ML081540279

Tech Spec Pages for Amendment 218 Regarding Administrative Changes to the Operating License and Technical Specifications

ML081540279
Person / Time
Site:	Robinson
Issue date:	06/19/2008
From:	NRC/NRR/ADRO/DORL/LPLII-2
To:
Vaaler, Marlayna, NRR/DORL 415-3178
Shared Package
ML081540203	List: ML081540220 ML081540279
References
TAC MD7351
Download: ML081540279 (10)

Text

C. Reports Carolina Power & Light Company shall make certain reports in-accordance with the requirements of the Technical Specifications.

D. Records Carolina Power & Light Company shall keep facility operating records in accordance with the requirements of the Technical Specifications.

E. Fire Protection Program Carolina Power & Company shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Fire Protection Safety Evaluation Report dated February 28, 1978, and supplements thereto. Carolina Power & Light Company may make changes to the approved Fire Protection Program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

F. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "H. B.

Robinson Steam Electric Plant Security, Training and Qualification, and Safeguards ContingencyPlan, Revision 0" submitted-by-letter-dated-October-1. - -

2004, as supplemented by letter dated October 20, 2004.

G. The following programs shall be implemented and maintained by the licensee:

(1) DELETED Renewed Facility Operating License No. DPR-23 Amendment No. 218

(2) DELETED (3) A progtrai to determine the airborne iodine concentration in vital areas under accident conditions. This program shall include: training of personnel, procedures for monitoring, and provisions for maintenance of sampling and analysis equipment.

(4) DELETED H. DELETED

1. DELETED J. DELETED K. Updated Final Safety Analysis Report The Carolina Power & Light Company Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54.21(d), describes certain future activities to be completed prior to the period of extended operation. The Carolina Power & Light Company shall complete these activities no later than July 31, 2010, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement, as revised, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (eX4) following issuance of this renewed license. Until that update is complete, the Carolina Power & Light Company may make changes to the programs and activities described in the supplement without prior Commission approval, provided that the Carolina Power & Light Company evaluates each such-change-pursuant-to the criteria set-forth-in ...

10 CFR 50.59 and otherwise complies with the requirements in that section.

Renewed Facility Operating License No. DPR-23 Amendment No. 218

Definitions 1.1 1.1 Definitions SHUTDOWN MARGIN a. All rod cluster control assemblies (RCCAs) are (cont-i nued) fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn. With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDM; and

b. In MODES 1 and 2, the fuel and moderator temperatures are changed to 547°F. I SLAVE RELAY TEST A SLAVE RELAY TEST shall consist of energizing each slave relay and verifying the OPERABILITY of each slave relay. The SLAVE RELAY TEST shall include, as a minimum, a continuity check of associated testable actuation devices.

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER THERMAL POWER shall be the'total reactor core heat transfer rate to the reactor coolant.

-TRI P--ACTUATING-DEVICE- A-TADOTh§a1 c-F6-si st -of- op-ratin-the -trip OPERATIONAL TEST actuating device and verifying the OPERABILITY of (TADOT) required alarm, interlock, display, and trip functions. The TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the required accuracy.

HBRSEP Unit No. 2 1.1-5 Amendment No. 218

Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Analog Rod Position Indication (ARPI) System and the Demand Position Indication System shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

---

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

Separate Condition entry is allowed for each inoperable rod position indicator per group and each demand position indicator per bank.

CONDITION REQUIRED ACTION COMPLETION TIME A. One ARPI per group inoperable for one or A.1 Verify the position Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> more groups. of the rods with inoperable position indicators by using movable incore detectors.

OR

- A---

-A.-2 - Reduce-THERMAL--POWER- - &8-hours to < 50% RTP.

B. One or more rods with B.1 Verify the position 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable position of the rods with indicators have been inoperable position moved in excess of indicators by using 24 steps in one movable incore direction since the detectors.

,last determination of the rod's position. OR (continued)

HBRSEP Unit No. 2 ,3,.1- 15 Amendment No.218

RCS P/T Limits 3.4.3 MATERIALS PROPERTIES BASE Curves applicable for heatup rates up to 60 *F/Hr for CONTROLLING MATERIAL: Upper Shell Plate W10201-1 service period up to 35 EFPY.

Limiting ART Values at 35 EFPY: 1/4T, 167°F Heatup Curves include +10°F and -60 psig allowance 3/4T, 147°F for instrumentation error.

97Rn . ... .. .

2500 7

2250-

-1 Leak Test Lim it -- t -T - -, -, - , ,,,-  !,--

2000-1750-Unacceptable Operation

.i Acceptable Operation 1500 Heatup*4/~ Rate to ~ ~1 *:: -x11-...

U) 60*F/Hr F U)

.2 I tI+/-7I j

0 50 100 150 200 250 300 350 400 450 500 550 Indicated Temperature (*F)

Figure 3.4.3-1 Reactor Coolant System Heatup Limits Applicable Up to 35 EFPY HBRSEP Unit No. 2 3.4-7EPU itN. "e..n...1 Amendment No-218

RCS P/T Limits 3.4.3 MATERIALS PROPERTY BASE Curves applicable for cooldown rates up to CONTROLLING MATERIAL: Upper Shell Plate W1 0201-1 IO 0 FIHr for the service period up to 35 EFPY.

and Girth Weld 10-273 Curves include +10OF and -60 PSIG allowance Limiting ART Values at 35 EFPY: 1/4T, 167°F and 242°F for instrument error.

314T, 147°F and 172°F 2750 2500 2250 Uncepal Operation i'*-i 2000 1750 a-U) i~~~~~~4-1 ArI'IiIl iI:

[I 1500

i~t,i i ' Pi' i ~ i ' I cceptable Operation

.. .. ' 0*F' Hr 1250 10 , r . . ,j - [ iI

' ' F 4-1000 PII S  : r l I i  ; I .i '  ! i  : I 750 r* '~

and 2'

.--- ,i ~ ~i.. ~~~~~~~-

i:: iiH ] i! ii] i' 500 610} " =i. .

250 1 ,' ,00 i,  ! i i

'  : i ! i ]  :

• I I i i I * ' iT* '

0 0 50 100 150 200 250 300 350 400 450 500 550 Indicated Temperature (°F)

Figure 3.4.3-2 Reactor Coolant System Cooldown Limits Applicable Up to 35 EFPY HBRSEP Unit No. 2 3.4-8 Amendment No-2.18

Pressurizer 3.4.9-3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with:

a. Pressurizer water level - 63.3% in MODE 1;

b. Pressurizer water level

• 92% in MODES 2 and 3; and

c. Pressurizer heaters.OPERABLE with a capacity of > 125 kW and capable of being powered from an emergency power supply.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water A.1 Be in MODE 3 with 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> level not within reactor trip breakers limit. open.

AND A.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B. Capacity of required B.1 Restore required 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> pressurizer heaters pressurizer heaters to OPERABLE status.

< 125 kW.

I C. Required pressurizer C.1 Restore capability to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

heaters not capable of power the required being powered from an pressurizer heaters emergency power from an emergency supply. power supply.,

(continued)

HBRSEP Unit No. 2 3.4-21 Amendment No.218

AFW System 3-.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time for Condition A AND or B not met.

C.2 Be in MODE 4. 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> D. Steam driven AFW pump D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or flow path inoperable in MODE 1, AND 2, or 3.

D.2 Be in MODE 4. 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> AND One motor driven AFW pump or flow path inoperable in MODE 1, 2, or 3.

E. Four AFW flow paths E.1 --------- NOTE --------

inoperable in MODE 1. LCO 3.0.3 and all 2, or 3. other LCO Required Actions requiring OR MODE changes are suspended until Three AFW pumps one AFW pump and flow inoperable in MODE 1, path are restored to 2, or 3. OPERABLE status.

Initiate action to Immediately restore one AFW pump and flow path to OPERABLE status.

F. Required AFW pump and F.1 Initiate action to Immediately flow path inoperable restore AFW pump and in MODE 4. flow path to OPERABLE status.

HBRSEP Unit No. 2 3.7-11 Amendment No.218

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testing Program (VFTP) (continued)

d. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, and the charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below.

ESF Filter System Delta P Flowrate Control Room <3.4 inches 3300 - 4150 ACFM Emergency water gauge Spent Fuel <6 inches 12300 CFM +10%

Building water gauge Containment. <6 inches 35000 CFM +10%

Purge water gauge

e. Demonstrate thatothe heaters for the Spent Fuel Building ventilation filter system maintains the filter inlet air at

• 70% relative humidity when tested in accordance with ASME N510-1975.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

5.5.12 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Waste Gas Decay Tanks, the quantity of radioactivity contained in The Waste Gas Decay Tanks and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The program shall include:

a. The limits for concentration of oxygen in the Waste Gas I Decay Tanks and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate (continued)

A HBRSEP Unit No. 2 5.0-18 Amendment. No. 21

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

19. EMF-92-081(A), "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors," approved version as specified in the COLR.

20. EMF-92-153(P)(A), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel,"

approved version as specified in the COLR.

21. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," approved version as specified in the COLR.

22. EMF-96-029(P)(A), "Reactor Analysis System for PWRs,"

approved version as specified in the COLR.

23. EMF-92-116, "Generic Mechanical Design Criteria for PWR Fuel Designs," approved version as specified in the COLR.

24. EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," approved version as specified in the COLR.

25. EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," approved version as specified in the COLR.

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 Systems (ECCS) limits, nuclear limits such as SDM, 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) Instrumentation Report When a report is required by Condition B or G of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

(continued)

HBRSEP Unit No. 2 5.0-27 Amendment No.218