the Shift Manager, Control Room Supervisor, and Chemistry Management.

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev:24 SPECIFICATIONS AND FREQUENCIES Page 5 of 19 2.1.4 Refer to Reference 5.3.4 for Dose Equivalent Iodine (DEl) and Dose Equivalent Xenon (DEX) and associated required actions for radiochemical analyses of RCS.

2.1.5 Prior to entering Mode 1, RCS at-temperature pH shall be greater than 7.0.

2.1.6 Deleted.

2.1. 7 Attachment 7, Reactor Coolant Boron/Lithium Specifications, provides the input parameters for calculating the lithium limits based on the boron concentration. These limits are implemented in the chemistry data management system and chemistry technician aids with hardcopy outputs are provided in the event the electronic system is down.

2.1.8 The critical procedures and sample points for monitoring the inhibition of steam generator degradation, as required by Plant Technical Specifications, are located in the Primary Strategic Water Chemistry Plan.

2.1.9 Data consistency checks may be performed using Chemworks Primary pH Calculator OR Smart Chemworks ensuring that the data set has been uploaded at the time of verification.

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev:24 SPECIFICATIONS AND FREQUENCIES Page 6 of 19 2.2 General Information 2.2.1 Plant Modes MODE TITLE REACTIVITY %POWER Tave 1 PowerOps ~0.99 >5 NA 2 Startup ~0.99 :o;5 NA 3 Hot Standby <0.99 NA ~350 4 Hot Shutdown <0.99 NA 350 > Tave >200 5 Cold Shutdown <0.99 NA :o;200 6 Refueling NA NA NA 2.2.2 The Out-Of-Specification Action Guidelines presented in Attachments 5 and 6 are not all-inclusive. Other actions may be appropriate for evaluation in some cases.

2.2.3 Boron/Lithium program is based on a target pH of7.10 calculated at each unit's Tave at 100% power with a minimum pH of 6.9 during plant startups.

2.2.4 Tave at 0 and 100% power are as follows:

Unit 2 0% Power T ave = 545° 100% Power T ave = 565°

Unit 3 0% Power Tave = 550° 100% Power T ave = 570° 3.0 PREREQUISITES NONE

REACTOR COOLANT SYSTEM No: 0-CY-231 0 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 7 of 19 4.0 PROCEDURE {Reference 5.1.5 & 5.1.6}

4.1 Reactor Coolant Chemistry Sampling and Analysis 4.1.1 Reactor Coolant chemistry shall be maintained within specifications in accordance with Attachment 2, RCS Control Parameter Specifications.

4.1.2 Reactor Coolant shall be sampled in accordance with Attachment 3, RCS Control Parameter Sampling & Analysis Frequency, and Attachment 4, RCS Diagnostic Parameter Sampling & Analysis Frequency.

4.2 Chemistry Parameters Out Of Specification 4.2.1 IF a parameter is out of specification, THEN PERFORM the following:

INFORM the Control Room Supervisor (CRS).

REFER TO Attachment 5, Primary Plant Action Levels, for required action.

4.2.2 lE ANY chemistry parameter listed in this procedure can NOT be maintained within chemistry specifications, THEN INITIATE corrective action as soon as possible per Attachment 6, Primary Plant Corrective Actions.

4.2.3 Per reference 5.1.5 & 5.1.6, RCS Chemistry is required to be returned to within specification in the time specified in reference 5.1.7.

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 8 of 19

5.0 REFERENCES

5.1 Commitment Documents 5.1.1 Technical Specifications 5.1.2 Technical Requirements Manual 5.1.3 Westinghouse Primary Chemistry Criteria and Specifications WCAP (5-1) 5.1.4 CR-IP3-2005-05471 concerning Crud-Induced Power Shift (CIPS) 5.1.5 IPEC license renewal implementation document NL-07-039, LRS A-3239 for unit 2. LRA Sections A.2.1.40 and 8.1.41. (LO-LAR-2011-0174, CA 22).

5.1.6 IPEC license renewal implementation document NL-07-039, LRA Section 8.1.31. (LO-LAR-2011-0174, CA40) 5.1.7 Pressurized Water Reactor Primary Water Chemistry Guidelines:

Volume 1 & 2, Revision 7. EPRI, Palo Alto, CA: 2014.

5.1.8 Interim Guidance Regarding PWR Primary Water Chemistry Guidelines

-Volume 1, Revision 7. EPRI, Palo Alto, CA: 20014. 1014986. EPRI SGMP IG-09-01, April 2, 2009 5.2 Development Documents 5.2.1 NEI 97-06, Primary-Side Water Chemistry, December 1997 5.2.2 IPEC Strategic Primary Water Chemistry Plan 5.2.3 EN-NF-102, Corporate Fuel Reliability 5.2.4 EPRI1015448, Fuel Reliability Guidelines: PWR Cladding Corrosion and Crud, March 2008 5.2.5 MTLS-06-131 rev. 4,Westinghouse supplement to the EPRI PWR Primary Water Guidelines Revision 6

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 9 of 19 5.2.6 Westinghouse PWR Zinc Addition Guidelines, PE-07-42, Rev. 12, March April 2012 5.2.7 Pressurized Water Reactor Primary Water Chemistry Guidelines:

Volume 1, Revision 7. EPRI, Palo Alto, CA: 20014.

5.2.8 Westinghouse Letter to Entergy, NF-ECH-12-34 dated May 9, 2012, Entergy AN0-2, Indian Point Unit 2, Indian Point Unit 3 and WESE-3 Westinghouse Position on EPRI PWR Primary Water Chemistry Guidelines Revised Guidance with Regard to Dissolved Hydrogen Concentration.

5.2.9 EC 44828, "Option to Remove Secondary Sources from Core Design".

5.3 Interface Documents 5.3.1 Technical Specifications 5.3.2 Technical Requirements Manual 5.3.3 Pressurized Water Reactor Primary Water Chemistry Guidelines:

Volume 1, Revision 7. EPRI, Palo Alto, CA: 2014.

5.3.4 0-CY-2765, Coolant Activity Limits- Dose Equivalent Iodine/Xenon 6.0 RECORDS AND DOCUMENTATION NONE

REACTOR COOLANT SYSTEM No: 0-CY-2310 Rev: 24 SPECIFICATIONS AND FREQUENCIES Page 10 of 19 ATTACHMENT 1 Page 1 of 1 Attachment deleted

REACTOR COOLANT SYSTEM SPECIFICATIONS AND No: 0-CY-2310 Rev: 24 FREQUENCIES Page 11 of 19 ATTACHMENT 2 Page 1 of 1 RCS CONTROL PARAMETER SPECIFICATIONS Refer to Attachment 6 for guidance while trying to maintain in specification RCS HOLD POINT REACTOR HOLD POINT POWER TEMPERATURE PRIOR TO SUBCRITICAL & PRIOR TO OPERATION PARAMETER AL1 AL2 AL3

~ 250°F EXCEEDING RCS > 250°F CRITICALITY or STARTUP (MODES 4, 5 & 6) 250°F (MODE 4) (MODES 3 and 4) (MODE 3) (MODES 1 and 2)

As required for As required for As required for As required for As required for None Boron, ppm None None reactivity control reactivity control reactivity control reactivity control reactivity control .

<150 111 5

Chloride, ppb " 150 <150 <150 S15 >15 >150 >1500

Fluoride, ppb "150 <150 111 <150 <150 S15 >15 >150 >15005