ML20078S770

From kanterella
Jump to navigation Jump to search
Corrected Page to Amend 34 to License NPF-86,inserting Replacement Page B 3/4 2-4
ML20078S770
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 02/22/1995
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20078S773 List:
References
NUDOCS 9502270131
Download: ML20078S770 (5)


Text

i l:

lN ATTACHMENT TO LICENSE AMENDMENT NO. 34 l

l FACILITY OPERATING LICENSE NO. NPF-86 l

DOCKET NO. 50-443 i

Replace the following pages of Appendix A, Technical Specifications, with the attached pages as indicated. The revised pages are identified by amendment i

number and contain vertic31 lines indicating the areas of change. Overleaf pages have been provided i

Remove Insert iX IX X

X Xiii Xiii*

Xiv Xiv j

~

xv xy 1-5 1-5 i

1 1-6*

l-6*

B 2-7 8 2-7 B 2-8*

B 2-8*

3/4 3-13 3/4 3-13 3/4 3-14*

3/4 3-14*

3/4 3-49 3/4 3-49 3/4 3-50*

3/4 3-50*

3/4 4-1*

3/4 4-1*

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

3/4 6-17 3/4 6-17 l

3/4 6-18*

3/4 6-18*

3/4 7-3 3/4 7-3 3/4 7-4*

3/4 7-4*

9502270131 950222 PDR ADOCK 05000443 i

P PDR

h;;

5) i Remove Insert 3/4 10-5*

3/4 10-5*

3/4 10-6 3/4 10-6 B 3/4 1-3 B 3/4 1-3 B 3/4 1-4*

B 3/4 1-4 B 3/4 2-3*

B 3/4 2-3*

B 3/4 2-4 B 3/4 2-4 B 3/4 3-l*

8 3/4 3-1*

B 3/4 3-2 B 3/4 3-2 B 3/4 4-5 B 3/4 4-5 B 3/4 4-6*

B 3/4 4-6*

B 3/4 10-1 B 3/4 10-1 5-9 5-9 5-10*

5-10*

6-5 6-5

)

6-6 6-6 6-7 6-7 6-8 6-8 6-8A 6-8B 6-9 6-9 6-10 6-10 6-11 6-11 6-12 6-12 I

6-13 6-13

r:;

a 4

.p: Remove Insert 6-14 6-14 6-14A 6-- 17*

S_17*

6-16 6-18 4

i f

l I

i

}

POWER DISTRIBUTION LIMITS BASES

)

3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued)

F" will be maintained within its limits pitvided Conditions a. through d.

above ar,e maintained. The design limit DNBR incbdes margin to offset any rod bow penalty. Nargin is also maintained between *he safety analysis limit DNBR and the design limit DNBR. This margin is available for plant design flexibility.

When an F measurement is taken, an allowance for both measurement error l

and manufacturi,ng tolerance must be made. An allower.ca of 5% is appropriate for a full-core map taken with the movable incore de*,ectors, while 5.21% is appropriate for surveillance results determined eith the fixed incore detectors.

A 3% allowance is appropriate for manufacturing tolerance.

I For operation with the Fixed Incore Detector System (FIDS) Alarm OPERABLE,

[

the cycle-dependent normalized axial peaking factor, K(Z), specified in COLR i

accounts for axial power shape sensitivity in the LOCA analysis. Assurance that the F,(Z) limit on Specification 3.2.2 is met during both normal operation and in the event of xenon redistribution following power changes is provided by the FIDS Alarm through the plant process computer. This assures that the j

consequences of a LOCA would be within specified acceptance criteria, j

For operation with the FIDS Alarm inoperable, the cycle-dependent normalized axial peaking factor, K(Z), specified in COLR accounts for possible xenon redistribution following power chrnges in addition to axial power shape 4

sensitivity in the LOCA analysis. This assures that the consequences of a LOCA would be within specified acceptance criteria.

i When RCS F" is measured, no additional allowances are necessary prior to comparison with M e established limit. A bounding mea.curement error of 4.13%

for F"a has been allowed for in determination of the design DNBR value, 1

3/4.2.4 OUADRANT POWER TILT RATIO The purpose of this specification is to detect gross changes in core power distribution between monthly Incore Detector System surveillances. During i

normal operation the QUADRANT POWER TILT RATIO is set equal to zero once acceptability of core peaking factors has been established by review of incore surveillances. The limit of 1.02 is established as an indication that the power distribution has changed enough to warrant further investigation.

l

'o i

SEABROOK - UNIT 1 B 3/4 2-3 Amendment No. 33 i

t:

u

$~

POWER DISTRIBUTION LIMITS BASES J

3/4.2.5 DNS PARAMETERS The limits on the DN8-related parameters assure that each of the parameters is_ 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 analytically demonstrated adequate to maintain a' minimum DNBR of 1.30 throughout each analyzed transient. Operating procedures include allowances for measurement and indication uncertainty so that the limits of 594.3*F for T,, and 2205 psig for pressurizer pressure are not l

exceeded.

t The measurement error of 2.4% for RCS total flow rate is based upon per-forming a precision heat balance and using the result to normalize the RCS flow rate indicators. Potential fouling of the feedwater venturi which might not be detected could bias the result from the precision heat balance in a noncon-servative manner. Therefore, a penalty of 0.1% for undetected fouling of the feedwater venturi is applied. Any fouling which might bias the RCS flow rate measurement greater than 0.1% can be detected by monitoring and trending various plant performance parameters.

If detected, action shall be taken before performing subsequent precision heat balance measurements, i.e., either the *,

effect of the fouling shall be quantified and compensated for in the RCS flow' rate measurement or the venturi shall be cleaned to eliminate.the _ fouling.

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

The periodic surveillance of indicated RCS flow is sufficient to detect only flow degradation which could lead to operation outside the specified limit.

d i

- SEABROOK UNIT I B 3/4 2-4 Amendment No. 34