ML20214C269

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Forwards Facility Final Draft Spec Table of Contents Designating Responsible Technical Review Branch.Tech Specs Upgrade Program Includes Schedule for Completion & Listing of Assigned Reviewers
ML20214C269
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 02/14/1986
From: Calvo J
Office of Nuclear Reactor Regulation
To: Parr O
Office of Nuclear Reactor Regulation
References
NUDOCS 8602210074
Download: ML20214C269 (9)
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Text

FEB 141986 NOTE T0: 0. Parr, Chief, Plant, Electrical, Instrumentation and Control

- ' Systems Branch, Division of PWR Licensing-B FROM: J. Calvo, Section Leader, Section A, Plant, Electrical, Instrumentation and Control Systems Branch ,

SUBJECT:

FORT ST. VRAIN (FSV) TECHNICAL SPECIFICATIONS UPGRADE PROGRAM (TSUP)

In reference to D. Crutchfield's memorandum dated February 7,1986, the PEICSB was requested to provide comments by February 21, 1986, on the assigned areas of review of the FSV TSUP including a schedule for completion and a listing of the assigned reviewer (s).

The enclosure is the FSV final draft specification Table of Contents des.ignating the responsible technical review branch within PWR-B. Certain sections have either been reviewed by the assigned F08 reviewer or are currently being reviewed by supporting contractors.

During a meeting with G. Plumlee of the F0B on February 12, 1986, it was agreed upon that the PEICSB would perform a complete review of Section 3/4.8 (Auxiliary Electric Power Systems) and an oversight review of the remaining sections assigned to the PEICSB. As indicated in the enclosure, the PEICSB reviewers will be Iqbal Ahmed and Norm Wagner for Sections A and B, respectively.

With regard to the schedule for completion, FSV TSUP Specification 3/4.8 final staff comments will be provided to the FSV TSUP coordinator, G. L.

Plumlee, III by February 22, 1986. Final staff coments on the balance of the FSV TSUP Specification Sections assigned to the PEICSB for oversight review will be provided to the FSV TSUP . coordinator by June 30, 1986.

Should you have any cues ions, please contact the FSV TSUP PEICSB coordinator, P. Shemanski, at extension 24607.

is!

J. Calvo, Section Leader Section A Plant, Electrical, Instrumentation and Control Systems Branch Division of PWR Licensing-B

Enclosure:

As Stated cc w/ enclosure: Distribution J. Wermiel Decket File PEICSB Rdg. File I. Ahmed JCalvo PShemanski N. Wagner Contact

  • P.Shem$nski,X24607 g22gg p

gg4 267 PM -

PEICSB D N h PEICSB PShemanski:as JCalvo / K 2//4/86 2/ /p/86

F,p* **%q'o~g UNITED STATES

! o NUCLEAR REGULATORY COMMISSION h WASHINGTON. D. C. 20555

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  • FEB 141986 NOTE T0: 0. Parr, Chief, Plant, Electrical, Instrumentation and Control Systems Branch, Division of PWR Licensing-B~

FROM: J. Calvo, Section Leader, Section A, Plant, Electrical, Instrumentation and Control Systems Branch

SUBJECT:

FORT ST. VRAIN (FSV) TECHNICAL SPECIFICATIONS UPGRADE PROGRAM (TSUP)

In reference to D. Crutchfield's memorandum dated February 7,1986, the PEICSB was requested to provide coments by February 21, 1986, on the assigned areas of review of the FSV TSUP including a schedule for completion and a listing of the assigned reviewer (s).

The enclosure is the FSV final draft specification Table of Contents designating the responsible technical review branch within PWR-B. Certain sections have either been reviewed by the assigned F0B reviewer or are currently being reviewed by supporting contractors.

During a meeting with G. Plumlee of the F0B on February 12, 1986, it was agreed upon that the PEICSB would perform a complete review of Section 3/4.8 (Auxiliary Electric Power Systems) and an oversight review of the remaining sections assigned to the PEICSB. As indicated in the enclosure, the PEICSB reviewers will,.be Iqbal Ahmed and Norm Wagner for Sections A and B, respectively.-

With regard to the schedule for completion, FSV TSUP Specification 3/4.8 final staff coments will be provided to the FSV TSUP coordinator, G. L.

Plumlee, III by February 28, 1986. Final staff comments on the balance of the FSV TSUP Specification Sections assigned to the PEICSB for oversight review will be provided to the FSV TSUP coordinator by June 30, 1986.

Should you have any questions, please contact the FSV TSUP PEICSB coordinator, P. Shemanski, at extension 24607.

P d. [cI'V J. Calvo, Section Leader Section A Plant, Electrical, Instrumentation and Control Systems Branch Division of PWR Licensing-B

Enclosure:

As Stated cc w/ enclosure:

J. Wermiel I. Ahmed  !

j N. Wagner Ccntact:

P. Shemanski, X24607  !

i 1

l FORT ST. VRAIN NUCLEAR GENERATING STATION

^'# # '" # A

, , , UPGRADE TECHNICAL SPECIFICATIONS NOV 3 0 25 TABLE OF CONTENTS Rev;< s Braxk (s)

SECTION DESCRIPTION PAGE 4 INTRODUCTION IEICf6 B 1.0 DEFINITIONS 1-1 E 8 /A5 d / ErcsB 2.0 SAFETY LIMITS and LIMITING SAFETY SYSTEM SETTINGS 2.1 Safety Limits 2.1.1 Reactor Core Safety Limit 2-1 68/#38 PEICgg g4 2.1.2 Reactor Vessel Pressure 2-7 R.s B 2.2 Limiting Safety System Settings 2.2.1 Trip Setpoints 2-9 EE/#ss / EIts_d_

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS et 3/4.0 APPLICABILITY 3/4 0-1 f_U V.'

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 Control Rod Pair Operability 3/4 1-1 IS 3/4.1.2 Control Rod Pair Position Indication Systems E E I CI A(( 3/4.1.2.1 Control Rod Pair Position 3/4 1-9 E8 /EJcss Indication Systems-Operating Q E.lcs A(( 3/4.1.2.2 Control Rod Pair Position 3/4 1-16 . f8.2.fres B Indication Systems-Shutdown 3/4.1.3 Shutdown Margin 3/4 1-20 _.. 458 3/4.1.4 Control Rod Worth and Position Requirements 3/4.1.4.1 Coritrol Rod Worth and Position 3/4 1 RSB Re-3/4.1.4.2 Con'quirements-Operating trol Rod Worth and Position 3/4 1 ##8

' Requirements-Shutdown 3/4.1.5 Reactivity Change with 3/4 1-36 Rf4 Temperature 3/4.1.6 Reserve Shutdown System 3/4 1-39 - RS8 3/4.1.7 Reactivity Status 3/4 1-45 #38 f Nog.h wgs,JEjt n h ~.LQSAL AB ME.9

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

. 2 DRAFT NOV 3 01985 SECTION DESCRIPTION PAGE 3/4.2 '

CORE IRRADIATION, TEMPERATURE

- AND FLOW LIMITS .

3/4.2.1 Core Irradiation 3/4 2-1 R5 8 3/4.2.2 Core Inlet Orifice Valves / 3/4 2-3 R5_8 Region Outlet Temperature Limits 3/4.2.3 Core Inlet Orifice Valves / 3/4 2-8 RSS Comparison Regions 3/4.2.4 Core Inlet Orifice Valves / 3/4 2-12 RSB Minimum Helium Flow and Core Region Temperature Rise 3/4.2.5 Region Constraint Devices 3/4 2-20 8S8 3/4.2.6 Power-to-Flow Ratio 3/4 2-22 RJB 3/4.3 INSTRUMENTATION P E T.C r A 3/4.3.1 Plant Protective System 3/4 3-1_fB /RsB/EJc5A YNS A u 3/4.3.2 Monitoring Instrumentation e Analytical Moisture Monitors 3/4 3-70 _LB/Eftfg__,

f act A ** 3/4.3.2.1 3/4.3.2.2 Radiation Monitoring 3/4 3-73 ____ I I cA A Instrumentation 3/4.3.2.3 Seismic Instrumentation 3/4 3-80 _ 1 8 3/4.3.2.4 Meteorological Instru- 3/4 3-84 Asa y mentation 9Eict A 3/4.3.2.5 Fire Detection and Alarm 3/4 3 E tc.s 4 ti System 9CICS 8 3/4.3.2.6 Chlorine Detection and Alarm 3/4 3-93 ErtrS System i 3/4.3.2.7 Power-to-Flow Ratio Instru- 3/4 3-95 ._..AJ S mentation System i 3/4.3.2.8 Core Region Outlet Thermocouples 3/4 3-98 RSS PE.T.Cr 3/4.3.3 Three Room Control Complex 3/4 3-102 EIc3 8 Temperature Monitoring D 19BAL A)tggQ l

DRAFT  ;

l

. SECTION DESCRIPTION PAGE  ;

NOV 3'O 885 I

3/4.4 PRIMARY COOLANT .

3/4.4.1 Primary Coolant Activity 3/4 4-1 #38 1

3/4.4.2 Primary Coolant Impurity Levels- 3/4 4-8 #58 High Terrperature 3/4.4.3 Primary Coolant Impurity Levels- 3/4 4-12 A 1 6- _

Low Temperature 3/4.5 SAFE SHUTDOWN COOLING SYSTEMS 3/4.5.1 Helium Circulators 3/4.5.1.1 Helium Circulators-Operating 3/4 5-1 E6 //ss 3/4.5.1.2 Helium Circulators-Shutdown 3/4 5-8 _ EB / ** 8 -

3/4.5.2 Steam Generators 3/4.5.2.1 Steam Generators - Power 3/4 5-13 _ Ed /fs B and Low Power 3/4.5.2.2 Steam Generators - Startup 3/4 5-18 (8/4sd

,m 3/4.5.2.3 Steam Generators - Shutdown 3/4 5-20 _I4/#56

) and Refueling 3/4.5.3 Emergency Condensate and Emergency Feedwater Headers 3/4.5.3.1 Emergency Condensate and Emergency 3/4 5-26 #44 .-

Feedwater Headers-Operating 3/4.5.3.2 Emergency Condensate and Emergency 3/4 5-27 .. #s B YEICf Bg Feedwater Headers - Shutdown 3/4.5.4 Safe Shutdown Cooling Water 3/4 5-29 E B /EJc3 B Supply System 3/4.6 PCRV AND CONFINEMENT SYSTEMS 3/4.6.1 PCRV Pressurization 3/4.6.1.1 PCRV Safety Valves 3/4 6-1 RS.6 3/4.6.1.2 Steam Generator / 3/4 6-5 E8 /Esa Circulator Penetration

. Overpressure Protection 3/4.6.1.3 Interspace Minimum Pressurization 3/4 6-8 N'8 3/4.6.1.4 PCRV Closure Leakage -

MCS Bg 3/4.6.1.5 Steam Generator Interspace 3/4 6-11 3/4 6-15 RJJ IIc3B Radiation Monitoring 1 Nof.K W AG ksEA

DRAFT

' 4 NOV 3 0 1l85 SFLTION DESCRIPTION PAGE 3/4.6.2 ~

Reactor Plant Cooling Water / --

- ~

PCRV Liner Cooling System YE'LCf 6( _3/4.6.2.1 Reactor Plant Cooling Water / 3/4 6-18 R58/EJcs 8 PCRV Liner Cooling System-Operating YETCf 6g 3/4.6.2.2 Reactor Plant Cooling Water / 3/4 6-21 JLsa /EJcJR PCRV Liner Cooling System-Shutdown Y6TCf Bi 3/4.6.3 Reactor Plant Cooling Water / 3/4 6-24 ##IIIJIeJA_

PCRV Liner Cooling System Temperatures 3/4.6.4 PCRV Integrity 3/4 6-27 _ EB.

3/4.6.5 Reactor Building Confinement 3/4.6.5.1 Reactor Building Confinement 3/4 6-42 EB V61CS B 3/4.6.5.2 R tr ilding Exhaust 3/4 6-45 EJc3B System 3/4.6.5.3 Reactor Building Over- 3/4 6-50 fB Pressure Protection System 3/4.7 PLANT and SAFE SHUTDOWN COOLING SUPPORT SYSTEMS rh

!  % 3/4.7.1 Turbine Cycle bW b 3/4.7.1.1 Boiler Feed Pumps 3/4 7-1 f.rcrB 3/4.7.1.2 Steam / Water Dump System 3/4 7-4 Ircs s 3/4.7.1.3 Pressure Relief Valves 3/4 7-8 rres_A 3/4:7.1.4 Secondary Coolant Activity 3/4 7-10 _..EJcJ B 3/4.7.2 Hydraulic Power System 3/4 7-12 frc3 A 3/4.7.3 Instrument Air System 3/4 7-16 fresJ 3/4.7.4 Service Water System 3/4.7.4.1 Service Water System - Operating 3/4 7-18 IIt.r8 3/4.7.4.2 Service Water System - Shutdown 3/4 7-21 tress 3/4.7.5 Primary Coolant Depressurization 3/4 7-25 E res E 3/4.7.6 Fire Suppression Systems 3/4.7.6.1 Spray and/or Sprinkler 3/4 7-29 #Ieda Systems 3/4.7.6.2 Carbon Dioxide Systems 3/4 7-33 IJcr4 3/4.7.6.3 Halon Systems 3/4 7-35 F rs2 A 3/4.7.6.4 Fire Hose Stations 3/4 7-38 If " 8 3/4.7.6.5 Yard Fire Hydrants and Hydrant 3/4 7-44 Irced Hose Houses II 3/4.7.7 Fire Rated Barriers 3/4 7-47 Efes E g 3/4.7.8 ACM Diesel Generator 3/4 7-50 #5B YCICf B 3/4.7.9 Control Room Emergency 3/4 7-56 Erc5R Ventilation System

, 4 Nolth W AG N E.B.

, 5 NOV 3 01985 SECTION DESCRIPTION PAGE 3/4.7.10 Snubbers 3/4 7-61 E8 5/4.8 AUXILIARY ELECTRIC POWER SYSTEMS U 3/4.8.1 A.C. Power Sources PEIcr A 3/4.8.1.1 A.C. Power Sources - Operating 3/4 8-1 EF56. '

3/4.8.1.2 A.C. Power Sources - Shutdown 3/4 8-14 __..fr e s s 3/4.8.2 D.C. Power Sources '

3/4.8.2.1 D.C. Power Sources - Operating 3/4 8-20 Ercr o 3/4.8.2.2 D.C. Power Sources - Shutdown 3/4 8-25 ._._ffeJ 8 3/4.8.3 Onsite Power Distribution 3/4.8.3.1 Onsite Power Distribution- 3/4 8-29 trer B Operating V 3/4.8.3.2 Onsite Power Distribution- 3/4 8-31 (Ic5J Shutdown 3/4.9 FUEL HANDLING and STORAGE SYSTEMS 3/4.9.1 Fuel Handling and Maintenance 3/4 9-1 ___.Eff58

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3/4.9.2 F 1 n achine 3/4 9-4 ffCJ8 _

3/4.9.3 Fuel Storage Wells 3/4 3-9 f f rJ B ~-

3/4.9.4 Spent Fuel Shipping Cask 3/4 9-13 _ 5151J V 3/4.9.S Communications During Core 3/4 9-15 . Erc;A Alterations 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 Xenon Stability 3/4 10-1 Rfd d NO$h W4GNER K 'l IQBAL AM ME.D l

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. .- UKAH 6

NOV 3 01985 SECTION DESCRIPTION PAGE 5.0 DESIGN FEATURES 5.1 Site 5-1 ES.___ _.

-5:2 Reactor Coolant System and Steam Plant System

'5.2.1 Prestressed Concrete Reactor 5-4 E B.. . _ . .

Vessel (PCRV) g c,7 . 5.2.2 Steam Generator Orifices 5-5 .. . EG 5.2.3 Steam Safety Valves 5-6 ..J.I e s 1. _ _ .

5.3 Reactor Core 5-6 45E. . _. . .

5.3.1 Reactor Assembly 44 6 .

5.3.2 Active Core 5-7 __.__ . RS 0 5-6 5.3.3 Fuel 5-8 .__. . . R s S 5.3.4 Reload Segment Design 5-9 . RSS ...

5.3.5 Reflector 5-12 OJB _ __

5.3.6 Control Rods 5-12 RJS 5.3.7 Reserve Shutdown System 5-13 R r G .__ _ .

VEIcr Bt 5.4 Fuel Storage 5-15 fits S _ . . . .

5.4,1 Criticality 5-15 EJ r5J_ ._

5 . 4'. 2 Containment 5-15 Ef c3 o V 5.4.3 Neutron Absorber-Heat Sink 5-15 pruS .~

5.5 Meteorological Tower Location 5-15 R.fE. .

5.6 Component and Transient Cyclic Limit 5-15 ____ .. . E B .

, rm lV N NORM WAGNE.R 7

,. , .-- , .c.. * -- w

7 DRAFT SECTION NOV 3 0 IST5 DESCRIPTION

. - _PAGE 6.0 ,

ADMINISTRATIVE CONTROLS

,_6.. I Responsibility 6.2 Organization 6-4 FC1

- 6.3 6-4 #c6 6.4 Unit Staff Qualifications 6-11 _ f o o Training _

6.5 Review and Audit 6-12 ___._ Icf . ....__

6.5.1 6-13 fc.B Plant Operations Review 6-13 _ 1AS _ . .

6.5.2 Committee (PORC)

Nuclear Facility Safety 6-17 fc 6 _.

6.6 Committee (NFSC) 6.7 Re.ortable Events Action 6-21 _ _ Ic5 Sa)=ty Limit Violations 6-22 F* B 6.8 Procedures'and Programs 6.9 Reporting Requirements 6-23 _. . Jc 6 . . _ . . .

6.9.1 Routine Reports and 6-26 _ _. fc 8 Reportable Events 6-26 fcB

! 6.9.2 Special Reports 6-36 . EC E ~

b M %n 6.10 6.11 Record Retention Radiation Protection Program 6-36 /' 8_

6.12 High Radiation Area 6-39 US14 _ . . .

6.13 .

6-39 - IfcjE .. _.__.

Process Control Program (PCP)-

6.14 Offsitt Dose Calculation 6-41 JJr.s.4 _

Manual (ODCM) 6-42 __ 45.c 4.__ ..

. . V E.15 r Major Changes to Liquid, Gaseous 6-43 .

and Solid Radwaste Treatment If c.r 4_ . . .

Systems 6.16 Fuel Surveillance Program 6.17 Environmental Qualification 6-44 _ .. 8.f4 6-45 .ES . _ --

7.0 NOT USED 8.0 RADIOLOGICAL and ENVIRONMENTAL .

F.s v Intavse t 5.spre rw Ea A"o Trs rws Pxc6nw (u p e nar... }41 & P.tc .)

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  • N ofL M W AG N E R, 1 i' ,

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