ML20067C099

Proposed Tech Specs Re Reactivity Control Sys Moderator Temp Coefficient & Core Operating Limits Rept

ML20067C099
Person / Time
Site:	Davis Besse
Issue date:	02/06/1991
From:	CENTERIOR ENERGY
To:
Shared Package
ML20067C093	List: ML20067C091 ML20067C095 ML20067C099
References
NUDOCS 9102110196
Download: ML20067C099 (6)

Text

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Docktig Number 50-346 License Number NPr3 Serial Number 1902 Attachment )

J'aBe 6 of 9 dTT7tTT CO?mt0L SYSTDG MODtRATOR ftMPERATURE COETTtCTUf7 .

LIMitiMC CONDIT10N 70R OPERAT!0W .

3.1.1.3 The moderator temperature cr'.fficient (MIC) shall bet

s. Less positive than 0.9 = 10** Ak/k/'T whenever TIER.% POWER is < 93% of '

RATED TETA % POWER, '

b. Less positive than 0.0 = 10** t.k/k/*? whenever TIERMAL POWER is 2 95%

RATED TIER'.%L P%TR, and Equal to or less negative than -1.^

- ja** 1S/*? at RATED TEERHAL POWER.

c.

Ik \imw geod1 A % Cats. OMRume L.\ms CUbtw a AFFLtCAlttIrtt MODES 1 and 2*f.

Mt ide any of the above limits, m'ith the modarator temperature coef ficient outs be in at least IIOT STAND 3Y vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. .

$URVETLt.ANCE RE0"IL".IhT5 The MTC shall be determined to be within its limits by confirmatory 4.1.1.3.1 MTC measured values shall be extrapelated and/or compensated to measurements.

permit dirset comparison with the above limits, The MIC shall be determined at the following frequencies and 4.1.1.3.1 TEE 30%L POWER conditions during each fuel cyc.las

a. Prior to initial operation above 5% of RATED ', TMERMAL POWER, af ter e fuel loading.

b.

At any TEERMAL ?%TR, within 7 days af ter raat.hing a RATED THER equilibrium baron concentration of 300 ppe.

i

• With k,gg 2 1.0.

l isee Special Test- Exception 310.2.

3 /4 l *4 Amendment No. 45

! DAVIS-SESSE. WIT 1 .

91G2110196 910206 PDR ADOCK 05000346 P PDR

_.___..._____________.--.m__ . _ _ _ . . _ . _ . . - _ _ _ . . _ _ . _ . -_ . _ _ _ . _

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Docket humber 50-346 Attachment !

License Number NPP3 Page 9 of 9 .

Serial Numb'qi 1902 ADMIN!STRAT!VC CONTROLS i

microcuries per gram as a function of time for the duration of the specific activity above the steady-state levelt and (5) The time duration wnen the specific activity of the primary coolant exceeded l

tne radiciodine limit. 4

, HONTHLY OPERAT!NG REPORT 6.9.1. '

tine reports of operating statistics, shutdown experience and challer , i .4 the Pressuriger Pilot Operated Relief Valve (PORV) and the Pressurf ter Code Safety Valves shall be submitted on a monthly basis to arrive no later than the 15th of each month following the calender month covered by the i report, as follows: The signed original to the Nuclear Regulatory Comission, Document Control Desk, Washington, D. C. 20555, and one copy each to the Region 111 Administrator and the Davis Besse Resident Inspector.

CORE OPERATING LIMITS REPORT t

6. 9.1. 7 Core operating limits shall be established and documented in the CORE-OPERATING LIMITS REPORT before each reload cycle and any remaining part of a i reload cycle for the following:

CJQ4 w* h a 1 n \ ,% wh R.kh*hecAv.

3.1.3.6 Regulating Rod Insertion Limits 3.1.3.7 Rod Program 3.1.3.8 Xenon Reactivity 3.1.3.9 Axial Power Shaping Rod Insertion Limits 3.2.1 AXIAL POWER IMSALANCE

-3.2.4 QUADRANT POWER TILT >

The analytical methods used to detemine t1e core operating limits addressed by the individual Technical Specifications shall be those previously reviewed and approved by the NRC, specifically:

1) BAW 10122A Rev.1, "Nonnal Operating Controls May 1984

.2) BAW-10116A, " Assembly. Calculations and Fitted nuclear Data." May 1977 i

3) BAW-10117P A, " Babcock & Wilcox Version of PDQ User's Manual,"

January 1977

4) BAW-10118A, " Core Calculational Techniques and Procedures,"

December 1979-

5) BAW-10124A, " FLAME 3 A Three-Dimensional Nodal Code for Calculating Core Resctivity and Power Olstributions," August 1976

-6) - BAW-10125A, " Verification 'of Three-Mansional FLAME Code." August 1976

7) BAW 10152A, "N000LE - A Multi-Dimensional Two-Group Reactor Simulator," June 1985 0 AVIS-BESSE. UNIT 1 6 16 Amendment No. 8.12.f3.JH 135,144 i

__.d.~-..- ~ . ~ , . . ~ . ~ ~ - - _ .-- - ~ . - , - . , - - . . . - - - - - , - - . . . . , - - . - , - ~ - . . . - , , - - , - - - - , . - - - , . - . , . . , _ ~

_ . _ . . . ~

_.____ . . _ ._.._..._m_____--_____. .

._._.__.7__

-i k>che t Hutnber ' 50-346 .;

i . License Number NPP3 Serial Number 1902 COLR E-

- Attachtwnt 2 Page 3 of 26 1

. .. Page 1 of 4- Revision 0 3.2.1 Figure 5a AXIAL POVER IMBALANCE i Limits. O to 30 l 4 +10/-0 EFFD, Tour RC Pumps '

3.2.1 Figure 5b AXIAL POVER IMBALANCE l Limits. 30 10/-0 to 75 l 10/-0 EFPD, Four RC Pumps 3.2.1 i

Figure 5c AX1AL POVER IMBALANCE 4 Limits. 75 +10/-0 to 335 10 ~

ETPD, Four RC Pumps 3.2.1 Figure $d AXIAL POVtR IMBALANCE Limits. Af ter 335 +10 EFPD, -

Four RC Pumps 3.2.1 Figure 6a AXIAL POVER IMBALANCE Limits. O to 30 +10/-0 EFPD,  ;

Three RC Pumps 3.2.1 Figure-6b AXIAL POVER IMBALANCE Limits, 30 +10/-0 to 75 4

+10/-0 EFPD, Three RC Pumps 3.2.1 Figure 6c AXIAL POVER IMBALANCE Limits 75 +10/-0 to 335

• 10 EFPD, Three RC Pumps 3.2.1 Figure 6d AXIAL POVER IMBALANCE Limits Atter 335 +10 EFPD, Three RC Pumps

- 3.2.4 Table 1 OUADRANT POVER TILT Limits

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v. .we,-- -,,--w-s #,,.-+,-em,,,..w. #- - . , .,,-..,..-,wr,my.- , ,,,--,-,-%- ,-wv.,.-~w-nr--.c~~,. *<x -

--,-.ve. - . -e a ve , a.w e .m +esw , = -w.-vw-a, *e L- ww-+w----ws -

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Docket' Number 50-346 eLicense Number NPF3 COLR Serial Number 1902 Attachment 2 Page 4 sf 26

.Fege 2 of 4- Pr. .k- 0 TOLEDO EDISON DAVIS-BESSE UNIT 1 CYCLE 7 I

CORE OPERATING LIMITS REFORT 1.0 Core Operating Limits ,

This CORE OPERATING LIMITS REPORT for DB-1 Cycle 7 has been prepared in accordance with the requirements of Technical Specification 6.9.1.7. The core operating limits have been developed using the methodology provided in the references.

The following cycle-specific core operating limits are included in this report

1) Regulating rod insertion limits

2) Rod program group positions

3) Axial power shaping rod insertion limits

4) AXIAL POVER IMBALANCE operating lisits and

$) OUADfJWT POVER TILT lialts/

(h hubt. Wobembt- % cS d to CocM tank b'.%

2.0- Rdferences

1) B&V Fuel Company Topical Report BAl' 10122A Rev.1 " Normal Operating Controls", May 1964

2) B&V Fuel Company, Topical Report BAV-10116A, " Assembly Calculations and Fitted Nuclear Data", May 1977-

3) B&V Fuel Company. Topical Report BAV-10117P-A, " Babcock & Vilcox Version of PD0 User's Manual", January 1977

4) B&V Fuel Company, Topical Report BAV-10118A, " Core Calculational Techniques and Procedures". December 1979.

-5) B&V Fuel Cotaparf, Topical Report BAV-10124A, "TLAME 3 - A Three-Dimensional Nodal Code for Calculating Core Reactivity and Power Distributions" August 1976

6) B&V Fuel ~ Company,' Topical Report BAV-10125A,-" Verification of Three-Dimensional FLAME Code', August 1976

7) B&V Fuel Company, Topical Report BAV-10152A, " NOODLE - A _

Multi-Dimensional Two-Group Reactor Simulator", June 1985 C-4

. _ _ . . _ _ -. . . . _ . , . . . _ . _ . ~ . . . ~ . _ _ _ , _ . . . . _ , _ _ _ _ . , - - _ . - - , _ _ _ - . . . _ _ . , _ .

Docket Number 50-346 d1,1 cense Number NPF3 I COLR Serial Nornher 1902 Pcge L of 26

• Attachment 2 Revision 0

• Page 3 or 4'

8) B&V Tuel Company. Topical Report BAV-10119. "Pover Pesting Nuc)&ar heliability Tactors". June 1977

9) Log Number 3139, dated January 11, 1990 (T. V. Vambach (NRC) to D. C.

Shelton (TE)). (NRC SER for Rod Program)

( - (MPCh *o D.C. S U M

56) \. Seebe hdeth s.%

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Co@6td bmh) i l c.5 y .-,.g, , ,i,o... .---s-.--e- --i-- i  % % y- m v 3 y e e e ,, . - - + - .--es---y-sr ,,

pocket *Nurube r 30-346 1leent.e Number hTi'3 Serial Number 1902 Attachment 2

'Page 4 of 4" COLR Page XX of XX Revision X Table 2 Necative Moderator Temrierature Co-fficient Limit This Table is referred to by Technical Specification 3.1.1.3c Negative Moderator Temperature Coefficient Limit -

3.62 x 10 AkM'F (at RATED THERMAL POWER)

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