Text

Amendment to License, Technical Specification Pages Re 1.7% Power Uprate
	ML023110285
Person / Time
Site:	Robinson
Issue date:	11/05/2002
From:	Subbaratnam R; NRC/NRR/DLPM/LPD2
To:	;
References
	Download: ML023110285 (12)
	v • d • e

3. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified below:

A. Maximum Power Level The licensee is authorized to operate the facility at a steady state reactor core power level not in excess of 2339 megawatts thermal.

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 196 , are hereby incorporated in the license. Carolina Power &

Light Company shall operate the facility in accordance with the Technical Specifications.

(1) For Surveillance Requirements (SRs) that are new in Amendment 176 to Final Operating License DPR-23, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 176. For SRs that existed prior to Amendment 176, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 176.

C. Reports CP&L shall make certain reports in accordance with the requirements of the Technical Specifications.

D. Records CP&L shall keep facility operating records in accordance with the requirements of the Technical Specifications.

Amendment No. 1--f*, 196

- 4d -

4. Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No.

1 96, are hereby incorporated into this license. Carolina Power & Light Company shall operate the facility in accordance with the Additional Conditions.

5. This amended license is effective as of the date of issuance and shall expire at midnight July 31, 2010.

FOR THE ATOMIC ENERGY COMMISSION Original Signed by Peter A. Morris Peter A. Morris, Director Division of Reactor Licensing

Attachment:

Appendix A - Technical Specifications Date of Issuance: JUL 31 1970 Amendment No. 1.6, 196

Definitions 1.1 1.1 Definitions MODE specified in Table 1.1-1 with fuel in the reactor (continued) vessel.

OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train.

component, or device to perform its specified safety function(s) are a so capable of performing their related support function(s).

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.

These tests are:

a. Described in Chapter 14, Initial Test Program of the Updated Final Safety Analysis Report (UFSAR):

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

QUADRANT POWER TILT QPTR shall be the ratio of the maximum upper RATIO (QPTR) excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 2339 MWt.

SDM shall be the instantaneous amount of I

SHUTDOWN MARGIN (SDM) reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

(continued)

HBRSEP Unit No. 2 1.1-4 Amendment No. t7'6, 196

SLs 2.0 680

"". 2 DO NOT OPERATE 0I IN THIS AREA 0

_,J

-I 600.

&40 540 00 Q HIGH FLUX TRIP 520- 00 RATED POWER- .

0 20 4060 80 100 120 PERCENT OF RATED THERMAL POWER NOTE: BASED ON A MINIMUM RCS FLOW OF 97.3 x 106 libm/hr Figure 2.1.1-1 (page 1 of 1)

Reactor Core Safety Limits HBRSEP Unit No. 2 2.0-2 Amendment No. 1-n, 196

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 7)

Reactor Protection System Instrumentation Nntp 1. nvprtPmnPrnfijrP AT The Overtemperature AT Function Allowable Value shall not exceed the fol l owing Nominal Trip Setpoint by more than 2.96% of AT span.

A AT 0 { Ki-K2 (1 +(

+'S) T) + K3 (P - Y)-f( A I}

Where: ATo is the indicated AT at RTP, OF.

s is the Laplace transform operator, sec'.

T is the measured RCS average temperature, OF.

T' is the reference Tavn at RTP,

575.9°F.

P is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure,

2235 psig Ki g 1.1265 K2 = 0.01228/'F K3 = 0.00089/psig ii > 20.08 sec T2 g 3.08 sec f(AI) = 2.4{(qb - qt) 171 when qt - qb < - 17% RTP 0% of RTP when -17% RTP q - qb

12% RTP 2.4{(qt qb) - 12} when qt - qb > 12% RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total T*ERMAL POWER in percent RTP.

HBRSEP Unit No. 2 3.3-18 Amendment No. -76, 196

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 7 of 7)

Reactor Protection System Instrumentation Note 2' -Ovrpnwpr AT The Overpower AT Function Allowable Value shall not exceed the following Nominal Trip Setpoint by more than 3.17% of AT span.

ATsetpoonr *_ATo K 4 -K 5 [ 3

+-T s]T-K6(T- )-f(AI)

Where: ATo is the indicated AT at RTP, OF.

s is the Laplace transform operator, sec T is the measured RCS average temperature, °F.

T' is the reference Tavg at RTP,

575.9°F.

K4 < 1.06 Ks5 > 0.02/°F for increasing Tavg K6 > 0.00277/°F when T > T' 0/*F for decreasing Tavg 0/°F when T

T' T3 k 9 sec f(AI) = as defined in Note 1 for Overtemperature AT 3.3-19 Amendment No. i-76, 196 HBRSEP Unit No. 2

ESFAS INSTRUMENTATION 3.3.2 Table 3.3.2-1 (page 1 of 4)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR NOMINAL OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

1. Safety Injection

a. Manual Initiation 1,2,3.4 2 B SR 3.3.2.6 NA NA

b. Automatic Actuation 1.2.3.4 2 trains C SR 3.3.2.2 NA NA Logic and Actuation SR 3.3.2.3 Relays SR 3.3.2.5

c. Containment 1.2,3,4 3 E SR 3.3.2.1 :_4.45 psig 4 psig Pressure - High SR 3.3.2.4 SR 3.3.2.7

d. Pressurizer 1,2.3(a) 3 D SR 3.3.2.1 Ž 1709.89 1715 psig Pressure - Low SR 3.3.2.4 psig SR 3.3.2.7

e. Steam Line High 1,2.3(a) 3 per D SR 3.3.2.1 z 83.76 100 psig Differential steam SR 3.3.2.4 psig Pressure Between line SR 3.3.2.7 Steam Header and <162 Steam Lines psg

f. High Steam Flow in 1.2 .3 2 per D SR 3.3.2.1 (c) (d)

Two Steam Lines steam SR 3.3.2.4 line SR 3.3.2.7 Coincident with Tavg 1,2 M.3 (b) 1 per D SR 3.3.2.1 ; 541.50 5430F

- Low loop SR 3.3.2.4 OF SR 3.3.2.7 b), 3 (b) 2 per D SR 3.3.2.1 (c) (d)

g. High Steam Flow in 1, 2 Two Steam Lines steam SR 3.3.2.4 line SR 3.3.2.7 Mb (b) 614 psig Coincident with 1,2 .3 1 per D SR 3.3.2.1 2 605.05 Steam Line Pressure loop SR 3.3.2.4 psig

- Low SR 3.3.2.7 (continued)

(1) A channel is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

(a) Above the Pressurizer Pressure interlock.

(b) Above the Tavg-Low interlock.

and (c) Less than or equal to a function defined as Ap corresponding to 41.58% full steam flow below 20% load, AP increasing linearly from 41.58% full steam flow at 20% load to 110.5% full steam flow at 100% load, and AP corresponding to 11D.5% full steam flow above 100% load.

(d) A function defined as AP corresponding to 37.25% full steam flow between 0% and 20% load and then a AP increasing linearly from 37.25% steam flow at 20% load to 109% full steam flow at 10% load.

-PPHý,7P I1nit lIL*i\*Li Nn Vii I I. lIv° 9 3.3-25 Amendment No. 176, 196

RCS P/T Limits 3.4.3 MAHNS PROPERMSE MAE C~aoavhn mots" : Lmw Ckousftwind Wdd ma~nfi for heat*

Compe Conten 0.2M wt.X rates G Wii/H for the N" Contwd M1.06; eMWt. pwo up to23.G6EFPY.

swv RrND~T" : -- WF kxdud. +1OTF and - 80 PS

RTMXMrv 23.96 EFPY : 114 T- 207AY3F rowaro e for fwtwumwnIttIon 1/4 T. 137.16'V error.

3=0O 2500 o 12000 LO* Tog a

Heatlip Rata UP, To WFIHr 1 :11 1 H.:

I fit IA] jil"11 110 Uffa komebauc tnt

'Wmorchn (327M for tto w od to 23.96 EM 50 100 150 200 250 300 350 400 480 500 INDICATED TEMPERATURE CF)

Figure 3.4.3-1 Reactor Coolant System Heatup Limits Applicable Up to 23.96 EFPY HBRSEP Unit No. 2 3.4-7 Amendment No. 17, 196

"I C,)

m INDICATED PRESSURE (PSIG)

I c:5

'iI C+

0 I

C+

C-I tu g 8t ------------------

i iiii I

0

5 cI)

"W0 "0( - - - - -

-5 - - - - - - - - -

mo . . . . . . . . . . . . .

I co .. . . . . -- - - - - - - - - - - . .

CJ m m III (D

C+

(-9.

a,° o-9

-- - - I I I I I I I

. . . . . . . . . . I1ut1 ill' C) c-fl

-v

-1 0 C.A 4:s.-2.

(-9 CA) (n

-,.,.i 1.0

MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)

LCO 3.7.1 The MSSVs shall be OPERABLE as specified in Table 3.7.1-1 and Table 3.7.1-2.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONs

----- NOTE ....................................

Separate Condition entry is allowed for each MSSV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more steam A.1 Reduce THERMAL POWER to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months generators with one < 50 % RTP.

MSSV inoperable and the Moderator Temperature Coefficient (MTC) zero or negative at all power levels.

(continued)

HBRSEP Unit No. 2 3.7-1 Amendment No. -7176,196

MFIVs, MFRVs, and Bypass Valves 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more bypass C.1 Close or isolate bypass 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months valves inoperable, valve.

AND C.2 Verify bypass valve is Once per 7 days closed or isolated.

D Two valves in the D.1 Isolate affected flow 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months same flow path path.

inoperable.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND E.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each MFRV and In accordance bypass valve is

20 seconds on an actual or simulated actuation signal.

with the Inservice I Testing Program SR 3.7.3.2 Verify the closure time of each MFIV is In accordance

50 seconds on an actual or simulated with the actuation signal. Inservice Testing Program HBRSEP Unit No. 2 3.7-9 Amendment No. t76,+-&?, 196

APPENDIX B ADDITIONAL CONDITIONS OPERATING LICENSE NO. DPR-23 Carolina Power & Light Company (the term licensee in Appendix B refers to Carolina Power &

Light Company) shall comply with the following conditions on the schedules noted below:

Amendment Number Additional Conditions Implementation Date 176 The licensee is authorized to relocate This amendment is certain requirements included in effective immediately Appendix A and the former Appendix B to and shall be implemented licensee-controlled documents. within 90 days of the date Implementation of this amendment shall of this amendment.

include the relocation of these requirements to the appropriate documents, as described in the licensee's letters dated September 10, 1997, and October 13,1997, evaluated in the NRC staff's Safety Evaluation enclosed with this amendment.

196 Operation of H. B. Robinson Steam This amendment is Electric Plant, Unit No. 2, is limited to effective immediately 504 effective full-power days. This and shall be implemented additional condition shall remain in within 30 days of the date effect until approval of a license of this amendment amendment that removes this limitation.

Amendment No. 176, 196

ML023110285

Text

Attachment:

Navigation menu

Search