ML20024G229

Proposed Tech Specs Involving Main Steam Line Low Pressure Setpoint & MCPR Limit

ML20024G229
Person / Time
Site:	Monticello
Issue date:	12/01/1975
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20024G225	List: ML20024G224 ML20024G227 ML20024G229
References
NUDOCS 9102080374
Download: ML20024G229 (7)

Text

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l EXHIBIT B

, , LICENSE AMENIHENT REQUEST DATED DECDiBER 1,1975

' Exhibit B, attached, consists of newly prepared pages for the Appendix A

.., Technical Specifications as listed below. These pages incorporate the v . ",q':)( proposed changes.

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PAGES 50 66 1 1890

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Instrumentation '! hat Initiates Primary Contaitunent Isolation Functions , . ,

i Min. No. of Operable -

Total No. of Instnt- or Operating Instru-ment Channels Per ment Qiannels Per Trip Bequired Function Trip Settings _ Trip System System (1,2) Coralitions*

1. Main Steam and Becire Semqple Lithes (Group 1)

a. Iow Iow Heactor d6'-u n.10" 2 2 A O

! Weter Ievel

b. High Flow in Main

{ Steen Line il' 0%

4 rated 8 8 A

c. High tesp. in k in 2 of k in each i Steam Line Tunnel b200% 8 of 2 sets A

d. Iow Pressure in hin I Steam Line (3) d825 pais 2 2 3

e. R16h Radiation In Main 610 I Nonnel Steam Line Tunnel backgroual at 2 2 ,

A rested power

2. RER System, Head Cooling, Dryvell, Stasp, TIP (Group -

2)

e. Iow Beactor Water 310'6" above the 2 2 C Ievel tcp of the active fuel 3 2/k.2 50 I

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e Bases Continued:

32 instrumentation is provided which causes a trip of Group 1 isolation valves, he primary function of the instrumentation is to detect a break in the main steenline, tnus only Group 1 valves are clored. For the worst case accident, main steamline break outside the dryvell, this trip setting of 1h0% of rated steam flow in conjunction with the flev limiters and main stearline valve closure, limit the mess inventory loss such tha< fuel is not uncovered, fuel clei temperatures remain less than 1000 F and release of radioactiv! ty to the environs is well belov 10 CFR 100 guidelines.

Reference Sections 14.6.5 FEAR.

Temperature monitoring instrumentation is provided in the nain steemline tunnel to detect leeks g in this area. Trips are provided on ghis inst 2.nentation end when excee'ied cause closure of Group 1 isolation valves. Its setting of 200 F is lov enough to detect leaks of the order of 5 to 10 gpm; thus, it is capable of covering the entire spectn:m of breaks. For large breaks, it is a back-up to high steam flow instrumentation discussed above, and for small % reeks with the resultant small release of radioactivity, gives isolation before the guidelinen of 10 CFR 100 are exce-ded.

High radiation monitors in the main steamline tunnel have been provided to detect gross fuel failure I

resulting frce a control rod drop accident. This instnzmentation causes closure of Group 1 valves, I the only valves required to close for this accident. With the established setting of 10 times nomal background, and mein steamline isolation valve closure, firsion product release is limited so that 10 CFR 100 guidelines are not exceeded for this accident. Reference Section 14.6.2 FSAR.

De perfomance of the process radiation monitoring system relative to detecting fuel leakage shall be evaluated during the first five years of operation. The conclusions of this evaluation vill be reported to the Atomic Energy Ccruission.

Pressure instnzmentation is provided which trip- when main steamline pressure drops belov 825 l

peig. A trip of this instrumentation results in closure of Group 1 isolation valves. In the g

" refuel" and "Startup" mode this trip function is bypassed. This 11tnction is provided primarily to provide protection against a pressure regulator malfunction which would cause the control and/or l bypass valves to open. With the trip set at 825 psig inventory loss is limited so that fuel is I

not uncovered and peak clad te=peratures are much less then 1500 F; thus, there are no fission products available for release other than those in the reactor water. Reference License Amendment Request Dated December 1,1975 from L. O. Mayer (NSP) to R S. Boyd (USNRC).

66 REV 3.2 BASES .

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3.0 LIMITING CmDITIWS F,0R _0PERATIW 4.0 SURVEILLANCE REQUIREMDITS

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C. Minf== Critical Power Ratio (MCPR) C. Minimum Critical Power Ratio OtCFR)

During steady state power operation, 1. MCPR shall be checked daily the Operating MCPR Limit shs11 be during reactor power operation at l 21.38 for 8x8 fuel and 21.29 for E 257. rated thermal powsr. -

7x7 fuel at rated power and flow.

For core flows other than rated the 2. Whenever the plant technical staff determines Operating PCPR Limit shall be the that more frequent surveillance of MCPR is above value nazitiplied by Kg , neces % ;, it shall specify an augmented where Kg is given by Figure 3.11.2.  :;.,rvet11ance program comunensurate with reactor If at any time it is determined that conditions, the limiting value of NCPR is being exceeded, action shall be taken imunediately to restore operation to within prescribed limits.

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e Bases 3.11- (continued) ," ",

C Minietzn Critical Power Ratio (MCPR)

The ECCS evaluation presented in Reference 4 assumed the steady state MCPR prior to the postulated loss of coolant accident to be 1.18 for all fuel types. The Operating MCPR Limit l of 1.33 for 8x8 feel and 1.29 for 7x7 fuel is detemined from the analysis of transients discussed in Bases Sections 2.1 and 2.3. By maintaining an operating MCPR above these limits.

the Safety Limit of 1.06 (T.S.2.1. A) applicable to all fuel types is pintained in the event of the most lim'_ ting abnomal operational transient.

For operation with less than rated core flow the Operating MCPR Limit is adjusted by multiplying the above limit by K f. Reference 5 discusses how the transient analysis done at rated conditions encompasses the reduced flow situa' tion when the proper gK factor g

is applied.

It is recognized that MCPR is a calculated parameter that is not continually monitored and alanned directly during core power distribution and thermal-hydraulic changes. If at the time of the evaluation it is found that the limits are being exceeded, there is always an action which will return the MCPR to within prescribed limits, namely power reduction. Under most circumstances, this will not be the only alternative. Whenever the limit is exceeded the monitored value will be documented and available for review, audit and inspectf on of plant operations.

The only way to violate the Limiting Condition for Operation is to knowingly allow operation beyond the prescribed limits without taking the necessary action to restore the MCPR to within prescribed limite.

Re ferences

1. " Fuel Densification Effecte in General Electric Boiling Water Reactor Fuel," Supplements 6, 7, and 8, NEDM-10735, Augusq 1973.

2. Supplement I to Technical Report on Densification of General Electric Reactor Fuels, December 9 14, 1974 (USAEC Regulatory Staff)

3. Ccemunication: V A Moore to I S Mitchell, " Modified GE Model for Fuel Densification,"

Docket 50-321, March 27,1974.

4. "Monticello Nuclear Generating Plant Loss-Of-Coolant Accident Analysis Conformance with 10 CFR 50 Appendix K, August 1974," L 0 Mayer (NSP) to J F O' Leary, August 20, 1974.

5. " General Electric BWR Generic Reload Application for 8 x 8 Fuel," NEDO-20360. Revision 1, Novembe r, 1974 3.11 BASES F n.

NRC DISTRIBUTION FOR PART 50 DOCKET MATERI AL

, * (TEMPORARY FORM)

CONTROL NO: 13535 e

, FILE:

FROM: Northern States Power Cc . DATE OF DOC DATE REC'D LTR TWX RPT OTHER 55401 i

g e g s, Minn. 12-1-75 12-3-75 XX

-- TO: . ORIG CC OTHER SENT NRC POR XX Mr. R.S. Boyd 1 signed XX 39 SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:

XXX 40 50-263 -

DESCRIPTION: Ltr trans the following: ENCLOSURES: Request for Amdt to OL/DPR-22 notarized 12-1-75 / Tech Specs with Exhibit A entitled " Proposed Changes to Tech Specs App. A of OL/DPR-22'? & ExhibitB entitled

" License Amdt Request dated Dec. 1.,1975"...

(3 Orig & 37 CC' rec'd)

PLANT NAME: Monticello Plant FOR ACTION /INFL RMATION DHL 12-3-73 BUTLER (L) SCHWENCER (L) dlEA NN (L) REG AN (E) REID(L)

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STELLO MCDONALD MOORE (L) HOUSTON M. RUI.lER00?(L)

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DICKER S. SHEPPARD (L) E. COUPE GO8.LER (L) (Ltr) IPPOLITO KNIGHTON M. SLATER (E) PETERSON P. COLLINS TEDESCO YOUNGBLOOD H. SMITH (L)

DENISE HARTFIELD (2)

J. COLLINS REGAN S. TEETS (L) KLECKER W.G OPR -

LAIN AS *@ CT LDR G. WILLI AMS (E) EISENHUT

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VOLLMER _.I A@.ES _

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