Text

Amend 142 to License NPF-12,changing VCSNS TSs to Permit Use of Beacon Core Power Distribution Monitoring & Support Sys with Moveable in-core Detectors to Augment VCSNS Flux Mapping Sys When Power Greater than 25% Rated Thermal Power
	ML20205P505
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Site:	Summer
Issue date:	04/09/1999
From:	Emch R; NRC (Affiliation Not Assigned)
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	NUDOCS 9904200196
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88"ICuq 4

UNITED STATES p "Y.

j

,j NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D.C. 20555 0001

'+9.....,o SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.142 License No. NPF-12 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by South Carolina Elec.tric & Gas Company (the licensee), dated September 18,1998, as supplemented by letter dated February 5,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the r';blic; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:

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i 9904200196 990409 PDR ADOCK 05000395 P

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(2)

Technical Soecifications and Environmental Protection Plan The Technical Specifications contained ia Appendix A, as revised through Amendment No. 142, and the Environmental Protection Plan contained in l

Appendix B, are hereby incorporated in the license. South Carolina Electric &

Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This amendment is effective as cf its date of issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Richard L. Emch, Chief, Section 1 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation Attachmer.t: Changes to the Technical Specifications Date of issuance: April 9,1999

(

I I

s ATTACHMENT TO LICENSE AMENDMENT NO.142 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginallines.

Remove Paoes insert Paaes Index page IV Index page IV 3/4 1-15 3/4 1-15 3/4 2-4 3/4 2-4 3/4 2-5 3/4 2-5 3/4 2-6 3/4 2-6 3/4 2-6a 3/4 2-6a 3/4 2-6b 3/4 2-6b 3/4 2-6c 3/4 2-6c 3/4 2-8 3/4 2-8 3/4 2-9 3/4 2-9 3/4 2-14 3/4 2-14 3/4 3-46 3/4 3-46 3/4 3-73 3/4 3-74 3/4 3-75 B3/4 2 4 B3/4 2-4 B3/4 2-5 B3/4 2-5 B3/4 3-4 B3/4 3-4 B3/4 3-5 16 6-16 6-16a 6-16a i

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i l

1 a

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l

SECTION PAGE l

3/4.2 POWER DISTRIBUTION LIMITS l

3/4.2.1 AXIAL FLUX DIFFERENCE

. 3/4 2-1 1

3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR.

.-.... 3/4 2-4 l

3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR....

.3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATIO...

. 3/4 2-12 3/4.2.5 DNB PARAMETERS...

.3/4 2-15 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION............... 3/4 31 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUM ENTATION.....................

. 3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring..........

.. 3/4 3-41 Movable incore Detectors

.... 3/4 3-46 DELETED..

. 3/4 3-47 Meteorological Instrumentation

..... 3/4 3-50 Remote Shutdown Instrumentation................

.. 3/4 3-53 Accident Monitoring Instrumentation.....

..... 3/4 3-56 Explosive Gas Monitoring Instrumentation.....

...... 3/4 3-67 Loose-Put Detection Instrumentation...

.. 3/4 3-72 l

Power Distribution Monitoring System...

... 3/4 3-73 l

l SUMMER - UNIT 1 IV Amendment No. 79,104,122,142 i

I REACTIVITY CONTROL SYSTEMS LIMITING CJ.0ITION FOR OPERATION (Continued)

I

\\

a)

A reevaluation of each accident analysia of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these coriditions.

b)

The SHUTDOWN MARGIN requiremerit of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c)

A core power distribution measurement is obtained and Fo(z) and Ffi, are verified to be within their limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and d)

The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the next hour and within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.

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SURVEILLANCE REQUIREMENTS

_ A:

4.1.3.1.1 The position of each Mllength rod shall be determined to be within the group i

demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Hod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2

-Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.

SUMMER - UNIT 1 3/4 1-15 Amendment No. 142

POWER DISTRIBUTION LIMITS

@/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - Fo{zl l

LIMITING CONDITION FOR OPERATION 3.2.2 Fo(z) shall be limited by the following relationships:

f TP' Fo(z)s

[K(z)] for P > 0.5 P

F (z)s F"dP [K(z)] for P s 0.5 o

. E5 where Ff the Fo limit at RATED THERMAL POWER (RTP) specified

=

in the CORE OPERATING LIMITS REPORT (COLR),

p THERMAL POWER RATED THERMAL POWER, and K(z) the normalized Fo(z) for a given core height specified in the COLR.

APPLICABILITY:

MODE 1.

ACTION:

With Fo(z) exceeding its limit:

a.

Reduce THERMAL POWER at least 1% for each 1% Fo(z) exceeds the limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION may proceed provided the Overpower delta T Trip Setpoints have been reduced at least 1% for each L

1% Fo(z) exceeds the limit.

b.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER above the reduced limit required by a, above; THERMAL POWER may then be increased provided Fo(z) is demonstrated through core i

power distribution measurement to be within its limit.

I SUMMER - UNIT 1 3/4 2-4 Amendment No. SS,75,88,142 i

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1 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.2 For RAOC operation, Fo(z) shall be evaluated to determine if Fo(z) is within its limit by:

' a.

Using the movable incore detectors to obtain a power distribution map 1.

When THERMAL POWER is s 25%, but > 5% of RATED THERMAL POWER, or j

2.

When the Power Distribution Monitoring System (PDMS) is inoperable:

and increasing the Measured Fo(z) by the applicable manufacturing and measurement uncertainties as specified in the COLR.

b.

Using the PDMS when THERMAL POWER is > 25% of RATED THERMAL POWER, and increasing the measured Fo(z) by the applicable manufacturing and measurement uncertainties as specified in the COLR.

i c.

Satisfying the following relationship:

I l

Fs(z)s

)frP>0.5 P

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I Fj(z)s for P < 0.5 W(z) x 0.5 where F5(z) is the measured Fo(z) increased by the applicable allowances for manufacturing tolerances and measurement uncertainty as specified in the COLR, Fj" is the Fo limit, K(z) is the normalized Fo(z) as a function of core height, P is the relative THERMAL POWER, and W(z) is the cycle dependent function that accounts for power dstribution transients encountered during normal operation. Fj", K(z) and W(z) are specified in the CORE OPERATING LIMITS REPORT as per Specification 6.9.1.11.

d.

Measuring F5(z) according to the following schedule:

1.

Upon achieving equilibrium conditions after exceeding by 10% or more l

of RATED THERMAL POWER, the THERMAL POWER at which Fo(z) was last determined,

or 2.

At least once per 31 Effective Full Power Days, whichever occurs first.

During power escalation at the beginning of each cycle, power level may be increased until a power level for extended operation has been achieved and the core power distribution measurement is obtained.

SUMMER - UNIT 1 3/4 2-5 Am(ndment No. 887 142 l

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P_OWER DISTRIBUTION LIMITS SURVElLLANCE REQUIREMENTS (Continued) e.

With the maximum value of

~

FU(z)

K(z) over the core height (z) increasing since the previous determination of FU(z) either of the following actions shall be taken-(1)

F5(z) shall be increased by 2% over that specified in Specification 4.2.2.2c. or i

(2)

Fs(z) shall be measured at least once per 7 Effective Full Power Days until two successive power distribution measurements indicate that the maximum value of F5(z)

K(z) i over the core height (z) is not increasing.

f.

With the relationships specified in Specification 4.2.2.2c. above not being satisfied:

1 1

(1)

Calculate the maximum percent over the core height (z) that Fo(z) exceeds its limit by the following expression:

-1. x 100 for P 2 0.5

< p",

x K(z)

. p

-1, x 100 for P < 0.5 Ff

0.5 l

SUMMER - UNIT 1 3/4 2-6 Amendment No. M 142

rr POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) i (2)

One of the following actions shall be taken:

(a)

Within 15 minutes, control the AFD to within new AFD limits which are determined by reducing the applicable AFD limits by 1% AFD for each percent Fo(z) exceeds its limits as determined in Specification 4.2.2.2f.1). Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , reset the AFD alarm I

setpoints to these modified limits, or l

l (b)

Comply with the requirements of Specification 3.2.2 for Fo(z) l exceeding its limit by the percent calculated above, or (c)

Verify that the requirements of Specification 4.2.2.3 for Base Load operation are satisfied and enter Base Load operation.

g.

The limits specified in Specifications 4.2.2.2c.,4.2.2.2e., and 4.2.2.2f. above are not applicable in the following core plane regions:

r 1.

Lower core region from 0 to 15%, inclusive.

2.

Upper core region from 85 to 100%, inclusive.

4.2.2.3 Base Load operation is permitted at powers above APL" if the following conditions are satisfied:

a.

Prior to entering Base Load operation, maintain THERMAL POWER above APL" and less than or equal to that allowed by Specification 4.2.2.2 for at least the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Maintain Base Load operation surveillance (AFD within i

l applicable target band about the target flux difference) during this time period.

Base Load operation is then permitted providing THERMAL POWER is maintained between APL" and APL"or between APL" and 100% (whichever is most limiting)is defined as the minimum value of:and Fo surveillan 4.2.2.4. APL APL" = 5(z) x W(z)a x 100%

F

'over the core height (z) where: Fj(z) is the measured Fo(z) increased by the applicable allowances for manufacturing tolerances and measurement uncertainty as,specified in the COLR. The Fo limit is Fj". W(z)a is the cycle dependent functio 1 that accounts for limited power distribution transient encountered during base load operation. Fj", K(z), and W(z)a are specified in the CORE OPERATING LIMITS REPORT as per Specification 6.9.1.11.

SUMMER - UNIT 1 3/4 24a Amendment No. 76r88,142

F l

c POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) b.

Durin APL"g Base Load operation, if the THERMAL POWER is decreased below then the conditions of 4.2.2.3.a shall be satisfied before re-entering Base Load operation.

4.2.2.4 During Base Load Operation Fo(z) shall be evaluated to determine if Fo(z) is within its limit by:

Using the movable incore detectors to obtain a power distribution map at any a.

THERMAL POWER above APL" when the Power Distribution Monitoring System (PDMS) is inoperable; and increasing the measured Fo(z) by the applicable manufacturing and measurement uncertainties as specified in the COLR.

b.

Using the PDMS at any THERMAL POWER greater than APLND; and increasing the measured Fo(z) by the applicable manufacturing and measurement uncertainties as specified in the COLR.

c.

Satisfying the following relationship:

Fs(z)s: P x W (z)st for P > APL" where: Fj(z) is the measured Fo(z) increased by the applicable allowances for manufacturint and measurement uncertainties as specified in the COLR. The Fo limit is Fj" P is the relative THERMAL POWER. W(z)st s the cycle i

deperdent function that accounts for limited power distribution transients encountered during normal operation. Fj" K(z) and W(z)st are specified in the CORE OPERATING LIMITS REPORT as per Specification 6.9.1.11.

d.

Measuring Fs(z) in conjunction with target flux difference determination according to the following schedule:

1.

Prior to entering BASE LOAD operation after satisfying Section 4.2.2.3 unless a core power distribution measurement has been obtained in the previous 31 EFPD with the relative thermal power having been maintained above APL" for the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to.neasurement, and 2.

At least once per 31 Effective Full Power Days.

l e.

With the maximum value of F5(z)

K(z)

SUMMER - UNIT 1 3/4 2-6b Amendment No. 75r8% 142

p.

l POWER DISTRIBUTION LIMITS I

j SURVEILLANCE REQUIREMENTS (Continued) over the core height (z) increasing since the previous determination of Fs(z) either of l

the following actions shall be taken:

1.

F5(z) shall be increased by 2 percent over that specified in 4.2.2.4.c, or 2.

Fs(z) shall be measured at least once per 7 Effective Full Power Days unti! 2 successive power distribution measurements indicate that the maximum value of i

Fs(z)

K(z) over the core height (z) is not increasing.

f.

With the relationship specified in 4.2.2.4.c above not being satisfied, either of the following actions shall be taken:

1.

Place core in an equilibrium condition where the limit in 4.2.2.2.c is satisfied, and remeasure Fs(z), or 2.

Comply with the requirements of Specification 3.2.2 for Fo(z) exceeding its limit by the maximum percent calculated over the core height (z) with the following

{

express a F#(z)x W(z)m. -1, x 100 for P lt APL"o xK(z)

l. P g.

The limits specified in 4.2.2.4.c,4.2.2.4.e, and 4.2.2.4.f above are not apphcable in the following core plane regions:

1.

Lower core region 0 to 15 percent, inclusive.

2.

Uoper core region 85 to 100 percent, inclusive.

4.2.2.5 ~ When Fo(z)is measured for reasons other than meetmg the requirements of Spec hcation 4.2.2.2 i

en overall measured Fo(z) shall be obtained:

a.

from a power distribution map 1.

when THERMAL POWER is s 25%, but > 5% of RATED THERMAL POWER, or 2.

when the Power Distnbution Monitoring System (PDMS) is inoperable; and increasmg the measured Fo(z) by the applicable manufacturing and measurement i

uncertanties as specshed in the COLR.

b.

from the PDMS when THERMAL POWER is > 25% of RATED THERMAL POWER; and increasing the measured Fo(z) by the applicable manufacturing and measurement uncertainties as specified in the COLR.

SUMMER UNIT 1 3/4 2-6c Amendment No. ;%.88r 142

I r*

POWER DISTRIBUTION LIMITS 3/4 2 3 RCS FLOW RATE AND NUCLEA.R ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION 3.2.3 The combination of indicated Reactor Coolant System (RCS) total flow rate and R shall be maintained within the region of allowable operation as specified in the CORE OPERATING LIMITS REPORT (COLR) figure entitled RCS Total Flow Rate Versus R For Three Loop Operation.

Where:

a.

R

=

FETP{1.0 + PFm(1.0- P)]

b.

P

=

RATED THERMAL POWER '

F1 Measuredvaluesof F5 obtainedby c.

1.

Using the movable incore detectors to obtain a power distribution map when THERMAL POWER is s 25% but > 5% of RATED THERMAL POWER, or when PDMS is inoperable, and 2.

Using the PDMS when THERMAL POWER is > 25% of RATED THERMAL POWER.

The measured values of F1 shall be increased by the applicable F1 measurement uncertainties as specified in the COLR, and used to calculate R since the RCS Total Flow Rate Versus R figure in the COLR includes measurement uncertainties of 2.1% (includes 0.1% for feedwater venturi fouling) for flow, d.

F$"

=

The F$ limit at RATED THERMAL POWER specified in the COLR, and j

e.

PFm The Power Factor Multiplier specified in the COLR.

APPLICABILITY:

MODE 1.

ACTION:

With the combination of RCS total flow rate and R outside the region of acceptable operation specified in the COLR:

a.

Wrthin 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

1.

Restore the combination of RCS total flow rate and R to within the above limits, or 2.

Reduce THERMAL POWER to less than 50. M RATED THERMAL POWER and reduce the Power Range Neutron Flux - High up setpoint to less than or equal to 55%

of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

I' b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initially being outside the above limits, verify through a core power distribution measurement and RCS total flow rate comparison that the mmbination of R and l

f RCS total flow rate are restored to within the above limits, or reduce THERMAL POWER to j

less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SUMMER - UNIT 1 3/42-8 Amendment No.

45. T, 75, Mr 448, 142 i

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i POWER DISTRIBUTION LIMITS l

LIMITING CONDITION FOR OPERATION l

ACTION: (Continued)

Identify and correct the cause of the out-of-limit condtion prior to increasing c.

THERMAL POWER above the reduced THERMAL POWER limit required by

{

ACTION items a.2. and/or b. above; subsequent POWER OPERATION may l

proceed provided that the combination of R and indicated RCS total flow rate are demonstrated, through a core power distribution measurement and RCS.

l total flow rate comparison, to be within the region of acceptable operation specified in the COLR prior to exceeding the following THERMAL POWER levels:

i 1.

A nominal 50% of RATED THERMAL POWER, j

i 2.

A nominal 75% of RATED THERMAL POWER, and 3.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attaining greater than or equal to 95% of RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specific. don 4.0.4 are not applicable.

4.2.3.2 The combination of indcated RCS total flow rate and R shall be determined to be within the region of acceptable operation specified in the COLR.

a.

Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and b.

At least once per 31 Effective Full Power Days.

f

- 4.2.3.3 The indcated RCS total flow rate shall be verified to be within the region of acceptable operation specified in the COLR at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the most recently l

obtained value of R, obtained per Specification 4.2.3.2, is assumed to exist.

4.2.3.4 The RCS total flow rate indcators shall be subjected to a CHANNEL CAllBRATION at least once per 18 months.

4.2.3.5 The RCS total flow rate shall be determined by heat balance measurement at :t90%

RATED THERMAL POWER at least once per 18 months.

l SUMMER - UNIT 1 3/4 2-9 Amendment No. 45, 75, SS, 419r 142

r POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION g

l l

ACTION: (Continued) 2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL l

POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High l

Trip Setpoints to less than or equal to 55% of RATED THERMAL i-POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least l

once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified at 95% or greater RATED THERMAL POWER.

d.

The provisions of Specification 3.0.4 are nct applicable.

SURVEILLANCE REQUIREMENTS 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by:

a.

Calculating the ratio at least once per 7 days when the alarm is OPERABLE.

b.

Calculating the ratio at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady state operation I

when the alarm is inoperable.

4.2.4.2 The OUADRANT POWER TILT RATIO shall be det. ermined to be within the limit when above 75 percent of RATED THERMAL POWER with one Power Range Channel inoperable by using the movable incore detectors to confirm that the normalized symmetric power distribution, obtained from 2 sets of 4 symmetric thimble locations or a core power i

distribution measurement, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I i

SUMMER - UNIT 1 3/4 2-14 Amendment No.142

{

l

- INSTRUMENTATION

. MOVABLE INCORE DETECTORS

' LIMITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detection system shall be OPERABLE with:

a.

At least 75% of the detector thimbles, b.

A minimum of 2 detector thimbles per core quadrant, and Sufficient movable detectors, drive, and readout equipment to map these c.

thimbles.

APPLICABILITY:

When the movable incore detection system is used for:

Recalibration of the excore neutron flux detection system, a.

b.

Monitoring the QUADRANT POWER TILT RATIO using a full-core flux map per Specification 4.2.4.2, or c.

Measurement of F1 and Fo(z).

ACTION:

With the movable incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable I

i.

SURVElLLANCE REQUIREMENTS 4.3.3.2 The movable incore detection system shall be demonstrated OPERABLE at least l

once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , by normalizing each detector output when required for:

I Recalibration of the exoore neutron flux detection system, or a.

b.

' Monitoring the QUADRANT POWER TILT RATIO, or c.

Measurement of F1 and Fo(z).

SUMMER - UNIT 1 3/4 3-46 Amendment No.142 L

1 1

s INSTRUMENTATION POWER DISTRIBUTION MONITORING SYSTEM LIMITING CONDITION FOR OPERATION 3.3.3.11 The Power Distribution Monitoring System (PDMS) shall be OPERABLE with:

i A minimum of the following inputs from the plant available for use by the PDMS a.

as defined in Table 3.3-14.

1.

Control Bank Position 2.

Ta i

3.

Reactor Power Level 4.

NIS Power Range Detector Section Signals l

b.

Core Exit Thermocouples (T/C) meeting the criteria:

1.

At least 25% operable T/C with at least 2 T/C per quadrant, and 2.

The T/C pattern has coverage of all interior fuel assemblies (no face along the baffle), within a chess knight's move, radially, from a responding, calibrated T/C, or 3.

At least 25% operable T/C with at least 2 T/C per quadrant, and the installed PDMS calibration was determined within the last 31 Effective -

Full Power Days (EFPD).

4.

The T/C temperatures used by the PDMS are calibrated via cross calibration with the loop temperature measurement RTDs, and using the T/C flow mixing factors determined during installed PDMS calibration.

c.

An installed PDMS calibration satisfying the criteria:

l-1.

.The initial calibration in each operating cycle is determined using i

measurements from at least 75% of the incore movable detector l

thimbles obtained at a THERMAL POWER greater than 25% of RATED THERMAL POWER.

'2.

The calibration is determined using measurements from at least 50% of the incore movable detector thimbles at any time except as specified in 3.3.3.11.c.1, and 3.

The calibration is determined using a minimum of 2 detector thimbles per core quadrant.

i SU'

..R - UNIT 1 3/4 3-73 Amendment No.142 l

m

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5 i

INSTRUMENTATION LIMITING CONDITION FOR OPERATION (Continued)

APPLICABILITY: MODE 1, above 25% RATED THERMAL POWER (RTP) i ACTION:

With any of the operability criteria listed in 3.3.3.11.a. 3.3.3.11.b, or 3.3.3.11.c not met, either correct the deficient operability condition, or declare the PDMS inoperable and use the incore movable detector system, satisfying the OPERABILITY requirements listed in Specification 3.3.3.2, to obtain any required core power distribution measurements. Increase the measured core peaking factors using the values listed in the COLR for the PDMS inoperable condition.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.11.1 The operability criteria listed in 3.3.3.11.a. 3.3.3.11.b and 3.3.3.11.c shall be verified to be satisfied prior to acceptance of the PDMS core power distribution measurement i

results.

4.3.3.11.2 Calibration of the PDMS is required:

a.

at least once every 180 Effective Full Power Days when the minimum number and core coverage criteria as defined in 3.3.3.11.b.1 and 3.3.3.11.b.2 are satisfied, or b.

at least once every 31 Effective Full Power Days when only the minimum number criterion as defined in 3.3.3.11.b.3 is satisfied.

SUMMER - UNIT 1 3/4 3-74 Amendment No.142

I INSTRUMENTATION TABLE 3.3-14 l

l REQUIRED PDMS PLANT INPUT INFORMATION PLANT INPUT INFORMATION AVAILABLE MINIMUM NO.OF APPLICABLE INPUTS VALID INPUTS MODES 1.

Control Bank Position 4

4a jc 2.

Teoid 3

2 1c 3.

Reactor Power Level 3

1 ic b

4.

NIS Power Range Excore Detector 8

6 Ic d

Section Signals TABLE NOTATIONS Determined from either valid Demand Position or the average of the valid individual a.

RCCA position indications for all RCCAs in the Control Bank.

b.

Determined from either the reactor THERMAL POWER derived using a valid secondary calorimetric measurement, the average NIS Power Range Detector Power, or the average RCS Loop AT.

c.

Greater than 25% RTP.

d.

Comprised of an upper and lower detector section signal per Power Range Channel; a minimum of 3 OPERABLE channels required.

SUMMER - UNIT 1 3/4 3-75 Amendment No.142

I o

POWER DISTRIBUTION LIMIT j

BASES HEAT FLUX HOT CHANNEL FACTOR and RCS FLOWRATE and NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued) i j

For measurements obtained using the Power Distribution Monitoring System (PDMS),

the appropnate mKsurement uncertainty is determined using the measurement uncertainty methodology contained in WCAP-12472-P-A. The cycle and plant specific uncertainty calculation information needed to support the PDMS calculation is contained in the COLR.

The PDMS will automatically calculate and apply the correct measurement uncertainty, and apply a 3% allowance for manufacturing tolerance.

l The hot channel factorF5(z) is measured periodcally and increased by a cycle ard height dependent power factor appropriate to either RAOC or Base Load operation, W(z) or j

W(z)st, to provide assurance that the limit on the hot channel factor, Fo(z) is met. W(z) accounts for the effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core. W(z)st accounts for the more restrictive operating limits allowed by Base Load operation which result in less l

severe transient values. The W(z) and W(z)st unctions described above for normal operation f

are specified in the CORE OPERATING LIMITS REPORT (COLR) per Specification 6.9.1.11.

l When RCS flow rate is measured, no addtional allowances are necessary prior to comparison with the limits of the RCS Total Rate Versus R figure in the COLR. Measurement errors of 2.1% for RCS total flow rate, including 0.1% for feedwater venturi fouling, have been allowed for in determining the RCS Total Flow Rate Versus R Figure in the COLR.

For FL measurements obtained from a full core flux map taken with the incore detector flux mapping system, a 4% measurement uncertainty allowance should b. applied to the measured FL value prior to comparison with the limits of the RCS Total Flow Rate Versus R Figure in the COLR. The appropriate measurement uncertainty for F1 measurements obtained using the Power Distribution Monitoring System (PDMS) is determined using the uncertainty methodology described in WCAP-12472-P-A. The cycle and plant specific uncertainty calculation informaticn needed to support the PDMS uncertainty calculation is contained in the COLR. The PDMS will automatically calculate and apply the correct measurement uncertainty to the measured F1 value.

L The 12-hour periodic surveillance of indicated RCS flow is sufficient to detect only flow degradation which would lead to operation outside the acceptable region of operation specified on the RCS Total Flow Rate Versus R figure in the COLR.

l 3/4.2.4 QUADRANT POWER TILT RATIO

' The quadrant power tilt power ratio limit asstres that the radial power distribution satisfies the design values used in th'. power capoility analysis. Radial power distribution mes;um,ments are made during startup issting and periodically during power operation.

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L SUMMER - UNIT 1 B 3/4 2-4 Amendment No 35,45,75, 2, M 142 n

l N

POWER DISTRIBUTION LIMIT

)

l BASES QUADRANT POWER TILT RATIO (Continued)

The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts. A limiting tilt of 1.025 can be tolerated before the margin for uncertainty in Fo is depleted. The limit of 1.02 was selected to provide j

an allowance for the uncertainty associated with the indicated power tilt.

1 The two hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned control rod. In the event such action does not correct the tilt, the margin for uncertainty on Fo is reinstated by reducing the maximum allowed power by 3 percent for each percent of tilt in excess of 1.0.

I For purposes of monitoring OUADRANT POWER TILT RATIO when one excore detector is inoperable, the movable incore detectors or a core power distribution measurement are used to confirm that the normalized symmetric power distribution is consistent with the I

QUADR /NT POWER TILT RATIO. The incore detector monitoring is done with a fullincore flux map or two sets of 4 symmetric thimbles. These locations are C-8, E-5, E-11, H-3, H-13, L-5, L-11, N-8.

3/4.2.5 ' DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytmally demonstrated adequate to maintain a minimum of DNBR in the core at or above the design limit throughout each analyzed transient; Tht, maximum indcated T limit of m

589.2*F and the minimum indcated pressure limit of 2206 psig correspond to analytical limits of 591.4'F and 2185 psig respectively, read from control board indications.

The 12-hour penodo surveillance of tiiese parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation.

i i

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SUMMER - UNIT 1 B 3/4 2-5 Amendment No 45, ", S0,75,

??':), 9 9, 142

INSTRUMENTATION BASES 3/4.3.3.9 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring and controlling the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63 and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.10 LOOSE-PART DETECTION INSTRUMENTATION The OPERABILITY of the loose-part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for th3 Primary System of Light-Water-Cooled Reactors," May 1981.

3/4.3.3.11 POWER DISTRIBUTION MONITORING SYSTEM (PDMS)

The Power Distribution Monitoring System (PDMS) provides core monitoring of the limiting parameters. The PDMS continuous core power distribution measurement methodology begins with the periode generation of a highly accurate 3-D nodal simulation of the current reactor power distribution. The simulated reactor power dstribution is then continuously adjusted by nodal and thermocouple calibration factors derived from an incore power distribution measurement obtained using the incore movable detectors to producu u highly accurate power distribution measurement. The nodal calibration factors are updated at least once every 180 Effective Full Power Days (EFPD). Between calibrations, the fidelity of the measured power distribution is maintained via adjustment to the calibrated power dstribution provided by continuously input plant and core condition information. The plant and core condition data utilized by the PDMS is cross checked using redundant information to provide a robust basis for continued operation. The loop inlet temperature is generated by averaging the respective temperatures from each of the loops, excluding any bad data. The core exit thermocouples provide many readings across the core and by the nature of their usage with the PDMS, smoothing of the measured data and elimination of bad data is performed with the Surface Spline fit. PDMS uses the NIS Power Range excore detectors to provide information on the axial power distribution. Hence, the PDMS averages the data from the four Power Range excore detectors and eliminates any bad excore detector data.

The bases for the operability requirements of the PDMS is to provide assurance of the accuracy and reliability of the core parameters measured and calculated by the PDMS core power distribution monitor function. These requirements fall under four categories:

1.

Assure an adequate number of operable critical sensors.

2.

Assure sufficiently accurate calibration of these sensors.

3.

Assure an adequate calibration data base regarding the number of data sets.

4.

Assure the overall accuracy of the calibration.

SUMMER - UNIT 1 B 3/4 3-4 Amendment No. g 142

u N

INSTRUMENTATION l

BASES POWER DISTRIBUTION MONITORING SYSTEM (PDMS) (Continued) i l

l The minimum number of required plant and core condition inputs includes the following:

l 1.

Control Bank Positions.

2.

At least 50% of the cold leg temperatures.

3.

At least 75% of the signals from the Power Range excore detector channels (comprised of a top and bottom detector section).

4.

Reactor Power Level.

5.

~ A minin um number and distribution of operable core exit thermocouples.

6.

A minimum number and distribution of measured fuel assembly power distribution information obtained using the incore movable detectors is incorporated in the nodal model calibration information.

The sensor calibration of items 1.,2., 3., and 4. above are covered under other speofications.. Calibration of the core exit thermocouples is accomplished in two parts. The first being a sensor specific correction to K-type thermocouple temperature indications based on data from a cross calibration of the thermocouple temperature indications to the average RCS temperature measured via the RTDs under isothermal RCS conditions. The second part of the thermocouple calibration is the generation of thermocouple flow mixing factors which cause the i

radial power distribution measured via the thermocouples to agree with the radial power distribution from a full core flux map measured using the incore movable detectors. This calibration is updated at least once every 180 EFPD.

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SUMMER - UNIT 1 B 3/4 3-5

' Amendment No.142

r

'.O

+

_ ADMINISTRATIVE CONTROLS

(,S.I.9 -

Not used.

t MONTHLY OPERATING REPORT t

l 6.9.1.10 Routine re,< ris of operating statistics and shutdown experience, including documentation of all challenges to the PORV's or safety valves, shall be submitted on a 1

l monthly besis to the Director, Office of Resource Management, U.S. Nuclear Regulatory 1

Commission, Washington, D.C. 20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.

A report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the eve!uation was reviewed and accepted as set forth in 6.5 above.

CORE OPERATING LIMITS REPORT 6.9.1.11 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reload cycle, or prior to any remaining portion of a l

reload cycle, for the following:

Moderator Temperature Coefficient BOL and EOL Limits and 300 ppm a.

surveillance limit for Specification 3/4.1.1.3, b.

Shutdown Rod Insertion Limit for Specification 3/4.1.3.5, l

c.

Control Rod insertion Umits for Specification 3/4.1.3.6, d.

Axial Flux Difference Limits, target band, and APL" for Specification 3/4.2.1, Heat Flux Hot Channel Factor, (*, K(z), W(z),

APL", W(z)st, and Fo(z) e.

manufacturing / measurement uncertainties for Specification 3/4.2.2, l

f.

Nuc* ear Enthalpy Rise Hot Channel Factor, F5P, pggg7 pgggg7 ggggj gjg7, 3

1 N

PF s, and F y measurement uncertainties limits for Specification 3/4.2.3.

3 3

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 docunients:

j a.

WCAF-9272-P-A,

WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (W Proprietary).

l SUMMER - UNIT 1 6-16 Amendment No. 79, es,101, * * ?,142

A

- ADMINISTRATIVE CONTROLS CORE OPERATING L!MITS REPORT (Continued)

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Rod insertion Limit. 3.1.3.6 - Control Rod Insertion Limit, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Charinel Factor, and 3.2.3 -

- l RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor.)

b.

WCAP-10216-P-A, Rev.1 A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL Fo SURVEILLANCE TECHNICAL SPECIFICATION", February 1994 l

(W Proprietary).

(Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (Fo Methodology for l

W(z) surveillance requirements)).

c.

WCAP-103-P-A, Rev. 2, "THE 1981 VERSION OF WESTINGHOUPE EVALUATION MODEL USING BASH CODE", March 1987; including Addendum 2 A, BASH METHODOLOGY IMPROVEMENTS AND RELIABILITY l

ENHANCEMENTS", May 1988, (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor).

d.

WCAP-12472-P-A," BEACON CORE MONITORING AND OPERATIONS SUPPORT SYSTEM", August 1994, (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor, 3.2.3 -

I RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor, and 3.2.4 -

Quadrant Power Tilt Ratio).

The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limite, nuclear limits such es shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

l The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements

. there to shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident inspector.

l J

l I

p

. SUMMER - UNIT 1 6-16a Amendment No. M. 121,133, 142 i

i[

ML20205P505

Text

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