ML20202C249

Forwards Model Tech Spec Pages Re Inadequate Core Cooling Instrumentation in Response to Generic Ltr 82-28.Pages Inadvertently Omitted from 860508 Safety Evaluation

ML20202C249
Person / Time
Site:	Prairie Island
Issue date:	06/30/1986
From:	Diianni D Office of Nuclear Reactor Regulation
To:	Musolf D NORTHERN STATES POWER CO.
References
GL-82-28, GL-83-37, NUDOCS 8607110174
Download: ML20202C249 (7)

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Docket Nos. 50-282/306 3 0W Mr. D. M. Musolf, Manager Nuclear Support Services Northern States Power Company 414 Nicollet Mall Midland Square, 4th Floor Minneapolis, Minnesota 55401

Dear Mr. Musolf:

On May 8, 1986, the Commission issued a Safety Evaluation (SE) completing the review of your responses to Generic Letter (GL) 82-28 dealing with the inadequate core cooling (ICC) instrumentation system for Prairie Island Nuclear Generating Plan Unit Nos. I and 2. The model technical specifications which were found acceptable in meeting the generic requirements of GL-83-37 and the standard technical specifications were inadvertently not attached to the SE.

Enclosed are the model technical specifications pages. We regret any inconvenience caused by this error.

Sincerely,

/

/s Dominic . Dilanni, Project Manager Project Directorate #1 Division of PWR Licensing-A

Enclosures:

As Stated cc's: See Next Page Office: LA/ PAD #1 PM/ PAD #1 N h Surname: PShuttle DDilanni/tg Date: 06/Jo/86 06/30/86 8607110174 860630 PDR ADOCK 05000282 P PDR

Distrbution Copies:

Docket File 50-282/306 NRC PDR Local POR PAD #1 r/f PAD #1 p/f TNovak, Actg Div Dir Glear DDilanni PShuttleworth NThompson, DHFT ELD x^

LHarmon EJordan BGrimes JPartlow EButcher, TSCB TBarnhart (4)

WJenes F0B, DPLA Tech Branch that had input in package ACRS (10)

OPA LFMB (w/cy of TAC w/Amd No. & date issued) 3 . %. ,___ ,.. ..- . -

~..__ c. ,,- _ , , . - . , _ - - .m.. , , ,

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Mr. D. M. Musolf Prairie Island Nuclear Generating Northern States Power Company Plant cc:

Gerald Charnoff, Esq.

Shaw, Pittman, Potts and Trowbridge 1800 M Street, NW Washington, DC 20036 Executive Director Minnesota Pollution Control Agency 1935 W. County Road, B2 Roseville, Minnesota 55113 Mr. E. L. Watzl, Plant Manager Prairie Island Nuclear Generating Plant Northern States Power Company Route 2 Welch, Minnesota 55089 .

Jocelyn F. Olson, Esq.

Special Assistant Attorney General Minnesota Pollution Control Agency 1935 W. County Road, B2 Roseville, Minnesota 55113 U.S. Nuclear Regulatory Commission Resident Inspector's Office Route #2, Box 500A Welch, Minnesota 55089 Regional Administrator, Region III U.S. Nuclear Regulatory Comission Office of Executive Director for Operations 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. William Miller, Auditor Goodhue County Courthouse Red Wing, Minnesota 55066

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. TS.3.15-2 Y . .

C. Specification - Reactor Vessel Level Instrumentation

1. The reactor vessel level instrumentation channels specified in Table TS.3.15-3 shall be operable.

2. With the number of Operable reactor vessel level. instrumentation channels less than the Required Total Number of Channels shown on Table TS.3.15-3, either restore the inoperable channels to Operable status within -fourteen days, or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3. With the number of Operable reactor vessel level instrumentation channels less than the Minimum Channels Operable requirements of Table TS.3.15-3, either restore the minimum number of channels to Operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Basis The operability of the event monitoring instrumentation ensures that sufficient information is available on selected pl:ent parameters to monitor and assess these variables durfag and following sn accident. This capability is consistent with the recommendations of NUREG-0578, "21I-2 Lassons Learned Task Force Status Report and Short Tara Recommendatidas." -

Core exit thermocouple readings necessary to meet the requirements of Specification 3.15.A are available from the Plant Process Computer', the Control Room Core Exig Thermocouple Display or if no other readout is available, from test equipment readings from the Core Exit Thermocouple Junction Bcxes.

MODEL TECHNICAL SPECIFICATION A =

j TABI.E TS.3.15-1 EVENT HDNITORINC INSTRUMENTATION - PROCESS & CONTAINNENT

. Required Total No. Minimum Channels Instrument of channela Operable i .

1. Pressurizer Wa ter Level 2 1 l

l 2. Auxillary FeeJuster Flow to Steam Generators 2/ steam gen 1/ steam gen j (One Chansiel Flow and One Channel Wide Range

Levet for Eacle Steam Cenerator)

I

3. Reactor Coolant System Subcooling Margin 2 1

! ]

) 4. Pressurizer Power Operated Relief Valve Position 2/ valve 1/ valve

(One Common Channel Temperature, One Channel i 1.imit Switch per Valve, and One Cliannel Acoustic Sensor per Valve *)

, 5. Pressurizer Power Operated Relief Block Valve Position 2/ valve 1/ valve (Dise Common Channel Temperature. One Channel Limit Switch per Valve, and one Channel Acoustic Sensor

per Valve *)

j 6. Prescurizer S'afety Valve Position 2/ valve 1/ valve (one Cleasinet Temperature per Valve and Comunon Acoustic Sensor **) ,

j 7. a. Containment Water f.evel (wide range) 2 1 j b. Containmeist Water Level (narrow range) 2 1

8. Containment flydrogen Monitor (2 sensors per Channel), 2 1 1

9. Containment Pressure (wide range) 2 'l *

10. Core Exit Thermocouples 4/ core quadrant 2/ core quadrant lg

<r 4

Pt

- A common acoustic sensor provides backup position indication for eacle pressurizer power operated d 4

relief valve and its associated block valve.

• u

• • - The acoustic sensor channel la common to botli valves. When operable, tise acoustic sensor may be f considered as an cperable channel for each valve. -

i MODEL TECHNICAL SPECIFICATION a

Table TS.3.15-3 ,

EVENT MONITORING INSTRUMENTATION - REACTOR VESSEL LEVEL

• Instrument - Required Total No. Minimum Channels of Channels Operable .

2 1

1. Reactor Vessel Level Instrumentation

• I i

• Includes the full range and dynamic head range a b

N t!

L, m

j

MODEL TECHNICAL SPECIFICATION

-" ^

Tchla Ts.4.1-1 .

(Page 4 of 5) .

Channel Functional Response Description check

• Calibrate Test Test Remarks .

27. Turbine Overspeed NA R H NA Protection Trip Channel

.' 28. Deleted

29. Deleted

30. Deleted i

31. Seismic Monitors R -R NA NA

32. Coolant Flow - RTD S R H NA Bypass Flowmeter

33. CkpH Cooling Shroud S NA' R NA FSAR page 3.2-56

34. Hesctor Cap Exhaust Air S NA R NA Temperature

.  ?

35a. Post-Accident Honitoring H R NA NA Includes all those in Table j instruments TS.3.15-1 (except for contain-ment hydrogen monitors which are separately specified in

,I this table)

b. Post-Accident Honitoring D R H NA Includes all those in Table Radiation Instruments TS.3.15-2

c. Post-Accident Monitoring H R NA NA Includes all those in Table g Reactor Vessel Level' TS.3.15-3 h ,;,8 g j Instrumentation ,

y g' cy

36. Steam Exclusion Actuation W Y H NA See FSAR Appendix I, Section E*,

• System I.14.6 i v, ,,

s-

37. Overpreesure Hitigation NA R R NA Instrument Channels for PORV Control including overpressure l System' l

Hitigation System

38. Begraded Voltage NA R H NA 4 KV 3sfeguard Russes

39. Loss of Voltage NA R H HA

4 KV Safegaard Russes

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