ML19259D337

Amends 39 & 33 to Licenses DPR-42 & DPR-60,respectively, Adding License Conditions Re Completion of Mods & Implementation of Administrative Control

ML19259D337
Person / Time
Site:	Prairie Island
Issue date:	09/06/1979
From:	Schwencer A Office of Nuclear Reactor Regulation
To:
Shared Package
ML19259D338	List: ML19259D337 ML19259D342
References
TAC-11094, TAC-11095, NUDOCS 7910180158
Download: ML19259D337 (19)

Text

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o UN!TED STATES

[ \\ {, s. < j ',i NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 y m dg p g\\

f NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPE,aTING LICENSE Amendment No. 39 License No. DPR-42 1.

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

A.

The application for amendnent by Northern States Power Company (the licensee) dated January 31, 1977 as amended December 22, 1977, conplies with the standards ar.d requirenents of the Atonic 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 Conmission; C.

There is reasonable assurance (1) that the activities authorized by this amendnent 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 public; and E.

The issuance of this amendment is in accordance with 10 CFR ' art 51 of the Conmission's regulations and all applicable requirenents nave been satisfied.

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, Accordingly, the license is amended by adding paragraph 2.C.(4) and 2.

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. OPR-42 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 39, tre hereby incorporated in the license.

The licer.oce shall operate the facility in accordance with the Technical Specifications.

(4) Fire Protectivn The licensee may proceed with and is required to complete the modifications identified in Paragraphs 3.1.1 through 3.1.21 of the NRC's Fire Protection Safety Evaluation, dated September 6,1979 for the facility according to the schedule in Table 3.1.

If any nodifications cannot be completed on schedule the licensee shall submit a report explaining the circumstances and propose, for staff approval, a revised schedul e.

In addition, the licensee shall submit the additional informatior identified in Sections 3.1 and 3.2 of the related Safety Evaluation in accordance with the schedule contained therein.

In the event these dates for' submittal cannot be met, the licensee shall submit a report, explaining the circumstances, together with a revised schedule.

The licensee is required to develop and implement the administrat1<e controls identified in Section 6 of the related Safety Evaluat an within four months from the date of this amendment.

Paragraph 2.C.(4) is effective as of twenty days after the 3.

date of issuance of the notice of this amendment provided no hearing is requested under 10 CFR Part 2 paragraph 2.204.

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Paragraph 2.C.(2) will become effective upon date of issuance of this amendnent.

FOR THE NUCLEAR REGULATORY COMMISSION

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A. S'chwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors

Attachment:

Changes to the ".chnical Specifications Date of Issuance: September 6,1979 j

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o UNITED STATES ENf > v.

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NUCLEAR REGULATORY COMMISSION

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NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33 License No. DPR-60 1.

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

A.

The application for amendment by Northern States Power Company (the licensee) dated January 31, 1977 as amended December 22, 1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Conmission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate ir conformity with the application, the provisions of the Act, aad 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 public; and E.

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

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, 2.

Accordingly, the license is amended by adding paragraph 2.C.(4) and 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. DPR-60 is hereby amended to read a; follows:

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

33, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(4) Fire Protection The licensee may proceed with and is required to complete the modifications identified in Paragraphs 3.1.1 through 3.1.21 of the NRC's Fire Protection Safety Evaluation, dated September 6,1979 for the facility according to the schedule in Table 3.1.

If any modifications cannot be completed on schedule the licensee shall submit a report explaining the circumstances and propose, for staff approval, a revised schedul e.

In addition, the licensee shall submit the additional information identified in Sections 3.1 and 3.2 of the related Safety Evaluation in accordance with the schedule contained therein.

In the event these dates for submittal cannot be net, the licensee shall submit a report, explaining the circumstances, together with a revised schedule.

The licensee is required to develop and implement the administrative controls identified in Section 6 of the. elated Safety Evaluation within four months from the date of this amendment.

3.

Paragraph 2.C.(4) is effective as of twenty days after the date of issuance of the notice of this amendment provided no hearing is requested under 10 CFR Part 2 paragrapn 2.204.

. 4.

Paragraph 2.C.(2) will become effective upon date of issuance of this amendnent.

FOR THE NUCLEAR REGULATORY COMMISSION kLdBldOU A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors

Attachment:

Changes to the Tec'inical Specifications Date of Issuance: September 6,1979 jj e

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i ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 39 TO FACILITY OPERATING LICENSE NO. DPR-42 AMENDMENT N0. 33 TO FACILITY OPERATING LICENSE NO. DPR-60 DOCKET NOS. 50-282 AND 50-306 Revise Appendix A as follows:

Insert Pages 1emove Pages 1-6 1-6 2.3-1 2.3-1 Table TS 4.4-1 (1 of 5)

Table TS 4.4-1 (1 of 5)

Table TS 4.4-1 (2 of 5)

Table TS 4.4-1 (2 of 5)

Table TS 4.4-1 (3 of 5)

Table TS 4,4-1 (3 of 5)

Table TS 4.4-1 (4 of 5)

Table TS 4.4-1 (4 of 5)

Table TS 4.4-1 (4 of 4)

Table TS 4.4-1 (5 of 5) 4.16-1 4.16-1 4.16-2 4.16-2 6.1-1 5.1-1 Figure TS 6.1-1 Figure TS 6.1-1 Figure TS 6.1-2 Figure TS 6.1-2 1}

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TS.1-6 3.

Refueling Shutdown A reactor is in the ref ueling shutdown condition when a refueling operation is scheduled, the reactor is suberitical by at least 10% ti k/k and the reactor coolant everage temperature is less than 140 F.

Q.

Thermal Power Thermal power of a unit is the total heat transferred from the reaccor core to the coolant.

R.

Physics Tests Physics tests are those conducted to measure fundamental character-istics of the core and related int umentation. Physics tests are conducted such that the core power _s sufficiently reduced to allow for the perturbation due to the test snd therefore avoid exceeding power distribution limits in Specification 3 10.B.

Low power physics tests are run at reactor powers less than 5% of rated power.

S.

Startup Operation The process of heating up a reactor above 200 F, making it critical, and bringing it up to power operation.

T.

Fire Suppression Water System The fire suppression water system consists of : Water sources; pumps; and diotribution piping with associated sectionalizing isolation valves.

Such valves include yard hydrant s alves, and the first valve ahead of the water flow c? arm device on each sprinkler, hose standpipe, o spray system riser.

U.

Minimum Pressurization Temperature (MPT) l Reactor coolant system temperature below which reactor coolant system pressure is limited by Figures TS.3.1-1 and IS.3.1-2, Reactor Coolant System Heatup and Cooldown Limitations.

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J Amendment No. 39, Unit 1 Amendment No. 33, Unit 2

TS.2 3-1 i

2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE lilSTRUMENTATION Applicability Applies to trip settings for instruments monitoring reactor power and reactor coolant pressure, temperature, flow, and pressurizer level.

Objective To provide for automatic protective action in the event that the principal process variables approach a safety limit.

Specification A.

Protective instrumentation settings for reactor trip shall be as follows:

1.

Startup protection a.

High flux, intermediate range (high set point) -

current equivalent to 140% of full power.

b.

High flux, power range (low set point) -

<25% of rated power.

c.

High flux, sourcg range -

neutron flux 110 counts /second 2.

Core protection a.

High flux, power range (high set point) -

1108% of rated power.

b.

High pressurizer pressure - 12385 psig.

c.

Low pressurizer pressure - 21815 psig.

d.

Overtemperature 21T (1+ty ) + K (P-P - f (AI)]

s y

2 (T-T')

y, 3

as T Sj&T,

[K

-K where Indicated A T at rated power LI

=

Average temperature, F

T

=

T' 567.3 F

=

Pressurizer pressure, psig P

=

P' psig 2235

=

K i 1.11 y

/

'i1 0.0090 K

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=

2 1

0.000566 I

v K

=

3 20 see t

=

y t2 4 see

=

Amendment No. 39, Unit 1 Amendment No. 33, Unit 2

TABLE TS.4.1-1 (Page 1 of 5)

MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND

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TEST OF INSTRUMENT CHANNE' }

Channel Functional

Response

Descriition Check Calibrate Test Test Remarks

1) Once/shif t when in service

1. Nuclear Power S(1)

D(2)

M(3)

R

2) Heat balance Range M(4)

Q(4)

M(5)

3) Signal to AT; bistable action M(6)

(pe rmiss ive, rod stop, trips),

P( 7) with the exception of the items covered in Remark #7.

4) Upper and lower chambers for axial off-set using in-core detectors

5) Simulated signal for testing positive and negative rate bistable action

6) Quadrant Power Tilt Monitor

7) P8 and P10 permissives and the 25% High Flux Low Setpoint Trip.

2. Nuclear Inter-

• S(1)

NA T(2)

R

1) Once/shif t when in service mediate Range

2) Log Level; bistable action (permissive, rod stop, trips)

3. Nuclear Source

• S(1)

NA T(2)

R

1) Once/shif t when in service Range

2) Eistable action (alarw, crips)

4. Reactor Coolant

• S(1,2)

R(1,2,3)

M(1)

R(1)

1) Overtemperature AT Temperature M(2)

R(2)

2) Ove rpower as T T(3)

3) Control Rod Bank Insertion Limit Monitor

5. Reactor Coolant S

R M

NA Flow

6. Pressurizer S

R M

NA Water Level

7. Pressurizer S

R M

NA Pressure s

c.

Amendment No. 39, Unit 1 Amendment No. 33, Unit 2

TABLE TS.4.1-1 (Page 2 of 5)

MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CilANNELS Channel Functional

Response

l Description Check Calibrate Test Test Remarks 8.

4KV Voltage &

NA R

M NA Reactor protection circuits only Frequency 8a. RCP Breakers NA R

T NA 9.

Analog P.od S(1)

R T(2)

NA

1) With step counters Pos it ion M(2)

2) Rod Position Deviation Monitor Tested by updating computer bank count and comparing with analog rod position test signsi L.

C-Amendment No. 39, Unit 1 Amendment No. 32, Unit 2

TABLE TS.4.1-1 (Page 3 of 5)

Channel Functional Response l

Description Check Chlibrate Test st Remarks

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10.

Rod Position Bank S(1,2)

NA T(3)

NA

1) With analog rod position Counters M(3)

2) Following rod motion in excess of six inches when the computer is out of service

3) Control rod banks insertion limit monitor and control rod position deviation monitors 11.

Steam Generator Level S

R M

NA 12.

Steam Generator Flow S

R H

NA Mismatch 13.

Charging Flov S

R NA NA 14.

Res idua l llea t S(l)

R NA NA

1) When in ope'ation Removal Pump Flow 15.

Boric A?id Tank Level D

R(1)

M(1)

NA

1) Transfer logic to Refueling Water Storage Tank 16.

Refueling Water W

R M(1)

N/

1) runctional test can be performed Storage Tank Level by bleeding transmitter 17.

Volume Control Tank S

R NA NA Level 18a. Containment Pressure S

R M(1)

NA Wide Range Co :.ainment Pressure SI Signal

1) Isolation Valve Signal 18b. Containment Pressure S

R M

NA Narrow Range Containment Ptsssure Steam Line Isolation s s t 7 18c. Containment Pressure S

R M

NA Containment Spray 18d. Annulus Pressure NA R

R NA l

(Vacuum Breaker)

Amendment No. 39, Unit 1 Amendment No. 33, Unit 2

TABLE TS.4.1-1 (Page 4 of 5)

Channel Functional Response l

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Description Check Calibrate Test Test Remarks

• 19. Radiation Monitoring

• D R

M NA Includes all channels used for leak detection per Spec. 3 1 D. and effluent release monitoring per Spec. 3.9 and 5.5.

20. Boric Acid Make-up Flow NA R

NA NA Channel

21. Containment Sump Level NA R

R NA Includes Sumps A, B, and C

22. Accumulator Level S

R R

.NA and Pressure

23. Steam Generator Pressure S R

M NA

24. Turbine First Stage S

R M

NA Pressure

25. Fmergency Plan

• M R

M NA Includes those named in the emergency Radiation Inst.uments procedure (referenced in Spec.

6.5 A.6)

26. Protection Systems NA NA M

NA Includes auto load sequencers Logic Channel Testing

27. Turblu Overspeed NA R

M NA Protection Trip Channel

28. Containment Shell M

NA NA NA Includes those used per Spec. 3.6 D.

Temperature

29. Containment Air M

NA NA NA Includes those used per Spec. 3 6 C.

Temperature

30. Environmental Monitors M

NA NA NA Includes those used per Spec. 4.10

31. Seismic Monitors R

R NA NA Includes those r ported in Item 4 of Table TS.6.7-1

32. Coolant Flow-RTD S

R M

NA s

Bypass Flowmeter

33. CRDM. Cooling Shroud S

NA R

NA FSAR page 3.2-56

'I Exhaust Air Temperature ca

34. Reactor Gap Exhaust S

NA R

NA FSAR page 5.4-2 Air Temperature Amendment No. 39, Unit 1 Amendment No. 33, Unit 2

TABLE TS.4.1-1 l

(Page 5 of 5)

Chann-1 Functional Response Description Cheel.

Calibrate Test Test Remarks 35 Post-Accident Monitoring M

NA NA NA Includes all those in FSAR Instruments Table 7.7-2 that are not itemized in Table TS.4.1-1.

36.

Steam Exclusion W

R H

NA See FSAR Appendix I, Actuation System Section 1.14.6.

37.

Overpressure NA R

M NA Mitigation System Each Shif t S

Daily D

Weekly W

4anthly M

Quarterly Q

Each refueling shutdown R

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P Prior to each startup if not done previous week T

Prior to each tartup following snutdown in excess of 2 days if not done in the presious 30 days s

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NA Not applicable

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See Spec 4.1.D Amendment No. 39, Unit 1 Amendment No. 33, Unit 2

TS.4.16-1 4.16 FIRE DETECTION AND PRC'IECTION SYSTEMS Aoplicability_

Applies in the periedic testing of Lastrumentation and plant systems used for fire detection and protection of the nuclear safety related structures, systems, and components.

Objective To verify the operability of instrumentation and plant systems used for fire detection and protection of nuclear safety -elated structures, systems and components.

Specification A.

Fire Detection Instrumentation 1.

The minimum number of fire detectors required in each zone specified in Table TS.2.14-1 shall be functionally tested once eeery six months.

The ninimum number of fire detectors recuired in areas which are inaccessible during operation shell be functionally tested during each cold shutdown exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed during the previous six months, however, the outage need not be extended solely for completion of these tests.

2.

The alarm circuit for the detectors required in each, zone specified in Table TS.3.14-1 shall be tested every six months.

B.

_ Fire Sucoression Water System 1.

The system shall be verified operable as follows:

Operability of the diesel-driven fire pu=p starting battery a.

shall be demonstrated by:

1.

Once each week verify electrolyte level and voltage is within specifica:icns.

2.

Once every three months verify the specific gravity of each cell is withi; specifications.

3.

Once every la cnt' inspect the batteries, battery racks, and elo :rie 1 connections for damage or abnormal deter;orat.cn.

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Amendment No. 39, Unit 1 Amendment No 33, Unit 2

TS.4.16-2 b.

The motor-driven fire pump shall be started every month and run for at least 15 minutes on recirculation flow.

The diesel-driven fire pump shall be started every month c.

from ambient conditions and run for at least 20 minutes on recirculation flow.

d.

The level in the df esel-driven fire pump fuel storage tank shall be checked every month and verified to contain at least 500 gallons of fuel.

Every three months verify that a sample of fuel from the e.

diesel-driven fire pump fuel storage tank is within the acceptable itsits specified in Table 1 of ASTM D975-68 when checked for viscosity, water and sediment, f.

Every 18 months subject the diesel-driven fire pu=p engine to an inspection in accordance with procedures prepared in conjunction with the manufacturer's recommendations for this class of standby service, A simulated automatic actuation of each fire pump and the g.

screen wash pu=p, including verification of pump tapability, shall be conducted every 18 months.

h.

The header syster shall be flushed every 12 nonths.

1.

System flow tests shall be performed every three years,

j. Valves in flow pnias supplying fire suppression water to safety related strue:ures, systems, and components shall be cycled every 12 months.

k.

Each valve (manual, power operated, or automatic) in the flow path which is for safety-related areas and areas posing a fire hazard to safety-related areas, shall be verified to be in its correct position every month and the method of securing the valve in its correct position is functional shall be verified every month.

2.

When it is determined that ae of the two pumps required by specification 3.14.B.l.a is inoperable, the remaining operable pump shall be started daily and run for at least 15 minutes on recirculation flow until specification 3.14.B.1.a can be met.

Amendment No. 39, Unit 1 Amendacnt No. 33, Unit 2 33 i

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TS 6.1-1 6.0 ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION A.

The Plant Manager has the overall full-time onsite re-sponsibility for safe operation of the facility.

During periods when the Plant Manager is unavailable, he may delegate this responsibility to ether qualified super-visory personnel.

B.

The Northern States Power corporate organizational structure relating to the operation of this plant is shown in Figure TS.6.1-1.

C.

Th'e funccional organization for operation of the plant shall be as shown in Fig e TS.6.1-2 and :

1.

Each on duty shal? be co= posed of at least the minirum shift crew composition shown in Table TS.6.1-1.

2.

For each reactor that contains fuel:

a licensed operator in the control room.

3.

At least two licensed operators shall be preser' n the control room during a reactor startup, a scheduled reactor shutdown, and during recovery from a reactor tri7-These operators are in addition to those required for the ciher reactor.

4.

An individual qualified in radiation protection procedures shall be on site when fuel is in a reactor.

5.

All refueling operations shall be directly supervised by a licensed Senior Reactor Operator ot Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

6.

A fire brigade of at least five members shall be maintained on site at all times.*

The fire brigade shall not include the sf members of the minimun shift crew for safe shutdown of the reactors.

• Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of Fire Brigade members provided immediation action is taken to restore the Fire Brigade to within the minimum requirements.

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u Amendment No. 39, Unit 1 Amendment No. 37., linit 2

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Figure TS 6.1-1 t

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VICE PRESIDENT

• 5 VICE PRESILENT-VI.CE H..; DEST-R M O M ION 6 PIANT ENGINEERING WST OE W ION AND CONSTRUCTION I

i l'N hGER OF GESGAL FANAGER OF NUCLEAR SUPPORT SERVICES fGIER PRODUCTION I

SAC Administration i

1 GENERAL SUPERIbiENDENT NUCLEAR POL *ER PLAhT OPERATION SAFETY AUDIT CCHMITTEE (SAC)

.."1t3Ryiew A

PRAIRIE ISIAND FIGCL t.1 -1 NCP CCRP: W JCAN!ZATIONAL RELATIONSHI P O ON '.

GIMATIM OMNJI2ATTON j'/

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• Has the responsibility for the fire protection prc; ram.

Amendment No. 39, Unit 1 Amendment No. 33, Unit 2

PIAll2 MANAGElt*

OPERATIOIU COFHITTEE I

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, -. _ _ _ _ _ _ _ _ _ Rey i_eg &, A_ tuli t, _ _ _ _

SUPERIIffENDEfff-SUPERIffI'ENDEfff-OPHIATIONS &

PIAfff ENGINEERUlG &

MAnffENANCE * +

RADIATI0ti PROTECPION* (ISP)

QUALITY SL'P7EISOR OF ENGINEER 5 SECUF. TY & SI:"/ ICES I

I I

E I

MAIhTU!iANCE OPDMTIO!ci TRAI! LING RADIATION FIAITP PIA TP PLAITP SUPDWISOR*

SUPD UIS0!t" SUPDUISOlt PROTECTION EGIliE21 EilGINEER DGINPZR SUPERVISOR '

TE~'INICAL

• GPERATIO!G *

ffT.JJ.F. *

(1 ;0)

OPERA. TOR AND m

g, FIRE BRIGADE SilIFT SUPEii-TRAItilNG VlmH (IfiO)

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MEClfARICAL IJAD PIA!!r EQUIP-TECHNICAL TICIUiICAL TECHNICAL IE~ENICAL stErtl' & RKACPOR SUPPORT &

SUPPORT &

SUPPCRT &

SUPPORT &

ELECTItICAL JPERA10R (ID)

TECHNICIANS EGU{EERS F0h DIGIIEERS FOR DGINEZRS MAU(rELANCE FOR RADIATION I:ETRUMEffrS, OPERATION, POR !PJCIJA GROUP PIANT EQUIPMDir PROTECTION &

C0:lfROIS, &

MA UTPE!!ANCE, I:gn m Un

& REACIOR CIIHIISTRY I2/PUTER; SURVEILIAf;CE, N

OPERATOR (S) ( LOh I::STRUMEttr &

& TfsTIIC O

h

'!2:Tr30IS SPEC ASSISTAITP PIAIif

.N EQUIINETF OPERATOR ( S)

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AND PRAIRIE ISIA iD UUCIEAR GEliERATU;G PJLYr 7

M

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PIAlif ATTENDAITIS FUNCTIOI;AL DRSAHL~ATI0II FOR ON-SITE OPERATU;G GRJJP FIRE BRICADE (AS REQUIRED)

Key Strpez.-isor c_

LO Licer.E ei. ceratar 3

,i LSO Licer.sei Eenior Operator L

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lias responsibility for iraplementation of the iire protection progran Amendment No. 39, Unit 1 Amendment No. 33, Unit 2