ML19347F319

Forwards Notice of Issuance of Amend 5 to DPR-22 for Publication in Fr

ML19347F319
Person / Time
Site:	Monticello
Issue date:	05/07/1981
From:	Office of Nuclear Reactor Regulation
To:	NRC OFFICE OF THE SECRETARY (SECY)
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ML19347F320	List: ML19347F319 ML19347F323
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NUDOCS 8105180374
Download: ML19347F319 (1)

Text

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UNITED STATES N

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o, NUCLEAR REGULATORY COMMISSION WASHINGTON. O C. 20555

,l MAY 7 19 81 Docket No.

50-263 ff'!.j 27

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Docketing and Service Section

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Office of the Secretary of the Commission

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SUBJECT:

Monticello Nuclear Generating Plant w

(Northern States Power Company) 4 6

Two signed originals of the Federal Register Notice identified below are enclosed for your transmittal to the Office of the Federal Register for publication. Additional conformed copies (

)of the Notice are enclosed for your use.

O Notice of Receipt of Application for Construction Permit (s) and Operating License (s).

O Notice of Receipt of Partial Application for Construction Permit (s) and Facility License (s): Time for Submission of Views on Antitrust Matters.

C Nctice cf Availability of Applicant's Environmental Report.

O Notice of Proposed Issuance of Amendment to Facility Operating License.

O Notice of Receipt of Application for Facility License (s): Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License (s) and Notice of Opportunity for Hearing.

O Notice of Availability of NRC DraftFinal Environmental Statement.

O Notice of Limited Work Authorization.

O Notice of Availability of Safetv Evaluation Report.

C Notice of issuance of Construction Permit (s).

E Notice of issuance of Facility Operating License (s) or Amendment (s).

XE Other: Rafarancad aneuments haue heen provided to the pnp,,

Office of Nuclear Reactor Regulation

Enclosure:

ORB #2 As Stated OL

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION e

WASHINGTON, D. C. 20555 g,-

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[;3 h.[ bhak, Docket No. 50-263 Mr. L. O. Mayer, Manager Northern States Power Company 414 Nicollet Mall - 8th Floor Minneapolis, Minnesota 55401

Dear Mr. Mayer:

In response to your application dated February 6,1981, supplemented by letter dated March 19, 1981 and subsequent discussions between the NRC staff and your staff, the Consnission has issued the enclosed A.mendment No. S to Facility Operating License No. DPR-22 for the Monticello Nuclear Generating Plant.

This amendment authorizes Technical Specification changes that.:

(1)in-corporate the requirements of ODYN (0ption B) and new MAPLHGR and MCPR limits associated with recent analyses for Cycle 9 operation, (2) change the RPS delay time to the value assumed in the licensing analysis, and (3) make minor clarifying changes in the bases having no safety signif-Cance.

Copies of the Safety Evaluation and Notice of Issuance are also enclosed.

Sincerely, a

I hk Y&atan,d* r Thomas A. Ippolito, Chief

/ Operating Reactors Branch #2 Division of Licensing Enelosures :

1.

Amendnent No. 5 2.

Safety Evaluation 3.

Notice cc w/ enclosures:

See next page bloct30318 y

Mr. L. O. Mayer Norttern States Power Company cc:

Gerald Charnoff, Esquire The Environmental Conservation Shaw, Pittman, Potts and Library Trowbridge Minneapolis Public Library 1800 M Street, N. W.

300 Nicollet Mall Washington, D. C.

20036 Minneapolis, Minnesota 55401 Arthur Renquist, Esquire Commissioner of Health Vice President - Law Minnesota Department of Health Northern States Power Company 717 Delaware Street, S.E.

414 Nicollet Mall Minneapolis, Minnesota 55440 Minneapolis, Minnesota 55401 Mr. D. S. Douglas, Auditor Wright County Board of Commissioners Plant Manager Buffalo, Minnesota 55313 Monticello Nuclear Generating Plant Northern States Power Company Director, Criteria and Standards Monticello, Minnesota 55362 Division Office of Radiation Programs (ANR-460)

Russell J. Hatling, Chairman U. S. Environmental Protection Agency Minnesote Environmental Control Washingtor., D. C.

20460 Citizens Association (MECCA)

Energy Task Force 144 Melbourne Avenue, S. E.

U. S. Environmental Protection Agency Minneapolis, Minnesota 55414 Federal Activities Branch Region V Office ATTN:

EIS COORDINATOR Ms. Terry Hoffman Executive Director 230 South Dearborn Street Minnesota Pollution Control Agency Chicago, Illinois 60604 1935 W. County Road B2 Roseville, Minnesota 55113 Mr. Steve Gadler 2120 Carter Avenue St. Paul, Minnesota 55108 U.S. Nuclear Regulatory Commission Resident Inspectors Office Box 1200 Monticello, Minnesota 55362 e

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,o UNITED STATES g

NUCLEAR REGULATORY COMMISSION y';Tpr g

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/..E WASHINGTO N, D. C. 20555 Q*W/

NORTHERN STATES POWER COMPAtlY DOCKET NO. 50-263 lEITICELLO NUCLEAR GENERATING PLANT AMENDfENT TO FACILITY OPERATING LICENSE Amendment No. 5 License flo. DPR-22 1.

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

A.

The application for amendment by Northern States Power Company (tfie licensee) dated February 6,1981, as supplemented by letter dated March 19, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confomity with the application,

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the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

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

1 8msnosM

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2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-22 is hereby amended to read as follows:

2.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 5

, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.,

FOR THE flVCLEAR REGULATORY COMMISSION A

M omas A..Ippolito, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 4,1981

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ATTACHMENT TO LICENSE AMENDriENT NO. 5 FACILITY OPERATING LICENSE NO. DPR-22 ~~~ '~ I DOCKET NO. 50-263 Remove the following pages and insert identically numbered pages:

26 82 89 90 213 214 216 217 G

N 3.0 1.1HITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

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3.1. HEACTOR PROTECTION SYSTEM 4.1 REACTOR PROTECTION SYSTEM

'h.

Applicability:

Applicability:

Applies to the instrumentation and associated Applies to the surveillance of the instrumentation Javices which initiate a reactor scram, and associated devices which initiate reac'.or scram.

Obejective:

Objective:

g To assure the operability of the reactor To specify the type and frequency of surveillance protection system.

to be applied to the instrumentation that initiates g'

a scram to verify its operability.

j Specification:

Specification:

I A. The setpoints, minimum number of trip A. Instrumentation systems shall be functionally systems, and minimum number of instrument tested and calibrated as indicated in Tables k.

channels that must be operable for each 4.1.1 and 4.1.2, respectively.

position of the reactor mode switch shall g.

be as given in Table 3.1.1.

The time from initiation of any channel trip to the de-energization of the scram pilot val,ve solenoids l

shall not exceed 50 milliseconds.

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,i-I 26 j

1/4.1 i-!

l Amendment No. 5 1

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4.0 SURVEILLANCE REQUIREMENTS

~1.0 1.IIIITlHG CollDITIOttS FOR OPERATION h2 Any four rod group may contain a control rod which is valved l.

of service provided the above requirements and out Specification 3.3.A are met.

3. If the cycle average scram insert ion time ($s), based on the de-energization of the scram pilot value solenoids at t isse ze ro,

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of all operable control rods in the react or power ' peration o

I cond it ion at the 20% inserted position is larger than the adjusted analysis mese scram time ( 'fs

), a enore restrictive MCPR l

l limit (see section 3.II.C.1) siiall be used.

i l

D. Contral Rod Accumulators D. Control Rod Accumlators l

rod accumulator may be Once a shift check the status in the At all reactor operating pressures, a

inoperable provided that no other cont rol rod in the nine'-

control room of the accumulators pressure I and level alarms.

so.1 square array around this rod has a:

I. Inoperable accumulator.

7. Direct ional control valve electrically disarmed while in a non-fully inserted position.

I f a cont rol rod with an inoperable accumulator is inserted

" full-in" and it s direct ional control valves are electrically disarmed, it chall not be considered to have an inoperabe ac cu nns l a t o r.

82 l'

3.1/4.1 Amendment flo. 5

Bases Continued 3.3 and 4.3:

consequences of reactivity. accidents are functions of the initial neutron flux. The require-ment of at least 3 counts per second assures that any transient, should it occur, begins at or above the initial value of 10% of rated power used in the analyses of transients from cold j

i conditions. One operable SRM channel would be adequate to moaitor the approach to criticality using homogeneous patterns of scattered control rod withdrawal. A minimuu of two operable l

SRM's are provided as an added conservatism.

i 5.

The consequences of a rod block monitor f ailure have been evaluated. These evaluations show i

that during reactor operation with certain limiting control rod patterns, the withdrawal of a designated single control rod could result in one or more fuel rods with MCPR's below the

• Safety Limit (T.S.2.1.A).

During use of such patterns, it is judged that testing of the RBM system prior to withdrawal of such rods to assure its operability will assure that improper withdrawal does not occur.

It is the responsibility of the Engineer, Nuclear, to identify these limiting patterns and the designated rods either when the patterns are initially

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established or as they develop due to the occurrence of inoperable rods in other than limiting l'

I' patterns.

C.

Scram Insertion Times j

i The control rod system is designed to bring the reactor suberitical at a rate fast eneugh to g

prevent fuel damage; i.e., to prevent the MCPR from becoming less than the Safety Limit (T.S.2.1.A).

j This requires the negative reactivity insertion in any 1t eal region of the core and in the l

overall core to be equivalent to at least the scram reactivity curve used in the transient analysis. The required average scram times for three control rods in all two by two arrays and the required average scram times for all control rods are baged on inserting this amount of aegative reactivity at the specified rate locally and in the overall core. Under these conditions,

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the thermal limits are never reached during the transients requiring control rod scram. The limiting operational transient is that resulting from a turbine stop valve closure with failure of the turbine bypass system. Analysis of this transient shows that the negative reactivity rates resulting from the scram with the average response of all the drives as given in the above Specification, provide the requirel protection, and MCPR remains above the Safety Limit (T.S.2.1. A).l

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a 3.3/4.3 BASES 89 f,

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1 Amendment No. 5 s

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nases Continued 3.3 and 4.3:

n e analysis assumes 50 milliseconds for Reactor Protection System delay, 200 milli seconds from de-energization of serais solenoids to the beginning of rod motion, and 175 milliseconds later the rods are at the SI position.

Sect ion 3.3.C.3 allows a lower MCPR limit to be used if the cycle average scram time (%s ) is less than the adjusted analysis mean scram time (Ta) (see Reference 7, of Section 3.11) i Y,.. is the weighted cycle average scram t ime to the 20% insertion position (~ notch 38) of all the operable.

rods measured at any point in the cyce.

where:

n = the number of surveillance testa performed to date in this cycle.

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3 NT g i i = number of control rods w r.sured in the I"1 th test.

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'T,',,

=

f

'Y

= average scram time to the.20% insertion N

i position of all rods measured in the ith i=1 test.

T, i s the adjusted analysis mean scram time diere:

N

= total number of active rods measured in i

g to the 20% insert ion posit ion.

the first test following core alterations.

0.710 = the mean scram time used in the g

analysis.

N 0.0875 - 1.65x0.053 where 1.65 is the appropriate g

'I'g = 0. 710 + 0.0875 statistical number to provide a 95%

l, n

confidence level and, 0.053 is the N

j standard deviation of the distribution i

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for average scram insertion time to the 4

20% position, that was used in the analysis.

3.3/4.3 BASES 90 l

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4 f,

Amendnent flo. 5

3.0 LlfilTitlC CONDITIONS FOR OPERATION 4.0 SURVEILLANCE Kr,QUIREMENTS C. M.inisaum Critical Power Ratio (MCPR)

C. Minimum Cricical Power Radio (MCPR)

1. During power operation the Operating MCPR Limit shall 'be l

HCPR shall be determined. daily during reactor

> l.43 for 8x8 and 8x8R fuel, > 1.47 for P8x8R fuel at l

power operat. ion at >,25% rated thermal power rated power and flow, provided

'r', > 'l' Jk (see section and following any change in power level or 3.3.C.3).

If e' any time during operation it is distribution which has the potential of determined that the limiting value for MCPR is being bringing the core to its operating MCPR Limit, exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribed limits.

Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.

If the steady state HCPR is not returned to within the prescribed limits within two (2) hours, the reactor shall be brought to the Cold Shutdown conditivi within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

For core flows other th,an rated the Operating MCPR Limit shall be the above applicable MCPR value t*me K where g

K is as shown in Figure 3.11.3.

2. If the gross radioactivity release rate of noble gases at the steam jet air ejector monitors exceeds, for a period greater than 15 minutes, the equivalent of 216,000 uci/sec following a 30-minute decay, the Operating

!!CPR I.imit s speci f ied in 3.11.C.1 shall be adjusted to

>l.48 for all fuel types, times the apptopriate K l

Subsequent operaticnwiththeadjustedMCPRvaluek. shall be per paragraph 3.II.C.I.

• If

' I'.. > 1".

the operating MCPR Limit shall be a linear interpolation between the limits in 3.11.C.1 and 1.48 for Hn8 an.1 8x8R fuel and 1.52 for P8x8R fuel.

213 3.11/4.11 j

amendment No. 5 s

H TABLE 3.11.1 HAXIHUN AVERAGE PLANAR LINEAR llEAT GENERATION RATE vs. EXPOSURE HAPLilGR FOR EACil FUEL TYPE (kw/ft)

Exposure 1

HUD/STU 8DB262 8DB250 SDB219L 8DRB265L P8DRB265L 8DRB282 P8DRB282 P8DRB284LB 200 11.1 11.2 11.4 11.5 11.6 11.2 11.2 11.4 1,000 11.3 11.3 11.5 11.6 11.6 11.2 11.2 11.4 5,000 11.9 11.9 11.9 11.7 11.8 11.6 11.8 11.8 10,000 12.1 12.1 12.0 11.8 11.9 11.7 11.9 11.9 15,000 12.1 12.1

!!.9 11.7 11.9 11.7 11.8 11.9 20,000 12.0 11.9 11.8 11.6 11.8

!!.5

,11.7 11.7 25,000 11.6 11.5 11.3 11.3 11.3 11.3 11.3 11.4 10,000 10.3 10.6 10.2 10.3 10.5 10.4 10.7 10.6 35,000 9.3 9.3 9.3 9.2 9.5 9.2 9.5 9.5 (36,000) 9.1 9.0 9.1 l

9.0 9.3 9.0 9.3 9.3 40,000 8.9*

45,000 8.0*

50,000 7.3*

8

• 1'or extemleil bornup program test bundles 214 1.11/4.11 Amendment flo. 5

It.ine a Csuit inued Ilinimum Crit ical Power Ratio (HCPR)

C.

% e ECCS evalisation presented in Reference 4 and Reference 6 assumed the steady state MCPR prior to the'the Operat' to be 1.24 for all fuel types for normal and reduced flow.

accident By maintain-post.ulated loss-of-coolantis deterinined from the analysis of transients. discussed in Bases Sections 2.1 and 2.3.

ing an operating itCPR above these limits, the Safety Limit (T.S. 2.1.A) is maintained in the event of the flCPR 1.iinit limiting abnormal operational transient.

n.o s t to be a f actor in determining the MCPR lise of CE's new ODYN code Option B will require average scram tinue increase the operating envelope for HCPR below HCPR (ODYN code Option A), tlie cycle average scram t iene (Gar ) imust be deterinined (see Bases 3.3.C).

If q'm is below time adjusted analysis (Reference 7).

In order to L

>7,' a linear interpotution soust be used to determine the scram tiene, the MCPH 1.isait can be used.

If 3

appropriate MCPR.

For example:

'I'ui, Un IICPR = HCPR +

(MCPR -HCPRB)

'A B

0.9

'N limiting accident analyses.

and HCPR, have been determined f rom the most itCPR than rated core flow the Operating MCPR I.imit is adjusted by multiplylog the above For operation with less Reference 5 discusses how the transient analysis done at rated conditions encoinpasses time limit by K.

g factor is applied, reduced flow situation winen the proper Kg activity levels above that stated in 3.II.C.2 are indicative of fuel failure. Since the failure be posit ively identified, a enore conservative Operating HCPR Lianit must be applied to account tioble gas inode cannot for a possible fuel loading error.

nose abnorinal operat ional trans ient s, analyzed in FSAR Section 14.5, whicle result in an aut.2m.stic reactor sa: ram a re not considered a violation of the I.CO.

Exceeding MCPR limits in sucle cases need not be reported.

,21 fi

1. I I tt A:ild; Amendnent fio. 5

i 4

n.u.c n Continued lieferences

1. " Fuel Dennification Effects in General Electric Boiling Water Reactor Fuel," Supplements 6, 7.and 8, llEDH-10735, August, 1973.

2. Supplement I to Technical Report on Densification of General Elect ric Reactor Fuals, December 14, 1974 (USAEC Regulatory Staf f).

3. Communication: VA Hoore to IS liitchell, " Modified CE Hodel for Fuel Densification," Docket 50-321, Harch 27, 1974.

4. "I.oss-of moolant Accident Analysin Itepo r t for the Mont icello Huclear Generating Plant," HEDO-24050

-1, December, 1980, L 0 liayer (HSP) to Director of Huclear Reactor Regulation (USNRC),

February 6 1981.

5. " General Electric BWR Cencric Reload Application for 8x8 Fuel," NEDO-20360, Revision I, November 1974.

6. "itevision of 1.ow Core Flow Effects on LOCA Analysis for Operat ing BWR's," R L Gridley (CE) to D C Eisenhut (USNRC), September 28, 1977.

7. "itesponse to ^4C Request for Information on ODYH Computer Hode," R 11 Buchholz (CE) to P S Oseck (llSNRC), Sep' embe r 5, 1980.

it.iser. 4.1 I the Art.1;GR, l.IlGR and MCPR shall be checked daily to determine if fuel burnup, or control rod movement have caused c hanges in power distribution.

Since risangen due to burnup are slow, and only a few control rods are removed daily, a daily check of power distribution is adequate.

For a limiting value to oc.:ur below 25% of rated thermal power, an unreasonably large paaking f actor would be required, idiich is not the case for operating control rod sequences.

In level or distribut ion are made which have (lio potent ial' addition, the llCPR is checked whenever cha.nnes in the core power ul bringing the fuel rods to their thermal-hydraulic limits.

217 4.11 IlASES P

Anendment No. 5

.