Text

Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process; License Amendment Request No. 2015-03
	ML17095A530
Person / Time
Site:	Oconee
Issue date:	03/30/2017
From:	Teresa Ray; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	ON-2017-028
	Download: ML17095A530 (49)
	v • d • e

.,.

~~'------

~~DUKE

~ ENERGY ON-2017-028 March 30, 2017 Attn: Document Control Desk U. S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20582-27 46 Duke Energy Carolinas, LLC Oconee Nuclear Station, Units 1, 2, and 3 Docket Numbers 50-269, 50-270, and 50-287, 10 CFR 50.90 Renewed Operating Licenses DPR-38, DPR-47, and DPR-55 Thomas D. Ray Vice President Oconee Nuclear Station Duke Energy ON01 VP I 7800 Rochester Hwy Seneca, SC 29672

o. 864.873.5016

f. 864.873. 4208 Tom.Ray@duke-energy.com

Subject:

Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, using the Consolidated Line Item Improvement Process; License Amendment Request No. 2015-03 In accordance with 1 O CFR 50.90, Duke Energy Carolinas, LLC (Duke Energy), is submitting a request for an amendment to the Technical Specifications (TS) related to Control Room Envelope Habitability for the Oconee Nuclear Station (ONS). The proposed amendment would modify the TS in accordance with Technical Specification Task Force (TSTF)-448, "Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, using the Consolidated Line Item Improvement Process." The availability of this TS improvement was published in the Federal Register (72 FR 2022) on January 17, 2007 as part of the consolidated line item improvement process (CLllP).

The Enclosure provides a description of the proposed changes, the requested confirmation of applicability, and plant-specific variations. Attachment 1 provides the existing TS and TS Bases pages marked up to show the proposed changes and Attachment 2 provides the revised TS and TS Bases pages. There are no regulatory commitments made in this submittal.

Duke Energy requests NRC approval of this CLllP item by March 30, 2018, with a 180-day implementation period.

In accordance with Duke Energy administrative procedures and the Quality Assurance Program Topical Report, these proposed changes have been reviewed and approved by the Plant Operations Review Committee. Additionally, a copy of this LAR was transmitted to the State of South Carolina in accordance with 10 CFR 50.91 requirements.

Nuclear Regulatory Commission License Amendment Request No. 2015-03 March 30, 2017 Page 2 If you should have any questions regarding this submittal, please contact Stephen C. Newman, Lead Nuclear Engineer, Regulatory Affairs, at (864) 873-4388.

I declare under penalty of perjury that the foregoing is true and correct. Executed on March 30, 2017.

Since~>1 0~>>*u~

Thomas D. Ray Vice President Oconee Nuclear Sta 1

Enclosure:

Description and Assessment Attachments:

1. Proposed Technical Specification and Bases Changes (Mark-Ups).

2. Technical Specification and Bases Pages (Reprinted).

Nuclear Regulatory Commission License Amendment Request No. 2015-03 March 30, 2017 xc w/enclosure/attachments:

Catherine Haney, Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. Stephen Koenick, Project Manager (ONS)

(by electronic mail only)

U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop OWFN/8F14 Rockville, MD 20852-2738 Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station Susan E. Jenkins, Manager (by electronic mail only: jenkinse@dhec.sc.gov)

Radioactive & Infectious Waste Management SC Dept. of Health and Environmental Control 2600 Bull St.

Columbia, SC 29201 Page 3

ENCLOSURE DESCRIPTION AND ASSESSMENT

Subject:

Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance With TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process

1.0 DESCRIPTION

2.0 ASSESSMENT

2.1 Applicability of Published Safety Evaluation 2.2 Changes and Variations 2.3 License Condition Regarding Initial Performance of New Surveillance and Assessment Requirements

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Determination Environmental Evaluation 3.2 Commitments 4.0 ENVIRONMENTAL EVALUATION

Enclosure - Description and Assessment License Amendment Request No. 2015-03 March 30, 2017

1.0 DESCRIPTION

Page 2 This License Amendment Request (LAR) will modify Technical Specification (TS}

requirements related to Control Room Envelope (CRE) habitability in TS 3.7.9, "Control Room Ventilation System Booster Fans," and TS Section 5.5, "Programs and Manuals."

The changes are consistent with Nuclear Regulatory Commission (NRC) approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change, TSTF-448, Revision 3. The availability of this TS improvement was published in the Federal Register (72 FR 2022) on January 17, 2007, as part of the consolidated line item improvement process (CLllP).

2.0 ASSESSMENT

2.1 Applicability of Published Safety Evaluation Duke Energy Carolinas, LLC (Duke Energy) has reviewed the NRC Safety Evaluation (SE) dated January 9, 2007, as part of the CLllP. This review included a review of the NRC's evaluation, as well as the supporting information provided to support TSTF-448. Duke Energy has concluded that the justifications presented in the TSTF proposal and NRC SER (substituting the applicable Principle Design Criteria for the described General Design Criteria), are applicable to ONS Units 1, 2, and 3, and justify this amendment for incorporation of the changes to the ONS TSs.

2.2 Changes and Variations Duke Energy is proposing the following variances to the changes described in TSTF-448, Revision 3, to reflect ONS current configuration differences associated with the approved NRC model:

Variation

1. The TS and TSB number will be 3.7.9 rather than 3.7.10 as given in the model.

Control Room Ventilation System (CRVS) will be used rather than Control Room Emergency Ventilation System (CREVS) as given in the TSTF model.

2. Reworded "Applicability" description as follows: "... During movement of recently irradiated fuel assemblies for any unit."

Also, revised the TSB applicability section description accordingly.

To match ONS TS numbering and system nomenclature.

Based on ONS's three (3) unit and two (2) control room configuration, the proposed wording ensures the safety of control room personnel from the effects of a fuel handling accident occurring at any unit.

Enclosure - Description and Assessment License Amendment Request No. 2015-03 March 30, 2017 v.ariation

3. TS 3.7.9 Condition B, Required Action B.2 wording was revised to:

"Verify mitigating actions ensure CRE occupant radiological exposures will not exceed limits, and CRE occupants are protected from chemical and smoke hazards. "

4. TS Bases reference date for NEI 99-03, "Control Room Habitability Assessment," was changed from March 2001, as given in the NRC model, to June 2001. This error was identified in TSTF-448, R3 after issuance.

5. The NRC model wording given in TS 5.5.18, "Control Room Envelope Habitability Program,"

item (d) was changed [in part] to read:

"... The results shall be trended and used as part of the periodic assessment of the CRE boundary."

6. Relocated the non-conditional SR frequencies (3.7.9.1, 3.7.9.3, and 3.7.9.5) to a licensee controlled program.

7. The wording for Required Action D.1, "Place OPERABLE CRVS Booster Fan train in emergency mode," was changed to "Start the OPERABLE CRVS Booster Fan train." Additionally, the associated TSB was clarified accordingly.

8. TSTF Model Technical Specification Condition "F" Required Action I Completion Time was changed from "Enter LCO 3.0.3 / Immediately" to "Restore one CRVS Booster Fan train to OPERABLE status I 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ."

~ustifi.cation.

There are no chemical and smoke limit requirements for the ONS control rooms; Consequently, the original TSTF-448 R3 model verbiage is not applicable.

Page 3 Correction is documented in TSTF-06-37 letter, "Corrected Pages for TSTF-448, Revision 3, Control Room Habitability," dated December 29, 2006.

The original statement given in the NRC model was incorrect as the assessment being referenced is required (by Regulatory Guide 1.197) to be performed every 36 months, not every 18 months. This error was identified shortly before the final approval of TSTF-448 and acknowledged by the NRC and the industry.

ONS implementation of approved TSTF-425 amendment request (NRC Safety Evaluation dated March 21, 2011 ).

The ONS CRVS Booster Fan system does not have an emergency mode selection.

The ONS current licensing basis (CLB) action for both trains inoperable in MODE 1, 2, 3, or 4 (for reasons other than a loss of pressure boundary) is to restore one ( 1) CRVS Booster Fan train within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Enclosure - Description and Assessment License Amendment Request No. 2015-03 March 30, 2017

9. A new Condition "G" LCO 3.0.3 was added that requires a unit shutdown if the Required Action and Completion Time for Condition F (see #8 above) is not met.

10. TSTF 448 Model SR 3.7.10-3 wording was revised from "... on an actual or simulated actuation signal," to "... on a manual actuation signal."

)1.,1.stification;~ *

Maintains ONS CLB for not being able to restore an inoperable train (when both trains are inoperable),

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Page 4 Maintains ONS CLB. Upon receipt of a radiation alarm from the Control Room air radiation monitor, the CRVS Booster Fan trains are started manually to minimize unfiltered air from entering the control room. Upon starting the fans, dampers are automatically positioned to isolate the control room.

2.3 License Condition Regarding Initial Performance of New Surveillance and Assessment Requirements Duke Energy proposes the following as a license condition to support implementation of the proposed TS changes:

Upon implementation of the Amendment adopting TSTF-448, Revision 3, the determination of CRE unfiltered air in-leakage as required by TS SR 3.7.9.4, in accordance with TS 5.5.23.c.(i); the assessment of CRE habitability as required by TS 5.5.23.c.(ii); and the measurement of pressure as required by TS 5.5.23.d, shall be considered met. Following implementation:

(a) The first performance of SR 3.7.9.4 in accordance with Specification 5.5.23.c.(i), shall be within the specified Frequency of 6 years, plus the 18 month (25%) allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years. The most recent successful test as of the date of this submittal is June, 2007.

(b) The first performance of the periodic assessment of CRE habitability, TS 5.5.23.c.(ii), shall be within 3 years, plus the 9 month (25%) allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years. The most recent successful test as of the date of this submittal is June, 2007.

(c) The first performance of the periodic measurement of CRE pressure, TS 5.5.23.d shall be within 24 months plus the 6 months allowed by SR 3.0.2, as measured from the most recent successful pressure measurement test, or within 6 months if not performed previously.

Enclosure - Description and Assessment License Amendment Request No. 2015-03 March 30, 2017

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Determination Page 5 Duke Energy has reviewed the proposed no significant hazards consideration determination (NSHCD) published in the Federal Register as part of the CLllP.

Duke Energy has concluded that the proposed NSHCD presented in the Federal Register notice is applicable to ONS and is hereby incorporated by reference.

3.2 Commitments There are no new regulatory commitments contained in this LAR. This LAR satisfies the planned commitment made in Oconee's response to NRC GL 2003-01, dated December 9, 2003, to review and implement TSTF-448 once approved.

4.0 ENVIRONMENTAL EVALUATION Duke Energy has reviewed the environmental evaluation included in the model safety evaluation dated January 9, 2007, as part of the CLllP. Duke Energy has concluded that the staff's findings presented in that evaluation are applicable to ONS and the evaluation is incorporated by reference for this application.

ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION AND BASES PAGES (MARK-UP)

CRVS Booster Fans 3.7.9

3. 7 PLANT SYSTEMS 3.7.9 Control Room Ventilation System (CRVS) Booster Fans LCO 3.7.9 Two CRVS Booster Fan trains shall be OPERABLE.

NOTE----------------------------------------------

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

~--

APPLICABILITY:

MODES 1, 2, 3, aRG-4, 5, and 6, During movement of recently irradiated fuel assemblies for any unit.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Control Room pressure A.1 Restore Control Room 30 days? days

.:::: 0.0 psi§ durin§ pressure to ::::. 0.0 psi§ operation of two One durin§ operation of t\\vo CRVS Booster Fan train CRVS Booster Fan train inoperable for reasons to OPERABLE other than Condition Bs.

statustraifls.

B.

One or more CRVS B.1 Restore CRVS Booster Immediately Booster Fan train§.

i;:an train to QP~RABb~

inoperable due to staWslnitiate action to inoperable CRE implement mitigating boundary in MODE 1, 2, actions 3, or 4for reasons other than Condition A.

AND 2472 hours0.0286 days 0.687 hours 0.00409 weeks 9.40596e-4 months B.2 Verify mitigating actions ensure CRE occupant radiological exposures will not exceed limits and CRE occupants are protected from chemical and smoke hazards.

90 days OCONEE UNITS 1, 2, & 3 3.7.9-1 Amendment Nos. xxx~, xxx~, ~ xxx3-W

CONDITION ACTIONS (continued)

CONDITION C.

P.ve GRVS Beestei: F'.aR traiRs iRepeFable fOF Fe8S9RS etl:leF tl=laRReguired Action and associated Com[21etion Time of Condition A or B not met in MODE 1, 2, 3, or 4.

D.

Reguired Action and associated Com[21etion Time of Condition A not met in MODE 5 or 6, or during movement of recently irradiated fuel assemblies.

E.

Two CRVS Booster Fan trains ino[2erable in MODE 5 or 6, or during movement of recently irradiated fuel assemblies.

OR OCONEE UNITS 1, 2, & 3 REQUIRED ACTION B.3 Restore CRE boundary to OPERABLE status.

REQUIRED ACTION C. 1 Be in MODE 3.ResteFe 9Re GRVS BeesteF F8R tFaiR te QPE:RABbE:

status.

AND C.2 Be in MODE 5.

D.1 Start the OPERABLE CRVS Booster Fan train.

OR D.2 Sus[2end movement of recently irradiated fuel assemblies.

E.1.

Sus[2end movement of recently irradiated fuel assemblies.

CRVS Booster Fans 3.7.9 COMPLETION TIME (continued)

COMPLETION TIME 1224 hours0.0142 days 0.34 hours 0.00202 weeks 4.65732e-4 months 36 hours Immediately Immediately Immediately 3.7.9-2 Amendment Nos. xxx~. xxx~. ~ xxx~

,~---

CONDITION One or more CRVS Booster Fan trains inoperable due to an inoperable CRE boundary in MODE 5 or 6, or during movement of recently irradiated fuel assemblies.

OCONEE UNITS 1, 2, & 3 REQUIRED ACTION 3.7.9-3 CRVS Booster Fans 3.7.9 COMPLETION TIME (continued)

Amendment Nos. xxx~. xxx~. &j xxx~

ACTIONS (continued)

CONDITION F.

Two CRVS Booster Fan trains inogerable in MODE 1, 2, 3, or 4 for reasons other than Condition B.

G.

Reguired Action and associated Comgletion Time of Condition F not met.

OCONEE UNITS 1, 2, & 3 F.1 G.1 REQUIRED ACTION Restore one CRVS Booster Fan train to OPERABLE status.

Enter LCO 3.0.3.

CRVS Booster Fans 3.7.9 COMPLETION TIME 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Immediately (continued) I 3.7.9-4 Amendment Nos. xxx~. xxx~. &j xxx~

GQNQl+IGN REQ6JIREQ AG+IGN Q.

ReEjl::liFed,A,stieR aRd Q.1 Be iR MGQE 3.

assesiated Gem13letieR

+ime Ret met iR MGQE AN{}

1, 2, 3, 9F 4.

Q.2 Be iR MGQE a E.

ReEjl::liFed AstieR aRd E.1 S1::1s13eRd mevemeRt ef assesiated Gem13letieR FeseRtly iFFadiated f1::1el

+ime Ret met d1::1FiR§ assemblies.

mevemeRt ef FeseRtly iFFadiated f1::1el assemblies.

SURVEILLANCE REQUIREMENTS SR 3.7.9.1 SR 3.7.9.2 SR 3.7.9.3 SR 3.7.9.4 SURVEILLANCE Operate each CRVS Booster Fan train for 2 1 he1::1F15 minutes.

Perform required CRVS Booster Fan train filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

Verify the control room isolates on a manual actuation signal.

Perform required CRE unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program.

CRVS Booster Fans 3.7.9 GGMPbE+IGN +IME 12 h91::1FS 3e h91::1FS Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the VFTP In accordance with the Surveillance Frequency Control Program In accordance with the Control Room Envelope Habitability Program (continued)

OCONEE UNITS 1, 2, & 3 3.7.9-5 Amendment Nos. xxx~. xxx374, &I xxx~

SURVEILLANCE REQUIREMENTS (continued)

~R3.7.9.5~

SURVEILLANCE Verify the makeup flow rate for each booster fan is 1350 cfm +/-10% (i.e.. 1215 cfm to 1485 cfm) and < 1485 when supplying the control room with outside air tv;o CRVS Booster Fan trains can maintain the Control Room at a positive pressure.

CRVS Booster Fans 3.7.9 FREQUENCY In accordance with the Surveillance Frequency Control Program OCONEE UNITS 1, 2, & 3 3.7.9-6 Amendment Nos. xxx~. xxx~. ~ xxx~

\\"

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.22 Protected Service Water System Battery Monitoring and Maintenance Program 5.5.23 This program is applicable only to the Protected Service Water Battery cells and provides for battery restoration and maintenance, based on the recommendation of IEEE Standard 450-1995. "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," including the following:

1. Actions to restore battery cells with float voltage ::; 2.13 V;

2. Actions to determine whether the float voltage of the remaining battery cells is

> 2.13 V when the float voltage of a battery cell has been found to be ::; 2.13 V;

3. Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates;

4. Limits on average electrolyte temperature, battery connection resistance, and battery terminal voltage; and

5. A requirement to obtain specific gravity readings of all cells at each discharge test, consistent with manufacturer recommendations Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that. with an OPERABLE Control Room Ventilation System. CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event. hazardous chemical release. or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (OBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident.

The program shall include the following elements:

a.

The definition of the CRE and the CRE boundary.

b.

Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.

c.

Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197.

"Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors." Revision 0, May 2003, and (ii) assessing CRE habitability at the OCONEE UNITS 1, 2, & 3

& xxxa37-5.0-23 Amendment Nos. xxx~. xxx~.

5.5 Programs and Manuals Programs and Manuals 5.5 5.5.23 Control Room Envelope Habitability Program (continued)

Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d.

Measurement. at designated locations. of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CRVS, operating at the flow rate required by the VFTP. at a frequency of 24 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 24 month assessment of the CRE boundary.

e.

The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c.

The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of OBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f.

The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage. and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

OCONEE UNITS 1, 2, & 3

&xxx~

5.0-24 Amendment Nos. xxxJ8e, xxxJ88.,

5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements Reporting Requirements 5.6 The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Deleted 5.6.2 Annual Radiological Environmental Operating Report

NOTE---------------------------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year.

The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.8.2, IV.8.3, ar:td IV.C.

OCONEE UNITS 1, 2, & 3

& xxxJ37.

5.0-25 Amendment Nos. xxx~. xxx~.

5.6 Reporting Requirements (continued) 5.6.3 Radioactive Effluent Release Report Reporting Requirements 5.6

1'\\J()l"E---------------------------------------------------

A single submittal may be made for a multiple unit station. l"he submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

l"he Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. l"he report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

l"he material provided shall be consistent with the objectives outlined in the

()DCM and Process Control Program and in conformance with 1 O CFR 50.36a and 10 CFR part 50, Appendix I,Section IV.8.1.

5.6.4 Deleted 5.6.5 C()RE ()PERAl"ll'\\JG LIMll"S REP()R"f (C()LR)

Core operating limits shall be established, determined and issued in accordance with the following:

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and sh~ll be documented in the C()LR for the following:

1.

Shutdown Margin limit for Specification 3.1.1;

2.

Moderator l"emperature Coefficient limit for Specification 3.1.3;

3.

Physical Position, Sequence and ()verlap limits for Specification 3.2.1 Rod Insertion Limits;

4.

AXIAL P()WER IMBALAl'\\JCE operating limits for Specification 3.2.2;

5.

QUADRAl'\\Jl" P()WER l"IL l" (QPl") limits for Specification 3.2.3;

()C()l'\\JEE Ul'\\Jll"S 1, 2, & 3

& xxxJg.7.

5.0-26 Amendment !'\\Jos. xxxJOO, xxx~.

5.6 Reporting Requirements Reporting Requirements 5.6 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

6.

Nuclear Overpower Flux/Flow/Imbalance and RCS Variable Low Pressure allowable value limits for Specification 3.3.1;

7.

RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits for Specification 3.4.1

8.

Core Flood Tanks Boron concentration limits for Specification 3.5.1;

9.

Borated Water Storage Tank Boron concentration limits for Specification 3.5.4;

10.

Spent Fuel Pool Boron concentration limits for Specification 3. 7.12;

11.

RCS and Transfer Canal boron concentration limits for Specification 3.9.1; and

12.

AXIAL POWER IMBALANCE protective limits and RCS Variable Low Pressure protective limits for Specification 2.1.1.

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

(1)

DPC-NE-1002-A, Reload Design Methodology II; (2)

NFS-1001-A, Reload Design Methodology; (3)

DPC-NE-2003-P-A, Oconee Nuclear Station Core Thermal Hydraulic Methodology Using VIPRE-01; (4)

DPC-NE-1004-A, Nuclear Design Methodology Using CASM0-3/SIMULATE-3P; (5)

DPC-NE-2008-P-A, Fuel Mechanical Reload Analysis Methodology Using TAC03 and GDTACO; (6)

BAW-10192-P-A, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants; OCONEE UNITS 1, 2, & 3

& xxxJ37.

5.0-27 Amendment Nos. xxx~. xxx~.

5.6 Reporting Requirements Reporting Requirements 5.6 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

(7)

DPC-NE-3000-P-A, Thermal Hydraulic Transient Analysis Methodology; (8)

DPC-NE-2005-P-A, Thermal Hydraulic Statistical Core Design Methodology; (9)

DPC-NE-3005-P-A, UFSAR Chapter 15 Transient Analysis Methodology :

(10)

BAW-10227-P-A, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel; (11)

BAW-10164P-A, RELAP 5/MOD2-B&W - An Advanced Computer Program for Light Water Reactor LOCA and non-LOCA Transient Analysis; and (12)

DPC-NE-1006-P-A, Oconee Nuclear Design Methodology Using CASM0-4/SIMULATE-3 (Revision 0, May 2009).

The COLR will contain the complete identification for each of the Technical Specifications referenced topical reports used to prepare the COLR (i.e.,

report number, title, revision number, report date or NRC SER date, and any supplements).

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SOM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Post Accident Monitoring (PAM) and Main Feeder Bus Monitor Panel (MFPMP)

Report When a report is required by Condition B or G of LCO 3.3.8, "Post Accident Monitoring (PAM) Instrumentation" or Condition D of LCO 3.3.23, "Main Feeder Bus Monitor Panel," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring (PAM only),

the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

OCONEE UNITS 1, 2, & 3 xxx38-7 5.0-28 Amendment Nos. xxxd8e, xxx~, &

5.6 Reporting Requirements 5.6.7 Tendon Surveillance Report Reporting Requirements 5.6 Any abnormal degradation of the containment structure detected during the tests required by the Pre-stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken.

5.6.8 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with Specification 5.5.10, Steam Generator (SG) Program. The report shall include:

a.

The scope of inspections performed on each SG,

b.

Active degradation mechanisms found,

c.

Nondestructive examination techniques utilized for each degradation mechanism,

d.

Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e.

Number of tubes plugged during the inspection outage for each active degradation mechanism,

f.

Total number and percentage of tubes plugged to date,

g.

The results of condition monitoring, including the results of tube pulls and in-situ testing, and

h.

The effective plugging percentage for all plugging in each SG.

OCONEE UNITS 1, 2, & 3 xxxJg+

5.0-29 Amendment Nos. xxx~. xxx3M, &

I CRVS Booster Fans B 3.7.9 B 3. 7 PLANT SYSTEMS B 3.7.9 Control Room Ventilation System (CRVS) Booster Fans BASES BACKGROUND The CRVS Booster Fan trains provide a protected environment from which operators occupants can control the unit following an uncontrolled 1*

release of radioactivity, hazardous chemicals, or toxic gassmoke.

The CRVS consists of two Booster Fan trains that draw outside air and filter the air in the control room envelope (CRE) and a CRE boundary that limits the in leakage of unfiltered air (Ref. 1 ). Each CRVS Booster Fan train provides 50% capacity and consists of a fan filter assembly, Booster Fans, Ducting, and Dampers. Each CRVS Booster FanfH.tef--_train consists of a pre-filter, a high efficiency particulate air (HEPA) filter, and a charcoal filter for removal of gaseous activity (principally iodines). and a 100% capacity fan. Ductwork. valves or dampers. doors. barriers. and instrumentation also form part of the system..,.

The CRE is the area within the confines of the CRE boundary that contains the spaces that control room occupants inhabit to control the unit during normal and accident conditions. This area encompasses the control room. and may encompass other non-critical areas to which frequent personnel access or continuous occupancy is not necessary in the event of an accident. The CRE is protected during normal operation, natural events. and accident conditions. The CRE boundary is the combination of walls. floor, roof. ducting, doors. penetrations and equipment that physically form the CRE. The OPERABILITY of the CRE boundary must be maintained to ensure that the inleakage of unfiltered air into the CRE will not exceed the inleakage assumed in the licensing basis analysis of the design basis accident (OBA) consequences to CRE occupants. The CRE and its boundary are defined in the Control Room Envelope Habitability Program.

The CRVS Booster Fan.trains areis an emergency system. Upon receipt of a radiation alarm from the Control Room air radiation monitor, the CRVS Booster Fan trains can beare started manually to minimize unfiltered air from entering the control room. Upon starting the fans, dampers are automatically positioned to isolate the control room. The pre-filters remove any large particles in the air, and any entrained water droplets present, to prevent excessive loading of the HEPA and carbon filters.

The t\\voEach CRVS Booster Fan trains, when operated simultaneously, is capable of CRE unfiltered air infiltration below analyzed limits. Both CRVS Booster Fan trains operating simultaneously are capable of OCONEE UNITS 1, 2, & 3 B 3.7.9-1 Rev. 001BASES REVISION DP.TED 08/28/14

positively pressurizing the associated CREcan pressurize the Control Room to minimize infiltration of unfiltered air. The CRVS operation is discussed in the UFSAR, Section 9.4 (Ref. 1 ). The CRVS is designed to maintain a habitable environment in the CRE for 30-days of continuous occupancy after a Design Basis Accident (OBA), without exceeding a 5 rem total effective dose equivalent (TEDE).

APPLICABLE The CRVS Booster Fan train components are arranged in two ventilation trains. The SAFETY ANALYSIS location of components and ducting within the CRE ensures an adequate supply of filtered air to all areas requiring access. The CRVS provides airborne radiological protection for the control room operators CRE occupants as demonstrated by the CRE occupant dose analyses for the most limiting design basis loss of coolant accident fission product release presented in the UFSAR, Chapter 15 (Ref. 2).

LCO The CRVS Booster Fan trains provide protection from smoke and hazardous chemicals to the CRE occupants. The analysis of hazardous chemical releases demonstrates that the toxicity limits are not exceeded in the CRE following a hazardous chemical release (Ref. 3). The evaluation of a smoke challenge demonstrates that it will not result in the inability of the CRE occupants to control the reactor either from the control room or from the Standby Shutdown Facility (Ref. 6).

The CRVS Booster Fan trains satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii)

(Ref.1J).

Two +we-CRVS train§.s areara required to be OPERABLE to ensure that at least one is available if a single active failure disables the other train..-

Total system failure, such as from a loss of both ventilation trains or from an inoperable CRE boundary, could result in exceeding a dose of 5 rem TEDE to the CRE occupants ontrol Room operators in the event of a large radioactive release.

Each+Ae CRVS Booster Fan trainj§_8-3fe-considered OPERABLE when the individual components necessary to limit CRE occupant control operator exposure are OPERABLE in both trains. A CRVS Booster Fan train is considered OPERABLE when the associated:

a.

Booster Fan is OPERABLE;

b.

HEPA filter and carbon absorber are not excessively restricting flow, and are capable of performing their filtration functions; and

c.

Ductwork, valves, and flowpath dampers are OPERABLE, and control room unfiltered inleakagepressurization can be maintained within limits both trains operating.

LCO _____ In order for the CRVS Booster Fan trains to be considered OPERABLE.

(continued) the CRE boundary must be maintained such that the CRE occupant dose from a large radioactive release does not exceed the calculated dose in the licensing basis consequences analyses for DBAs and that CRE occupants are protected from hazardous chemicals and smoke.

APPLICABILITY ACTIONS The LCO is modified by a Note allowing the CRE boundary to be opened intermittently under administrative controls. This Note only applies to openings in the CRE boundary that can be rapidly restored to the design condition, such as doors. hatches, floor plugs, and access panels. For entry and exit through doors. the administrative control of the opening is performed by the person(s) entering or exiting the area. For other openings, these controls should be proceduralized and consist of stationing a dedicated individual at the opening who is in continuous communication with the operators in the CRE. This individual will have a method to rapidly close the opening and to restore the CRE boundary to a condition equivalent to the design condition when a need for CRE isolation is indicated. addition, the Control Room boundary, including the integrity of the walls, floors, ceilings, duct\\vork, return air temporary isolation panels, supply air temporary isolation plate, and access doors, must be maintained within the assumptions of the design analysis.

Breaches (excluding the removal of system performance test port caps per testing procedures) in'the CRVS, most commonly due to the opening of access doors, introduces the possibility of allowing unfiltered or unanalyzed concentrations of inleakage into the Control Room. This applies to breaches of the outside air filter trains, main air handling units and all duct\\vork outside the Control Room pressure boundary. Breaches are equivalent tq t\\vo Booster Fan trains out of service.

In MODES 1, 2, 3, aAG-4, 5, and 6, and during movement of recently irradiated fuel assembles for any unit. the CRVS Booster Fan trains must be OPERABLE to ensure that the CRE will remain habitable reduce radiation dose to personnel in the Control Room during and following a DBAn accident.

During movement of recently irradiated fuel assemblies by any unit, the CRVS Booster Fan trains must be OPERABLE to cope with a release due to a fuel handling accident involving handling recently irradiated fuel. Due to radioactive decay, the CRVS is only required to mitigate fuel handling accidents involving handling recently irradiated fuel (i.e., fuel that has occupied part of a critical reactor core within the previous 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ).

With one the t\\vo CRVS Booster Fan train inoperable for reasons other than an inoperable CRE boundary, action must be taken to restore OPERABLE status within 7 days. In this Condition, the remaining OPERABLE CRVS Booster Fan train is adequate to perform the CRE occupant protection function. However. the overall reliability is reduced because a failure in the OPERABLE CRVS Booster Fan train could result in loss of CRVS function. The 7 day Completion Time is based on the low probability of a OBA occurring during this time period and ability of the remaining booster fan train to provide the required capability. s incapable of pressurizing the control room, the capability to pressurize the control room must be restored within 30 days. In this Condition, the capability to minimize the radiation dose to personnel located in the Control Room during and after an accident is not assured. One or both CRVS Booster Fan trains may be OPERABLE in this Condition. If one or

ACTIONS both CRVS Booster rans are simultaneously inoperable, the Completion Time for these separate Conditions is more limiting than the 30 day Completion Time for Action A.1. If OPERABLE the CRVS Booster ran train(s) can provide some dose reduction. The 30 day Completion Time is based on the low probability of an accident occurring during the time period and the potential for OPERABLE CRVS Booster ran trains to provide some dose reduction.

B.1. B.2, and B.3 If the unfiltered inleakage of potentially contaminated air past the CRE boundary and into the CRE can result in CRE occupant radiological dose B.1. B.2, and B.3 (continued) greater than the calculated dose of the licensing basis analyses of consequences (allowed to be up to 5 rem TEDE), or inadequate protection of CRE occupants from hazardous chemicals or smoke. the CRE boundary is inoperable. Actions must be taken to restore an OPERABLE CRE boundary within 90 days.

During the period that the CRE boundary is considered inoperable. action must be initiated to implement mitigating actions to lessen the effect on CRE occupants from the potential hazards of a radiological or chemical event or a challenge from smoke. Actions must be taken with 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to verify that in the event of a DBA. the mitigating actions will ensure that CRE occupant radiological exposures will not exceed limits and that CRE occupants are protected from hazardous chemicals and smoke. These mitigating actions (i.e., actions that are taken to offset the consequences of the inoperable CRE boundary) should be preplanned for implementation upon entry into the condition, regardless of whether entry is intentional or unintentional. The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion Time is reasonable based on the low probability of a DBA occurring during this time period. and the use of mitigating actions. The 90 day Completion Time is reasonable based on the determination that the mitigating actions will ensure protection of CRE occupants within analyzed limits while limiting the probability that CRE occupants will have to implement protective measures that may adversely affect their ability to control the reactor and maintain it in a safe shutdown condition in the event of a OBA. In addition. the 90 day Completion Time is a reasonable time to diagnose. plan and possibly repair. and test most problems with the CRE boundary. VVith one CRVS Booster ran train inoperable fur reasons other than Condition A, action must be taken to restore the train to OPERABLE status *.vithin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . In this Condition, the remaining OPERABLE CRVS Booster ran train provides some dose reduction for personnel in the Control Room. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is based on the low probability of an accident occurring during this time period, and ability of the remaining train to provide some dose reduction.

C.1 and C.2 In MODE 1. 2. 3, or 4, if the inoperable CRVS Booster Fan train or the CRE boundary cannot be restored to OPERABLE status within the

ACTIONS required Completion Time. the unit must be placed in a MODE that minimizes accident risk. To achieve this status. the unit must be placed in at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . and in MODE 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable. based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging the systems.

With the t\\vo CRVS Booster Fan trains inoperable for reasons other than Condition A, one train must be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . In this Condition, the capability to minimize the radiation dose to personnel located in the Control Room during and after an accident is unavailable. The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion Time is based on the low probability of an accident occurring during this time period.

D.1 and D.2 In MODE 5 or 6, or during movement of recently irradiated fuel assemblies. if the inoperable CRVS Booster Fan train cannot be restored D.1 and D.2 (continued) to OPERABLE status within the required Completion Time, the OPERABLE CRVS Booster Fan train must be started. This action ensures that the remaining train is OPERABLE. and that any active failure will be readily detected. An alternative to Required Action D.1 is to immediately suspend activities that could release radioactivity that might require isolation of the CRE. This places the unit in a condition that minimizes the accident risk. This does not preclude the movement of fuel to a safe position.If the inoperable CRVS Booster Fan trains cannot be restored to OPERABLE status within the required Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and in MODE 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full po*.ver conditions in an orderly manner and without challenging unit systems.

In MODE 5 or 6, or during movement of recently irradiated fuel assembles. when two CRVS Booster Fan trains are inoperable. or with one or more CRVS Booster Fan trains inoperable due to an inoperable CRE boundary, action must be taken immediately to suspend activities that could result in a release of radioactivity that might require isolation of the CRE. This places the unit in a condition that minimized the accident risk. This does not preclude the movement of fuel to a safe position.During movement of recently irradiated fuel assemblies, when one or more CRVS trains are inoperable, action must be taken immediately to suspend activities that could release radioactivity that might require isolation of the control room. This places the unit in a condition that minimizes the accident risk. This does not preclude the movement of fuel to a safe position.

If both CRVS trains are inoperable in MODE 1, 2, 3, or 4 for reasons other than an inoperable CRE boundary (i.e.. Condition B). one

train must be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . In this Condition, the capability to minimize the radiation dose personnel located in the Control Room during and after an accident is unavailable. The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion Time is based on the low probability of an accident occurring during this time period.

G.1 If the Required Action and associated Completion Time of Condition F is not met. LCO 3.0.3 must be entered immediately.

SURVEILLANCE SR 3.7.9.1 REQUIREMENTS Standby systems should be checked periodically to ensure that they function properly. As the environment and normal operating conditions on this system are not severe, testing each train once every month adequately checks this system. The trains need only be operated for

15 minutesone hour and all dampers verified to be OPERABLE to demonstrate SURVEILLANCE SR 3.7.9.1 (continued)

REQUIREMENTS the function of the system. This test includes an external visual inspection of the CRVS Booster Fan trains. The Surveillance Frequency is based on the known reliability of the equipment and will be managed in accordance with the operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.

SR 3.7.9.2 This SR verifies that the required CRVS Booster Fan train testing is performed in accordance with the Ventilation Filter Testing Program (VFTP). The VFTP includes testing HEPA filter performance. carbon absorber efficiency. minimum system flow rate. and the physical properties of the activated carbon,:_ CRVS Booster Fan train filter test frequencies are in accordance with Regulatory Guide 1.52 (Ref. 4). The VFTP includes testing HEPA filter performance and carbon adsorber efficiency. Specific test frequencies and additional information are discussed in detail in the VFTP.

SR 3.7.9.3 This SR verifies that the CRE isolates and operates on a manual actuation signal. The Frequency is based on industry operating experience and is consistent with the typical refueling cycle and will be managed in accordance with the Surveillance Frequency Control Program.e integrity of the Control Room enclosure. The Control Room positive pressure, with respect to potentially contaminated adjacent areas, is periodically tested to verify that the CRVS Booster Fan trains

SURVEILLANCE REQUIREMENTS REFERENCES are functioning properly. During the emergency mode of operation, the CRVS Booster Fan trains are designed to pressurize the Control Room to minimize unfiltered inleakage. The CRVS Booster Fan trains are designed to maintain this positive pressure with both trains in operation.

SR 3.7.9.4 The Surveillance Frequency verifies the OPERABILITY of the CRE boundary by testing for unfiltered air inleakage past the CRE boundary and into the CRE. The details of the testing are specified in the Control Room Envelope Habitability Programis based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.

The CRE is considered habitable when the radiological dose to CRE occupants calculated in the licensing basis analyses of OBA consequences is no more than 5 rem TEDE and the CRE occupants are protected from hazardous chemicals and smoke. This SR verifies that the unfiltered air inleakage into the CRE is no greater than the flow rate assumed in the licensing basis analyses of OBA consequences. When unfiltered air inleakage is greater than the assumed flow rate, Condition B must be entered. Required Action B.3 allows time to restore the CRE boundary to OPERABLE status provided mitigating actions can ensure that the CRE remains within the licensing basis habitability limits for the occupants following an accident. Compensatory measures are discussed in Regulatory Guide 1.196, Section C.2. 7.3, (Ref. 6) which endorses. with exceptions. NEI 99-03, Section 8.4 and Appendix F (Ref. 7). These compensatory measures may also be used as mitigating actions as SR 3.7.9.4 (continued) required by Required Action B.2. Temporary analvtical methods may also be used as compensatory measures to restore OPERABILITY (Ref. 8).

Options for restoring the CRE boundary to OPERABLE status include changing the licensing basis OBA consequence analysis. repairing the CRE boundary, or a combination of these actions. Depending upon the nature of the problem and the corrective action. a full scope inleakage test may not be necessary to establish that the CRE boundary has been restored to OPERABLE status.

SR 3.7.9.5 This SR verifies the CRVS can supply the CRE with outside air to meet the design requirement. The design flowrate of each booster fan is 1350 cfm +/-10% (i.e.. 1215 cfm to 1485 cfm). This lower limit ensures each train is capable of supplying enough air to meet the minimum total system flowrate requirement of 1215 cfm. The 1485 cfm upper limit is required to meet the carbon filter residence time limit of each individual booster fan train (Ref. 5). The frequency is consistent with industry practice and other filtration SRs. and will be managed in accordance with the Surveillance Frequency Control Program.

1. UFSAR, Section 9.4.

2. UFSAR, Chapter 15.

3. UFSAR, Section 6.4.2.5 L 1 O CFR 50.36.

5. Regulatory Guide 1.52, Rev. 4Regulatory Guide 1.52, Rev. 2, March

~.:.

4.-_6._Regulatory Guide 1.196, Rev. 1.

5-:_7._NEI 99-03, "Control Room Habitability Assessment," June 2001.

§.,__Letter from Eric J. Leeds (NRC) to James W. Davis (NEI) dated January 30, 2004, "NEI Draft White Paper, Use of Generic Letter 91-18 Process and Alternative Source Terms in the Context of Control Room Habitability."

ATTACHMENT 2 REVISED TECHNICAL SPECIFICATION AND BASES PAGES Remove page*

lnse.rt page 3.7.9-1 3.7.9-1 3.7.9-2 3.7.9-2 3.7.9-3 3.7.9-4 5.0-23 5.0-23 5.0-24 5.0-24 5.0-25 5.0-25 5.0-26 5.0-26 5.0-27 5.0-27 5.0-28 5.0-28 5.0-29 B 3.7.9-1 B 3.7.9-1 B 3.7.9-2 B 3.7.9-2 B 3.7.9-3 B 3.7.9-3 B 3.7.9-4 B 3.7.9-4 B 3.7.9-5 B 3.7.9-5 B 3.7.9-6 B 3.7.9-7

3. 7 PLANT SYSTEMS 3.7.9 Control Room Ventilation Sys~em (CRVS) Booster Fans LC() 3.7.9 Two CRVS Booster Fan trains shall be ()PERABLE.

CRVS Booster Fans 3.7.9

N()TE----------------------------------------------

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY:

M()DES 1, 2, 3, 4, 5, and 6, During movement of recently irradiated fuel assemblies for any unit.

ACTl()NS C()NDITl()N REQUIRED ACTl()N COMPLETl()N TIME A.

()ne CRVS Booster Fan A.1 Restore CRVS Booster 7 days train inoperable for Fan train to ()PERABLE reasons other than status.

Condition B.

B.

()ne or more CRVS B.1 Initiate action to Immediately Booster Fan trains implement mitigating inoperable due to actions.

inoperable CRE boundary in M()DE 1, 2, AND 3, or4.

B.2 Verify mitigating actions 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ensure CRE occupant radiological exposures will not exceed limits and CRE occupants are protected from chemical and smoke hazards.

AND B.3 Restore CRE boundary 90 days to ()PERABLE status.

(continued)

()C()NEE UNITS 1, 2, & 3 3.7.9-1 Amendment Nos. xxx, xxx, & xxx

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

ACTIONS (continued)

CONDITION

c.

Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, 3, or 4.

D.

Required Action and associated Completion Time of Condition A not met in MODE 5 or 6, or during movement of recently irradiated fuel assemblies.

E.

Two CRVS Booster Fan trains inoperable in MODE 5 or 6, or during movement of recently irradiated fuel assemblies.

OR One or more CRVS Booster Fan trains inoperable due to an inoperable CRE boundary in MODE 5 or 6, or during movement of recently irradiated fuel assemblies.

OCONEE UNITS 1, 2, & 3 C.1 AND C.2 D.1 OR D.2 E.1 REQUIRED ACTION Be in MODE 3.

Be in MODE 5.

Start the OPERABLE CRVS Booster Fan train.

Suspend movement of recently irradiated fuel assemblies.

CRVS Booster Fans 3.7.9 COMPLETION TIME 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours Immediately Immediately Immediately (continued) 3.7.9-2 Amendment Nos. xxx, xxx, & xxx

ACTIONS (continued)

CONDITION REQUIRED ACTION F.

Two CRVS Booster Fan F.1 Restore one CRVS trains inoperable in Booster Fan train to MODE 1, 2, 3, or 4 for OPERABLE status.

reasons other than Condition B.

G.

Required Action and G.1 Enter LCO 3.0.3.

associated Completion Time of Condition F not met.

SURVEILLANCE REQUIREMENTS SR 3.7.9.1 SR 3.7.9.2 SR 3.7.9.3 SR 3.7.9.4 SURVEILLANCE Operate each CRVS Booster Fan train for

~ 15 minutes.

Perform required CRVS Booster Fan train filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

Verify the control room isolates on a manual actuation signal.

Perform required CRE unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program.

CRVS Booster Fans 3.7.9 COMPLETION TIME 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the VFTP In accordance with the Surveillance Frequency Control Program In accordance with the Control Room Envelope Habitability Program (continued)

OCONEE UNITS 1, 2, & 3 3.7.9-3 Amendment Nos. xxx, xxx, & xxx

SURVEILLANCE REQUIREMENTS (continued)

SR 3.7.9.5 SURVEILLANCE Verify the makeup flow rate for each booster fan is 1350 cfm +/-10% (i.e., 1215 cfm to 1485 cfm) when supplying the control room with outside air.

CRVS Booster Fans 3.7.9 FREQUENCY In accordance with the Surveillance Frequency Control Program OCONEE UNITS 1, 2, & 3 3.7.9-4 Amendment Nos. xxx, xxx, & xxx

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.22 Protected Service Water System Battery Monitoring and Maintenance Program 5.5.23 This program is applicable only to the Protected Service Water Battery cells and provides for battery restoration and maintenance, based on the recommendation of IEEE Standard 450-1995. "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," including the following:

1. Actions to restore battery cells with float voltage s 2.13 V;

2. Actions to determine whether the float voltage of the remaining battery cells is

> 2.13 V when the float voltage of a battery cell has been found to be s 2.13 V;

3. Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates;

4. Limits on average electrolyte temperature, battery connection resistance, and battery terminal voltage; and

5. A requirement to obtain specific gravity readings of all cells at each discharge test, consistent with manufacturer recommendations Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Ventilation System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (OBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident.

The program shall include the following elements:

a.

The definition of the CRE and the CRE boundary.

b.

Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.

c.

Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the OCONEE UNITS 1, 2, & 3 5.0-23 Amendment Nos. xxx, xxx, & xxx

5.5 Programs and Manuals Programs and Manuals 5.5 5.5.23 Control Room Envelope Habitability Program (continued)

Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d.

Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CRVS, operating at the flow rate required by the VFTP, at a frequency of 24 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 24 month assessment of the CRE boundary.

e.

The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c.

The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f.

The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

OCONEE UNITS 1, 2, & 3 5.0-24 Amendment Nos. xxx, xxx, & xxx

5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements Reporting Requirements 5.6 The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Deleted 5.6.2 Annual Radiological Environmental Operating Report

NOTE---------------------------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year.

The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 1 O CFR 50, Appendix I, Sections IV.8.2, IV.8.3, and IV.C.

OCONEE UNITS 1, 2, & 3 5.0-25 Amendment Nos. xxx, xxx, & xxx

5.6 Reporting Requirements (continued) 5.6.3 Radioactive Effluent Release Report Reporting Requirements 5.6

1\\!()"f E---------------------------------------------------

A single submittal may be made for a multiple unit station. "fhe submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

"fhe Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. "fhe report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

"fhe material provided shall be consistent with the objectives outlined in the

()DCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR part 50, Appendix I,Section IV.B.1.

5.6.4 Deleted 5.6.5 C()RE ()PERA"fll\\IG LIMl"fS REP()R"f (C()LR)

Core operating limits shall be established, determined and issued in accordance with the following:

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the C()LR for the following:

1.

Shutdown Margin limit for Specification 3.1.1;

2.

Moderator "f emperature Coefficient limit for Specification 3.1.3;

3.

Physical Position, Sequence and ()verlap limits for Specification 3.2.1 Rod Insertion Limits;

4.

AXIAL P()WER 1.MBALAl\\ICE operating limits for Specification 3.2.2;

5.

QUADRAl\\l"f P()WER l"IL "f (QP"f) limits for Specification 3.2.3;

()C()l\\IEE Ul\\lll"S 1, 2, & 3 5.0-26 Amendment l\\los. xxx*, xxx, & xxx

5.6 Reporting Requirements Reporting Requirements 5.6 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

6.

Nuclear Overpower Flux/Flow/Imbalance and RCS Variable Low Pressure allowable value limits for Specification 3.3.1;

7.

RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits for Specification 3.4.1

8.

Core Flood Tanks Boron concentration limits for Specification 3.5.1;

9.

Borated Water Storage Tank Boron concentration limits for Specification 3.5.4;

10.

Spent Fuel Pool Boron concentration limits for Specification 3.7.12;

11.

RCS and Transfer Canal boron concentration limits for Specification 3.9.1; and

12.

AXIAL POWER IMBALANCE protective limits and RCS Variable Low Pressure protective limits for Specification 2.1.1.

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

(1)

DPC-NE-1002-A, Reload Design Methodology II; (2)

NFS-1001-A, Reload Design Methodology; (3)

DPC-NE-2003-P-A, Oconee Nuclear Station Core Thermal Hydraulic Methodology Using VIPRE-01; (4)

DPC-NE-1004-A, Nuclear Design Methodology Using CASM0-3/SIMULATE-3P; (5)

DPC-NE-2008-P-A, Fuel Mechanical Reload Analysis Methodology Using TAC03 and GDTACO; (6)

BAW-10192-P-A, BWNT LOCA-BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants; OCONEE UNITS 1, 2, & 3 5.0-27 Amendment Nos. xxx, xxx, & xxx

5.6 Reporting Requirements Reporting Requirements 5.6 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

(7)

DPC-NE-3000-P-A, Thermal Hydraulic Transient Analysis Methodology; (8)

DPC-NE-2005-P-A, Thermal Hydraulic Statistical Core Design Methodology; (9)

DPC-NE-3005-P-A, UFSAR Chapter 15 Transient Analysis Methodology :

(10)

BAW-10227-P-A, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel; (11)

BAW-10164P-A, RELAP 5/MOD2-B&W -An Advanced Computer Program for Light Water Reactor LOCA and non-LOCATransient Analysis; and (12)

DPC-NE-1006-P-A, Oconee Nuclear Design Methodology Using CASM0-4/SIMULATE-3 (Revision 0, May 2009).

The COLR will contain the complete identification for each of the Technical Specifications referenced topical reports used to prepare the COLR (i.e.,

report number, title, revision number, report date or NRC SER date, and any supplements).

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SOM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Post Accident Monitoring (PAM) and Main Feeder Bus Monitor Panel (MFPMP)

Report When a report is required by Condition B or G of LCO 3.3.8, "Post Accident Monitoring (PAM) Instrumentation" or Condition D of LCO 3.3.23, "Main Feeder Bus Monitor Panel," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring (PAM only),

the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

OCONEE UNITS 1, 2, & 3 5.0-28 Amendment Nos. xxx, xxx, & xxx

5.6 Reporting Requirements 5.6.7 Tendon Surveillance Report Reporting Requirements 5.6 Any abnormal degradation of the containment structure detected during the tests required by the Pre-stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken.

5.6.8 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with Specification 5.5.10, Steam Generator (SG) Program. The report shall include:

a.

The scope of inspections performed on each SG,

b.

Active degradation mechanisms found,

c.

Nondestructive examination techniques utilized for each degradation mechanism,

d.

Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e.

Number of tubes plugged during the inspection outage for each active degradation mechanism,

f.

Total number and percentage of tubes plugged to date,

g.

The results of condition monitoring, including the results of tube pulls and in-situ testing, and

h.

The effective plugging percentage for all plugging in each SG.

OCONEE UNITS 1, 2, & 3 5.0-29 Amendment Nos. xxx, xxx, & xxx I

CRVS Booster Fans B 3.7.9 B 3. 7 PLANT SYSTEMS B 3.7.9 Control Room Ventilation System (CRVS) Booster Fans BASES BACKGROUND The CRVS Booster Fan trains provide a protected environment from which occupants can control the unit following an uncontrolled release of radioactivity, hazardous chemicals, or smoke.

The CRVS consists of two Booster Fan trains that draw outside air and filter the air in the control room envelope (CRE) and a CRE boundary that limits the inleakage of unfiltered air (Ref. 1 ). Each CRVS Booster Fan train consists of a pre-filter, a high efficiency particulate air (HEPA) filter, and a charcoal filter for removal of gaseous activity (principally iodines),

and a 100% capacity fan. Ductwork, valves or dampers, doors, barriers, and instrumentation also form part of the system.

The CRE is the area within the confines of the CRE boundary that contains the spaces that control room occupants inhabit to control the unit during normal and accident conditions. This area encompasses the control room, and may encompass other non-critical areas to which frequent personnel access or continuous occupancy is not necessary in the event of an accident. The CRE is protected during normal operation, natural events, and accident conditions. The CRE boundary is the combination of walls, floor, roof, ducting, doors, penetrations and equipment that physically form the CRE. The OPERABILITY of the CRE boundary must be maintained to ensure that the inleakage of unfiltered air into the CRE will not exceed the inleakage assumed in the licensing basis analysis of the design basis accident (OBA) consequences to CRE occupants. The CRE and its boundary are defined in the Control Room Envelope Habitability Program.

The CRVS is an emergency system. Upon receipt of a radiation alarm from the Control Room air radiation monitor, the CRVS Booster Fan trains are started manually to minimize unfiltered air from entering the control room. Upon starting the fans, dampers are automatically positioned to isolate the control room. The pre-filters remove any large particles in the air, and any entrained water droplets present, to prevent excessive loading of the HEPA and carbon filters.

Each CRVS Booster Fan train, is capable of CRE unfiltered air infiltration below analyzed limits. Both CRVS Booster Fan trains operating simultaneously are capable of positively pressurizing the associated CRE. The CRVS operation is discussed in the UFSAR, Section 9.4 (Ref.

1 ). The CRVS is designed to maintain a habitable environment in the CRE for 30-days of continuous occupancy after a Design Basis Accident (OBA), without exceeding a 5 rem total effective dose equivalent (TEDE).

OCONEE UNITS 1, 2, & 3 B 3.7.9-1 Rev. 001

~I

BASES (continued)

APPLICABLE SAFETY ANALYSIS LCO CRVS Booster Fans B 3.7.9 The CRVS components are arranged in two ventilation trains. The location of components and ducting within the CRE ensures an adequate supply of filtered air to all areas requiring access. The CRVS provides airborne radiological protection for the CRE occupants as demonstrated by the CRE occupant dose analyses for the most limiting design basis accident fission product release presented in the UFSAR, Chapter 15 (Ref. 2).

The CRVS Booster Fan trains provide protection from smoke and hazardous chemicals to the CRE occupants. The analysis of hazardous chemical releases demonstrates that the toxicity limits are not exceeded in the CRE following a hazardous chemical release (Ref. 3). The evaluation of a smoke challenge demonstrates that it will not result in the inability of the CRE occupants to control the reactor either from the control room or from the Standby Shutdown Facility (Ref. 6).

The CRVS Booster Fan trains satisfy Criterion 3of10 CFR 50.36(c)(2)(ii)

(Ref. 4).

Two CRVS trains are required to be OPERABLE to ensure that at least one is available if a single active failure disables the other train. Total system failure, such as from a loss of both ventilation trains or from an inoperable CRE boundary, could result in exceeding a dose of 5 rem TEDE to the CRE occupants in the event of a large radioactive release.

Each CRVS Booster Fan train is considered OPERABLE when the individual components necessary to limit CRE occupant exposure are OPERABLE. A CRVS Booster Fan train is considered OPERABLE when the associated:

a.

Booster Fan is OPERABLE;

b.

HEPA filter and carbon absorber are not excessively restricting flow, and are capable of performing their filtration functions; and

c.

Ductwork, valves, and flowpath dampers are OPERABLE, and control room unfiltered inleakage can be maintained within limits.

OCONEE UNITS 1, 2, & 3 B 3.7.9-2 Rev. 001 I

_J

BASES LCO (continued)

APPLICABILITY ACTIONS CRVS Booster Fans B 3.7.9 In order for the CRVS Booster Fan trains to be considered OPERABLE, the CRE boundary must be maintained such that the CRE occupant dose from a large radioactive release does not exceed the calculated dose in the licensing basis consequences analyses for DBAs and that CRE occupants are protected from hazardous chemicals and smoke.

The LCO is modified by a Note allowing the CRE boundary to be opened intermittently under administrative controls. This Note only applies to openings in the CRE boundary that can be rapidly restored to the design condition, such as doors, hatches, floor plugs, and access panels. For entry and exit through doors, the administrative control of the opening is performed by the person(s) entering or exiting the area. For other openings, these controls should be proceduralized and consist of stationing a dedicated individual at the opening who is in continuous communication with the operators in the CRE. This individual will have a method to rapidly close the opening and to restore the CRE boundary to a condition equivalent to the design condition when a need for CRE isolation is indicated.

In MODES 1, 2, 3, 4, 5, and 6, and during movement of recently irradiated fuel assembles for any unit, the CRVS must be OPERABLE to ensure that the CRE will remain habitable during and following a OBA.

During movement of recently irradiated fuel assemblies by any unit, the CRVS Booster Fan trains must be OPERABLE to cope with a release due to a fuel handling accident involving handling recently irradiated fuel. Due to radioactive decay, the CRVS is only required to mitigate fuel handling accidents involving handling recently irradiated fuel (i.e., fuel that has occupied part of a critical reactor core within the previous 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ).

With one CRVS Booster Fan train inoperable for reasons other than an inoperable CRE boundary, action must be taken to restore OPERABLE status within 7 days. In this Condition, the remaining OPERABLE CRVS Booster Fan train is adequate to perform the CRE occupant protection function. However, the overall reliability is reduced because a failure in the OPERABLE CRVS Booster Fan train could result in loss of CRVS function. The 7 day Completion Time is based on the low probability of a OBA occurring during this time period and ability of the remaining booster fan train to provide the required capability.

B.1, B.2, and B.3 If the unfiltered inleakage of potentially contaminated air past the CRE boundary and into the CRE can result in CRE occupant radiological dose OCONEE UNITS 1, 2, & 3 B 3.7.9-3 Rev. 001

BASES (continued)

ACTIONS B.1. B.2, and B.3 (continued)

CRVS Booster Fans B 3.7.9 greater than the calculated dose of the licensing basis analyses of consequences (allowed to be up to 5 rem TEDE), or inadequate protection of CRE occupants from hazardous chemicals or smoke, the CRE boundary is inoperable. Actions must be taken to restore an OPERABLE CRE boundary within 90 days.

During the period that the CRE boundary is considered inoperable, action must be initiated to implement mitigating actions to lessen the effect on CRE occupants from the potential hazards of a radiological or chemical event or a challenge from smoke. Actions must be taken with 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to verify that in the event of a OBA, the mitigating actions will ensure that CRE occupant radiological exposures will not exceed limits and that CRE occupants are protected from hazardous chemicals and smoke. These mitigating actions (i.e., actions that are taken to offset the consequences of the inoperable CRE boundary) should be preplanned for implementation upon entry into the condition, regardless of whether entry is intentional or unintentional. The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion Time is reasonable based on the low probability of a OBA occurring during this time period, and the use of mitigating actions. The 90 day Completion Time is reasonable based on the determination that the mitigating actions will ensure protection of CRE occupants within analyzed limits while limiting the probability that CRE occupants will have to implement protective measures that may adversely affect their ability to control the reactor and maintain it in a safe shutdown condition in the event of a OBA. In addition, the 90 day Completion Time is a reasonable time to diagnose, plan and possibly repair, and test most problems with the CRE boundary.

C.1 and C.2 In MODE 1, 2, 3, or 4, if the inoperable CRVS Booster Fan train or the CRE boundary cannot be restored to OPERABLE status within the required Completion Time, the unit must be placed in a MODE that minimizes accident risk. To achieve this status, the unit must be placed in at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and in MODE 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging the systems.

D.1 and D.2 In MODE 5 or 6, or during movement of recently irradiated fuel assemblies, if the inoperable CRVS Booster Fan train cannot be restored OCONEE UNITS 1, 2, & 3 B 3.. 7.9-4 Rev.001 I

BASES (continued)

ACTIONS D.1 and D.2 (continued)

CRVS Booster Fans B 3.7.9 to OPERABLE status within the required Completion Time, the OPERABLE CRVS Booster Fan train must be started. This action ensures that the remaining train is OPERABLE, and that any active failure will be readily detected. *An alternative to Required Action D.1 is to immediately suspend activities that could release radioactivity that might re.quire isolation of the CRE. This places the unit in a condition that minimizes the accident risk. This does not preclude the movement of fuel to a safe position.

In MODE 5 or 6, or during movement of recently irradiated fuel assembles, when two CRVS Booster Fan trains are inoperable, or with one or more CRVS Booster Fan trains inoperable due to an inoperable CRE boundary, action must be taken immediately to suspend activities that could result in a release of radioactivity that might require isolation of the CRE. This places the unit in a condition that minimized the accident risk. This does not preclude the movement of fuel to a safe position.

If both CRVS trains are inoperable in MODE 1, 2, 3, or 4 for reasons other than an inoperable CRE boundary (i.e., Condition B), one train must be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . In this Condition, the capability to minimize the radiation dose personnel located in the Control Room during and after an accident is unavailable. The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion Time is based on the low probability of an accident occurring during this time period.

If the Required Action and associated Completion Time of Condition F is not met, LCO 3.0.3 must be entered immediately.

SURVEILLANCE SR 3.7.9.1 REQUIREMENTS Standby systems should be checked periodically to ensure that they function properly. As the environment and normal operating conditions on this system are not severe, testing each train once every month adequately checks this system. The trains need only be operated for 2 15 minutes and all dampers verified to be OPERABLE to demonstrate OCONEE UNITS 1, 2, & 3 B 3.7.9-5 Rev. 001 I

BASES (continued)

CRVS Booster Fans B 3.7.9 SURVEILLANCE SR 3.7.9.1 (continued)

REQUIREMENTS the function of the system. This test includes an external visual inspection of the CRVS Booster Fan trains. The Surveillance Frequency is based on the known reliability of the equipment and will be managed in accordance with the Surveillance Frequency Control Program.

SR 3.7.9.2 This SR verifies that the required CRVS Booster Fan train testing is performed in accordance with the Ventilation Filter Testing Program (VFTP). The VFTP includes testing HEPA filter performance, carbon absorber efficiency, minimum system flow rate, and the physical properties of the activated carbon. Specific test frequencies and additional information are discussed in detail in the VFTP.

SR 3.7.9.3

. This SR verifies that the CRE isolates and operates on a manual actuation signal. The Frequency is based on industry operating experience and is consistent with the typical refueling cycle and will be managed in accordance with the Surveillance Frequency Control Program.

SR 3.7.9.4 The Surveillance Frequency verifies the OPERABILITY of the CRE boundary by testing for unfiltered air inleakage past the CRE boundary and into the CRE. The details of the testing are specified in the Control Room Envelope Habitability Program.

The CRE is considered habitable when the radiological dose to CRE occupants calculated in the licensing basis analyses of OBA consequences is no more than 5 rem TEOE and the CRE occupants are protected from hazardous chemicals and smoke. This SR verifies that the unfiltered air inleakage into the CRE is no greater than the flow rate assumed in the licensing basis analyses of OBA consequences. When unfiltered air in leakage is greater than the assumed flow rate, Condition B must be entered. Required Action B.3 allows time to restore the CRE boundary to OPERABLE status provided mitigating actions can ensure that the CRE remains within the licensing basis habitability limits for the occupants following an accident. Compensatory measures are discussed in Regulatory Guide 1.196, Section C.2. 7.3, (Ref. 6) which endorses, with exceptions, NEI 99-03, Section 8.4 and Appendix F (Ref. 7). These compensatory measures may also be used as mitigating actions as OCONEE UNITS 1, 2, & 3 B 3.7.9-6 Rev. 001 I

BASES CRVS Booster Fans B 3.7.9 SURVEILLANCE SR 3.7.9.4 (continued)

REQUIREMENTS REFERENCES required by Required Action B.2. Temporary analytical methods may also be used as compensatory measures to restore OPERABILITY (Ref. 8).

Options for restoring the CRE boundary to OPERABLE status include changing the licensing basis DBA consequence analysis, repairing the CRE boundary, or a combination of these actions. Depending upon the nature of the problem and the corrective action, a full scope in leakage test may not be necessary to establish that the CRE boundary has been restored to OPERABLE status.

SR 3.7.9.5 This SR verifies the CRVS can supply the CRE with outside air to meet the design requirement. The design flowrate of each booster fan is 1350 cfm +/-10% (i.e., 1215 cfm to 1485 cfm). This lower limit ensures each train is capable of supplying enough air to meet the minimum total system flowrate requirement of 1215 cfm. The 1485 cfm upper limit is required to meet the carbon filter residence time limit of each individual booster fan train (Ref. 5). The frequency is consistent with industry practice and other filtration SRs, and will be managed in accordance with the Surveillance Frequency Control Program.

1. UFSAR, Section 9.4.

2. UFSAR, Chapter 15.

3. UFSAR, Section 6.4.2.5

4. 10 CFR 50.36.

5. Regulatory Guide 1.52, Rev. 4.

6. Regulatory Guide 1.196, Rev. 1.

7. NEI 99-03, "Control Room Habitability Assessment,"June 2001.

8. Letter from Eric J. Leeds (NRC) to James W. Davis (NEI) dated January 30, 2004, "NEI Draft White Paper, Use of Generic Letter 91-18 Process and Alternative Source Terms in the Context of Control Room Habitability."

OCONEE UNITS 1, 2, & 3 B 3.7.9-7 Rev. 001 I

v t e Letter Sequence Request
CAC:MF9555, Control Room Habitability, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B (Approved, Closed)
Initiation Request Acceptance, Acceptance Supplement, Supplement Administration Questions 7 September 2017 Answers Results Approval Other: ML17202U731, ML17268A092
MONTHYEAR2017-05-25 [Table View]

ML17095A530

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