ML20133A824
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'o UNITED STATES
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March 12,1984 MEMORANDUM FOR: Darrell G. Eisenhut, Director Division of Licensing FROM:
Roger J. Mattson, Director Division of Systems Integration
SUBJECT:
' GRAND GULF TECHNICAL SPECIFICATIONS RE-REVIEW
Reference:
Memorandum from H. Denton to R. Vollmer, et al, dated 02/24/84,
Subject:
Grand Gulf Technical Specifications The reference memorandum directed a complete and thorough re-review of the Grand Gulf Technical Specifications. The purpose of this memorandum is to present the results of this re-review.
DSI has conducted a complete re-review of the Grand Gulf 1 Technical Spec-ifications to verify that the Technical Specifications were properly derived from the analyses and evaluation included in the FSAR as reviewed in the staff's SER. The results of the re-review are shown in Enclosures 1 through 3 as follows: provides a summary listing of Grand Gulf Technical Specification Sections needing modification. contains an annotated index of Grand Gulf Technical Specifications.
This index identifies the sections of the Grand Gulf Technical Specifications that were reviewed by each DSI branch. provides the detailed results of the review.
Overall, this re-review has identified 35 sections of the Technical Specifications that need modification. The majority of these changes have been identified pre-viously and have either not yet been implemented or are currently under review by the licensee or the staff.
~
'im ]&
Roger J.
ttson, Director Division of Systems Integration
Enclosures:
As stated cc: H. Denton E. Case B507200173 850515 R. Vollmer PDR FOIA H. Thompson BELL 84-459 PDR-
& BCs J. ;=;M ::d A.ss.
.w D. Houston C. Thomas R. Capra
. __, [_
SUMMARY
LIST!NG OF GRAND GULF TECHNfCAL SPECIFZCATION SECTIONS NEEDfNG MODZFICAT10N SECTION TITLE DSI BRANCHES 2.2.1 (Limits).. Reactor Protection System Instrumentation Setpoints.......RSB*, ICSB+
2.1.2 (Bases)... Thermal Power, High Pressure a nd High Flow................RSB*
3/4. 2. 2......... AR PM S e tpo i n ts............................................ RS B
- 3/4.3.1......... Reactor Pro tectio n System Ins trumenta tion.................ICSB+
3/4.3.2......... Isol a tio n Actua tio n I ns trumenta tion....................... ICSB+
3/4.3.3.........ECCS Actua tio n Instrumentatio n............................ ICSB+, RSB*, PSB*
3/4.3.4......... Recirculation Pump Tri p Actuation Instrumentation.........ICSB+
3/4.3.5.........RCIC Sys tem Actua tio n Instrumenta tion..................... ICSB+
3/4.3.6.........Co ntrol Rod Block Instrumenta tion......................... ICSB+
3/4.3.7.4....... Remote Shu tdown Moni tori ng Ins trumenta tio n................ ICSB 3/4.3.7.5....... Accident Moni tori ng Instrumenta tio n....................... ICSB 3/4.3.8.........Pla nt Systems Actua tio n Instrumenta tion................... ICSB 3/4.4.1.1....... Reci rc ul a ti o n Loo ps.......................................C PB
- 3/4.4. 3.2...... 0 pera tio nal Lea ka ge....................................... ICS B 3/4.6.1. 2.......Co nta i nme nt Lea ka ge.......................................C 5B 3/4.6.1.4.......MS IV Lea kage Co ntrol Sys tem...............................ASB*
3/4.6.1.9.......Co ntai nme nt Purge Sys tem..................................CSD 3/4. 6.3.1.......Su pres si o n Pool.......................................... 1 CS8, CSB*
3/4.6.4.........Co ntai nment and Drywell Isola ti on Val ves..................CSB 3/4.6.6.1.......Seco nda ry Co ntai nment Integri ty...........................CSB, AEB 3/4.6.6.3.......S ta ndby Ga s Trea tme nt Sys tem..............................CSB, AEB 3/4.6.7.2....... Containment and Drywell Hydrogen Igni tion System..........CSB 3/4. 7.1.1.......S ta ndby Se rvi c e Wa te r Sys tem.............................. ICS B, ASB*
3/4.7.1.2.......Hi gh Pressure Core Spray Service Wa ter System............ASB*
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3/4. 7.2......... Control Room Emergency Fil tra tio n System..................AEB, METB 3/4.7.3......... Reactor Core Isola tio n Cool i ng System.....................ICSB 3/4.8.1......... A.C. S o urc e s -Ope ra ti ng.................................... PS B
- 3/4.8. 2.........D.C. So urc es -Ope ra ti ng....................................PS B*
3/4. 9.1......... Re a c to r Mod e S wi tc h...................................... 1C5 B +
3/4.2.3 (Bases ). Minimum Cri tical Power Ra tio..............................CPB*
3/4.3.1 (Ba ses ) : Reactor Protection Sys tem Instrumenta tion................. ICSB i
3/4.6.1.7
.Co nta i nme nt Inte rnal Pres s ure.............................CSB*
(Bases)
I 3/4.6.2.5
. Drywel l I n terna l Pres s ure.................................CSB *
(Bases) l 3/4.6.3.........De pres s uri za tio n Sys tems..................................CS B*
6.8.3........... Procedures & Programs....................................
1C58
- New item, not previously identified. - Ib
+ Partially new/ modified from previously identified open issue.
r-a.
i ANNOTATED INDEX OF GRAND GULF TECHNICAL SPECIFICATIONS KEY 1.
Technical Specification Sections that have been reviewed by DSI are indicated by showing the Branch acronym (that conducted the re-review) between the Section Title and the Page Number.
2.
Technical Specification Sections not reviewed by DSI are identified by a box drawn around the Section Number / Title.
l 3.
Technical Specification Section that r.eed modification are identified by an arrow drawn in the left hand margin of the index. Details regarding the modifications are contained in Enclosure 3.
I
.w t
INDEX I
DEFINITIONS SECTION 1.0 DEFINITIONS PAGE 1.1 ACTION 1-1 1.2 AVERAGE PLANAR EXPOSURE........................... 9. D..
1-1 AVERAGE PLANAR, LINEAR HEAT GENERATION RATE....%.S.St.$f.0.
1-1 1.3 l
1.4 CHANNEL CALIBRATION.................. n.93.S.r...D.4.7 %....
1-1
- 1. 5 CHANNEL CHECK......................... ES.lb.6..D.U.S.....
1-1 1.6 CHANNEL FUNCTIONAL TEST...............@.%.S. i..D.U.S....
1-1
- 1. 7 COREALTERATION.................................$P.@......
1-2
- 1. 8 CRITICALPOWERRATIO.....................@.6.6.S.T.9......
1-2 1.9 DOSEEQUIVALENTI-131...........................6EO.....
1-2 1.10 ORYWELL INTEGRITY............................... $.3.D.....
1-2 1.11 E-AVERAGE DISINTEGRATION ENERGY..................h.D....
1-3 1.12 EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME.65%.@)61-3 1.13 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME..
1-3 RSS,3c50 1.14 FRACTION OF LIMITING POWER DENSITY.................. Sf.O.
1-3 1.15 FRACTION OF RATED THERMAL POWER.................... 9.I.D. 1-3 1.16 FREQUENCY N0TATION........................... rTU.S. !WrI.D.
1-3 1.17 GASEQUS RADWASTE TREATMENT (OFFGAS) SYSTEM........I1 K10t..
1-3 1.18 IDENTIFIED LEAXAGE.......................... M.S.i.9.% S...
1-4 1.19 ISOLATION SYSTEM RESPONSE TIME................... 95S,,,,
1 4
- 1. 20 LIMITING CONTROL ROD PATTERN.......................h..h....
1-4
- 1. 21 LINEAR HEAT GENERATION RATE..................N64. S.I.0L... 1-4 1.22LOGICSYSTEMFUNCTIONALTEST.....................D.D.....
1-4 1.23 MAXIMUM FRACTION OF LIMITING POWER DENSITY........ $.9.D..1-4 i
- 1. 24 MINIMUM CRITICAL POWER RATIO...............D.% s.i.E.0...
1-4
- 1. 25 0FFSITE DOSE CALCULATION MANUAL..................D.U.S.. 1-5 1.26 OPERABLE - OPERABILITY......................... M S.h...
1-5 l
l l
l GRAND GULF-UNIT 1 i
INDEX I
DEFINITIONS SECTION DEFINITIONS (Continued)
PAGE 1-5 Q OPERATIONAL CONDITION -CONDITION..........................
1.28 PHYSICS TESTS.....................................S P.D...
1-5 1.29PRESSUREBOUNDARYLEAXAGE.........................M.@....
1-5 1.30 PRIMARY CONTAINMENT INTEGRITY..................... N...
1-6
- 1. 31 PROCESS CONTROL PR0 GRAM.........................hE,TS,,,
1 6 1.32 PURGE-PURGING...................................D E T.O...
1-6
- 1. 33 RATED THERMAL P0WER...............................$.P.O...
1-6 1.34 REACTOR PROTECTION SYSTEM RESPONSE TIME..........f. 9.O...
1-7 1-7 M REPORTABLE OCCURRENCE......................................
1.36 RCD DENSITY.......................................$ ?.6...
1-7
- 1. 37 SECONDARY CONTAINMENT INTEGRITY................... flF.6...
1-7
- 1. 38 SHUTCOWN MARG IN................................... h. E.O..
1-8
- 1. 39 SO LIDIFICATION................................... D E.T 0..
1-8 1.40 SOURCE CHECK.....................................h ET.0...
1-8
- 1. 41 STAGGERED TEST BASIS........................... 1%A..
1-8 L 42 THERMAL P0WER.....................................h.f.D..
1-8 1
UNIDENTIFIED LEAKAGE........................@)E E flE.T 6.
1-8 1.44 VENTILATION EXHAUST TREATMENT SYSTEM..............D.C.6..
1-8 1-8 1.45 VENTING....................................................
TABLE 1.1, SURVEILLANCE FREQUENCY NOTATION......................
1-9 TABLE 1.2,,0PERATIONAL C0NDITIONS'...............................
1-10 GRAND GULF-UNIT 1 if
. = -
s INDEX k
SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PAGE 2.1 SAFETY LIMITS THERMAL POWER, Low Pressure or Low Flow........RS.Ba.C.9.G.
2-1 THERMALPOWER,HighPressureandHighFlow.... bks 4.S.I.@.
2-1 Reactor Coolant System Pressure.................... N k..
2-1 ReactorVesselWaterLeve1.........................N.@..
2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS RS S, ICS O t 8 tactor 3rotetction_Syltaa_instrumentatf orLSetno.ints..D.O.
2-3
~
g C90 IcaB 8ASES 2.1 SAFETY LIMITS THERMAL POWER, Low Pressure or Low Flow........ D Ds.9f.@.
B 2-1 NI6 b S S..C.D.9.
B 2-2 m
Reactor Cool ant System Pres s ure. ~.................N.9... B 2-5 Reactor Vessel Water Leve1........................ N.h...
B 2-5 2.2 LIMITING SAFETY SYSTEM SETTINGS
'pcs s Reactor Protection System Instrumentation Setpoints.......
B 2-6
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GRAND GULF-UNIT 1 iii i
,--,----,---,,-,-,v.
4 ene
,,,_..w-_-
,-----m.,m,,
, - - ~ -,,, _ -.
-,.mn,..
,,,--c_- -,_..,_,_., - -,
--,-,,,n.,,---
,,-,-,-,g..w--
,,-.v,-,.
,,, -,m,--m.
INDEX k
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE
)
3/4.01 APPLICABILITY...........................'..................
3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN...............................$.E.9....
3/4 1-1 3/4.1.2 REACTIVITY AN0MALIES......................... M....
3/4 1-2 3/4.1.3 CONTROL R005 Control Rod Operability.......................h.E.S...
3/4 1-3 Control Rod Maximum Scram Insertion Times......C.PS..
3/41-6 Control Rod Scram Accumulators.................$.P.O..
3/4 1-8 ControlRodDriveCoupling......................$.E.@...
3/4 1-10 Control Rod Position Indication..........E.S t.9.Q.
3/4 1-12 ControlRodDriveHousingSupport..............9.9.@...
3/4 1-14 3/4.1.4 CONTROL R00 PROGRAM CONTROLS ControlRodWithdrawa1........................$?.D....
3/4 1-15 Rod Pattern Control System..........T ES.Sc.. 9.$.9...
3/4 1-16 STANDBY LIQUID CONTROL SYSTEM..................h.D...
3/4 1-18 3/4.1.5 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGEPLANARLINEARHEATGENERATIONRATE.....D.@....3/4 2-l' Rse J /4 i 2 iPlUs i rTRisTi:.......................... M.B... M.Q.
3/4 2-s lL4.21_fi1HIMLN CRITICAL POWER RATI0.............g g :..qp g 3/4 2-6 LINEAR HEAT GENERATION RATE.................... C P B 3/4 2-9 3/4.2.4
~
i l
l l
GRAND GULF-UNIT 1 iv 1
.. ~ ~ -..,
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.3 INSTRUMENTATION CPS ZCS6 m jf4,3,CEACITdR PROTECTIOESYSTEM INSiEUMENTETIQN.5CS.B.tN.9. 3/4 3-1
- n c t o sa/.4,3 i~IYLAiiON ACI5AEESTEME TATI5N '..I.C.5,h, RS Q,, 3/4 3-9
~
~
~
9 2: CSS pg3,3 gifER'G'EN'd 'C0R5'~ddOLING SYST5M ACTUATIO[ f.?fk.D.
3/4 3 ~
~
PSB RSG,pc;B '
INSTRUMENTATI0tL.........................
s ICS G m f) b 1. 3 CIRCULATION PUMP TRIP ACTNATION INSTRUMENTATIhN'
~
.tC50 RSS ATWS Recirculation Pump Trip System Instrumentation..
3/4 3-34 End-of-Cycle Recirculation Pump Trip System Instrumentation...............................Yqg......
3/4 3-38 vc5s REACTOR CORE ISOLATI0_N_.C0_0GNG_ SYSTEM ACTUATION J/4.3.5 a N smME NTAH0 N......................... M.%.m.C 54. 3 /4 3 - 44
~
.E11E~CONTR6L R00-BLOCK IR$TRifENTATION._......Y.C.S.B...C.9.Q. 3/4 3-49 0
~
3/4.3.7 MONITORING INSTRUMENTATION BEB i Radiation Monitoring Instrumentation....S.A.S.NCT.D..
3/4 3-55
%.Sei smic Moni tori ng Instrumentation]..................
3/4 3-60 3 Meteorological Monitoring Instrumentation...T).U.S..
3/4 3-63 IC M lhemoja_5buidaynJoMtit.jiitlistr_umen_tatio).D.W.hMO3/4 3-66 5
IC56 (Xccident Monitorina Instr.gentation.....E.s L M D.
3/4 3-69 6 Source Range Moni tors...................@.9.5.9.i.9.? O. 3/4 3-73
[
t Traversing In-Core Probe System.........E.f.9
.C. f.M.
3/4 3-74 i
1 Chlorine Detection System......
3/4 3-75 i
l 1
Fi re Detecti on Instrumentati on.
3/4 3-76 to Loose-Part Detection System.................. 9.P, S,, 3/4 3 81 Radioactive Liquid Effloent Monitoring Instrumentation.............................. g g.........
3/4 3-82 3
It Radioactive Gaseous Effluent Monitoring Instrumentation.............................g g 3/4 3-87
< 3/4.3.fL PLANT. SYSTEMS ACTUAIIQH. INS _TRUMENTATIO 3/4 3-96 mg GRAND GULF-UNIT 1 v
- ~
INDEX I
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM C.E E 8 Recirculatioq, Loops.....................g$.E.(.,g....
3/4 4-1 1 Jet Pumps............................... D 6,.9.E.D..
3/4 4-2 3 Recirculation Loop Flow.....................%.6....
3/4 4-3 4 Idle Recirculation Loop Startup.............ES O...
3/4 4-4 3/4.4.2 SAFETY / RELIEF VALVES Safety / Relief Va1ves......................... N.k..
3/4 4-5 1 Safety / Relief Valves Low-Low Set Function. emf.S.O.
3/4 4-6 3/4 4.3 REACTOR COOLANT SYSTEM LEAXAGE Leakage Detection Systems........ 8.$.1.6.i. 6.5 0.....
3/4 4-7 d Tperational. Leakage...... )R 6.i...f C,1,L,$..f.....
3/4 4-8 9
S DO
,3/4.4.4 CHEMISTRY............................................
3/4 4-31 SPECIFICACTIVITY............................h.40...
3/4 4-14 3/4.4.5 3/4.4.6 PRESSURE / TEMPERATURE LIMITS a
3/4 4-17 i
Reactor Coolant System...............................
1ReactorSteam0 cme..........................D.S.....
3/4 4-21 l
3/4.4.7 MAIN STEAM LINE ISOLATION VALVES...E% E D.%9.@.S..
3/4 4-22 3/4 4-23 3/4.4.8 L STRUCTURAL INTEGRITY.................................
3/4.4.9 RESIDUAL HEAT REMOVAL Hot Shutdown................................. N....
3/4 4-24 I
1ColdShutdown................................E%O...
3/4 4-25 3/4.5 EMERGENCY CORE COOLING SYSTEMS ECCS - 0 P E RAT I NG............................
3/4 5-1 3/4.5.1 b..O....
3/4 5-6
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3/4.5.2 ECCS - SHUTD0WN.............................
SUPPRESSIONP00L.............................b.kO...
3/4 5-8 3/4.5.3 GRAND GULF-UNIT 1 vi y--
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMEN f
PAGE-SECTION 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT 1 Primary Containment Integrity............. 9.6.S 9.
3/4 6-1 l
C SM.
3/4 6-2 CN u 2 " Containment 1eakasem............................
l ContainmentAirLocks..........................@...
3/4 6-5 l
3 992.R.S.O.. 3/4 6-7 AS6
<-q MSIV fe'akaice Control Svsita..................
5 Feedwater Leakage Control System.............. 9.E.
3/4 6-8 O
L Containment Structural Integrity...............Q..
3/4 6-9 7 Contai nment Internal Pres sure................ 9.3.@
3/4 6-10 1 Contai nment Average Ai r Temperature.......... $ f E..
3/4 6-11 C..S.@...
3/4 6-12 CSO
'l[ContainmentPurceSystem....................:
3/4.6.2 DRYWELL C56 3/4 6-13 1 Drywell Integrity....................................
- 2. Drywell Bypass Le akage......................h.k9....
3/4 6-14 3 Drywell Air Locks...........................bS.O...
3/4 6-15 4OrywellStructuralIntegrity................h.h.O....
3/4 6-17
.9...
3/4 6-18 i Otp ell Internal Pressure....................
Drywell Average Ai r Temperature............. 9.50...
3/4 6-19 0
3/4.6.3 DEPRESSURIZATION SYSTEMS
~
i$.~............... M.D.s..$.1.0.....
3/4 6-20
- 2. CSS,CS6 m ) {suppressdon.Pon 1 Containment Spray.......,...................h.h.9....
3/4 6-24 3 Suppres si on Pool Cooli ng...................h.I.0.....
3/4 6-25 4 Suppression Pool Makeup System............b.9.....
3/4 6-26
' 3/4. 6.4.-. CONTAINMENT._AND_DRWELLISOLATIOR 3/4 6-27 C30 vii GRAND GULF-UNIT 1
INDEX k
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE CONTAINMENT SYSTEMS (Continued) 3/4.6.5 DRYWELL POST-LOCA VACUUM BREAKERS...........h. N...
3/4 6-45 3/4.6.6 SECONDARY CONTAINMENT C S B. A G! O x ITedonBiBEContaf nmdit7ntegpi ty.......M s.h.5.0...
3/4 6-46 2 Secondary Containment Automatic Isolation Dampers /
Va1ves...........................................BA%
3/4 6-47 CSB,OED LStandby. Gas.. Treatment.. System........... RE.% tg'T. 0t.
3/4 6-53 3/4.6.7 ATMOSPHERE CONTROL I Containment and Drywell Hydrogen Recombiner Systems.......................................9.9..
3/4 6-56 CS6
._1 [qqntainment and Dryhel{.[iydfo'geTIanftTon Sy_s_ tem.90 3/4 6-58 3 Drywell Purge System........................... $.9.
3/4 6-59 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS 33:'.1 6 RSO
' i 3tandby Se rvj cq Wate.r. Sy. stem.._......A..S.O... t. It.3.B..... 3/4 7-1
~ - - - - -
-~~~
t 4
ASS
' 2 di.igh _ Pressure _Co.r.e_19. ray _Servica_Watar_53. stem.M9. 2.C30 3/4 7-3
= - - _
3 Ul timate Heat S i nk............................%.0..
3/4 7-4 RS S
~
6ES NET 8'3743 L_CONTR0L ROCIM ENFDCFMcY FI1TRAIION SYSTEM.. 8)iir.OB.3FTP 3/4 7-5
~ ~ ~ E5dO[(OhI_11Ql,ATION_CQ0 LING SYiTU..N.U9.@..
3/4 7-7 MS m3/4. '/._3
_R 3/4.7.47 SNUBBERS.............................................
3/4 7-9 3/4.7.5 SEALED SOURCE CONTAMINATION.................. b Ct..
3/4 7-z6 3/4.7.6 FIRE SUPPRESSION SYSTEMS Fire Suppres sion Water System........................
3/4 7-28 Spray and/or Sprinkler Systems.......................
3/4 7-31 Sy s t em s............,.'.............................
3/4 7-32 CO2 Halon Systems........................................
3/4 7-34 Fire Hose Stations...................................
3/4 7-35 Yard Fire Hydrants and Hydrant Hese Houses...........
3/4 7-38 GRAND GULF-UNIT 1 viii
.___.____.__.,_______.___..._I
INDEX 1
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE PLANT SYSTEMS (Continued)
)3/4.7.7I IIRE RATED ASSEMBLIES................................
3/4 7-40 3/4.7.8 AREA TEMPERATURE MONITORING..................OS.S...
3/4 7-42 3/4.7.9 SPENT FUEL STORAGE POOL TEMPERATURE......... h.@.@....
3/4 7-44 l
3/4'.8' ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES PSG u E C. Joi des 3 difaA ng.................... 9.S B....
3/4 8-1 A.C. Sources-Shutdown......................O.$ 0....
3/4 8-9 3/4.8.2 D.C. SOURCES PSG
< p'.L_Siu' reg _E0;te_r.ati ng._...................P. S. Q...
3/4 8-10 D.C. Sources - Shutdown.....................f.E.h....
3/4 8-14 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS Distribution-Operating....................D.0.....
3/4 8-is Distribution - Shutdown.....................E. 9....
3/4 8-17 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES l
Primary Containment Penetration Conductor Overcurrent Protective Devices.......................U.S......
3/4 8-19 Motor Operated Valve Thermal Overload Protection.@.9.
3/4 8-39 Reactor Protection System Electric Power PSO Monitoring.........................................
3/4 8-46
~
GRAND GULF-UNIT 1 ix i
I l
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS MO t 3/(79,5 T R'EACTOR'. MODE.5 DITCH................... E E4 0.6 9.i.9.
3/4 9-1
~
~~
3/4.9.2 INSTRUMENTATION.............................$ ?.h...
3/4 9-3 3/4.9.3 CONTROL ROD P0SITION........................b.9...
3/4 9-5 DECAY TIME..................................h. D..
3/4 9-6 3/4.9.4 (3/4.9.5)
COMMUNICATIONS.......................................
3/4 9-7
[ 3/4. 9. 6 ) REFUELING PLATF0RM...........................'........
3/4 9-8 3/4.9.7 CRANE TRAVEL - SPENT FUEL AND UPPER CONTAINMENT FUEL STO RAGE P00 LS....................... 0 3.0. Rc D...
3/4 9-9 3/4.9.8 WATER LEVEL - REACTOR VESSEL............@.T-A s.D.O.
3/4 9-10 3/4.9.9 WATER LEVEL - SPENT FUEL AND UPPER CONTAINMENT FUEL
(
STO RAGE P00 LS....................... 6LI A. R K E.. 3/4 9-11 3/4.9.10 CONTROL ROD REMOVAL Singl e Control Rod Removal...................h.?9..
3/4 9-12 Multiple Control Rod Remova1.................C9 03/4 9-14 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Leve1............................N.9....
3/4 9-16 Low Water Leve1............................ N S....
3/4 9-17 HORIZONTAL FUEL TRANSFER SYSTEM............ b5.6....
3/4 9-18 3/4.9.12 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1lPRIMARYCONTAINMENTINTEGRITY/DRYWELLINTEGRITY...... 3/4 10-1 3/4.10.2 ROD PATTERN CONTROL SYSTEM................. MA....
3/4 10-2 SHUTDOWN MARGIN DEMONSTRATIONS............ 9.iM....
3/4 10-3 3/4.10.3 RECIRCULATION L00PS....................... N.S....
3/4 10-4 3/4.10.4 l3/4.10.5\\ TRAINING STARTUPS....................................
3/4 10-5 GRAND GULF-UNIT 1 x
INDEX
~
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration...............................D C.S..
3/4 n-1 D
0ose........................................ E.S...
3/4 11-5 Liquid Waste Treatment......................t1 ETD..
3/4 11-6 Li qui d Hol dup Tanks......................... D E'{.S..
3/4 11-7 3/4.n.2 GASEOUS EFFLUENTS Do s e Rate....................................D E.I.Q..
3/4 11-8 Do s e-Nobl e Gas e s..............................D.9.9.
3/4 11-12 Dose-Radiciodines, Particulate, and Radionuclide Other than Noble Gases....h?.lSt.
3/4 n-13
. Gaseous Waste ' reatment......................D.4 7.S..
3/4 11-14 T
Ventil ation Exhaust Treatment................D.O.0..
3/4 n-15 Expl osi ve Gas Mixture.........................he T O...
3/4 n-16 MainCondenser.................................D.E.lE.. 3/4 11-17 3/4. n.3 SOLID RADI0 ACTIVE VASTE....................... hliU.S. 3/4 n-18 3/4. n.4 TOTAL 00S E.....................................W.19.3/4 n-20 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING r10NITORING P R0 GRAM..............................N.D,,, 3/4 12 1 3/4.12;1 3/4.12.2 LAND USE CENSUS............................... 9.0.9..
3/4 12-11 3/4.1:? ? INTERLABORATORY COMPARISON.................... 99.Q..
3/4 12-12 GRAND GULF-UNIT 1 xi
INDEX BASES
.PAGE i
SECTION 3/4.0 APPLICABILITY........................................... B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS SHUTOOWNMARGIN....N.O........................B3/41-1 3/4.1.1 REACTIVITYANOMALIES..C.f.9t..................... B 3/4 1-1 3/4.1.2 3/4.1.3 CONT RO L R005....C.E. f4............................ B 3/4 1-2 3/4.1.4 CONTROL RCD PROGRAM CONTROLS. 9 f.9............... B 3/4 1-3 STANDBY LIQUID CONTROL SYSTEM..h.E.9.............. B 3/4.1.5 3/4.2 POWER DISTRIBUTION LIMITS AVERAGEPLANARLINEARHEATGENERATIONRATE..U.Q.B3/42-1 3/4.2.1 3/4.2.2 APRM SETPOINTS.. M R.9.P.@...................... B 3/4 2-2
'_ CP B
. '3/.4. 2.3 _ MINIMUM CRITICAL POWER RATIO..D.O. 9.9.9.......
LINEARHEATGENERATIONRATE..h.S9................B3/42-6 3/4.2.4 3/4.3 INSTRUMENTATION _
RSS,Icse v b/4.3.1EREACIOLBOTECTIDH SYSTm INSTRUMENTATICH..#9..
MO ISOLATION ACTUATION INSTRUMENTATION..D'.M.S.9. B 3/4 3-1 I
3/4.3.2 ESE EMERGENCY CORE COOLING SYSTEM ACTUATION 3/4.3.3 INSTRUMENTATION.........................M E.9,C B 3/4 3-2 i
RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION....................%.53. :.=. c5 G B 3/4 3-2 3/4.3.4
~'
REACTOR CORE ISOLATION COOLING SYSTEM 3/4.3.5 ACTUATION INSTRUMENTATION..............R,S,9f,ES,Q a 3/4 3-3 CONTROL ROD BLOCK INSTRUMENTATION.M.S.I' U.S... B 3/4 3-I 3/4.3.6
~
l l
l i
i GRAND GULF-UNIT 1 xii
f.
INDEX BASES SECTION PAGE INSTRUMENTATION (Continued) 3/4.3.7 MONITORING INSTRUMENTATION RE 6 l Radiation Monitoring Instrumentation.% %>.9 0.9.
B 3/4 3-4
[ 2 Seismic Monitoring Instrumentation.'
B 3/4 3-4
^
3 Meteorological Monitoring InstrumentationJ1ETQ..
B 3/4 3-4
'lRemoteShutdownMonitoringInstrumentation.MS..'B3/43-4b[
5 Accident Monitoring Instrumentation.B.S.B.T.C40..
B 3/4 3-4 r
4 Source Range Monitors.M.hBa.CP.O..............
B 3/4 3-5
'lTraversingIn-CoreProbeSystem.4.C.19.i.90.....
B 3/4 3-5 3 Chlorine Detection System......
B 3/4 3-5 9 Fire Detection Instrumentation.
B 3/4 3-5 toLoose-PartDetectionSystem..9f.O..............
B 3/4 3-5 11 Radioactive Liquid Effluent Monitoring @.W...
B 3/4 3-6 Instrumentation.......................
- 12. Radioactive Gaseous Effluent Monitoring Instrumentati on.......................D.C.9..
B 3/4 3-6 l
3/4.3.8 PLANT SYSTEMS ACTUATION INSTRUMENTATION.f. D...
B 3/4 3-6 Asa 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM..b. E.. N.6..............
B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES... N.B.'. 3. M.9...........
B 3/4 4-1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems. E.9.6.'..$.W.........
B 3/4 4-2 Operational Leakage.%9.S.Ba.SS.94. 9.4.Q........
B 3/4 4-2 L
3/4.4.4 CHEMISTRY.
B 3/4 4-2 3/4.4.5 SPECIFIC ACTIVITY... @.......................
B 3/4 4-3 3/4.4.6 PRESSURE / TEMPERATURE LINITS... M.............
B 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES..E.D:b.D.'.9.EG B 3/4 4-5 3/4.4.8 STRUCTURAL INTEGRITY.
B 3/4 4-5 3/4.4.9 RESIDUAL HEAT REMOVAL. 8N...................
B 3/4 4-5 GRAND GULF-UNIT 1 xiii
s INDEX BASES SECTION PAGE
' 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3
3/4.5.1/2 ECCS - OPERATING and SHUT 00WN.. M.D............
B 3/4 5-1 3/4.5.3 SUPPRESSIONP00L................$.S.@...........
B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT l Primary Containment Integrity......... 9. M ?G.
B 3/4 6-1 1 Containment Leakage..................... 9:%.h.
B 3/4 6-1 3 Containment Ai r Locks................... 9.9.@..
B 3/4 6-1 4MSIVLeakageControlSystem.........D.h.99.@..
B 3/4 6-1 5 Feedwater Leakage Control System......... 9.@..
B 3/4 6-2 6 Containment Structural Integrity......... 9.S.9..
B 3/4 6-2 C.S 6 m __ q Containde6t Intei nal Pi essure.............C,5,Q..
B 3/4 6-2
(
S Containment Average Air Temperature..... 9.5.Q..
B 3/4 6-2 3 Containment Purge System................ 9.S.9...
B 3/4 6-2 3/4.6.2 DRYWELL 1 Drywell Integri ty........................ $.%9...
B 3/4 6-3 2.Drywell Bypass Leakage.................. 9.5,Q...
B 3/4 6-3 3 Drywel l Ai r Locks....................... 95.Q...
B 3/4 6-3 4 Drywell Structural Integrity............ bh.9...
B 3/4 6-3 5 grywe.D Tn_5_,13f1'Tr'.eUEre................k ?.9...
B 3/4 6-3
^
0 76 Drywell Average Air Temperature..........kb.9...
B 3/4 6-4 C38 m 3/4.6.3 lDEPRESSURIZIiiON ~5kSTEMS.........--9. 9.8. 9.%.9.
B 3/4 6-4
'~
~
CONTAINMENT AND DRYWELL ISOLATION VALVES..h.D.S.
B 3/4 6-5 3/4.6.4 3/4.6.5 DRWELL POST-LOCA VACUUM BREAKERS........kh.h..
B 3/4 6-5 SECONDARY CONTAINMENT.......n..c...e.1.c.s..s.'..e se B 3/4 6-6 3/4.6.6 C
ATMOSPHERE CONTR0L,.....................s s......
B 3/4 6-6 3/4.6.7 i
GRAND GULF-UNIT 1 xiv
INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS..............O ).h M.9.
B 3/4 7-1 REO 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM..D@.@.." B 3/4 7-1 ht70 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM. D.Ss. G.O B 3/4 7-1 3/4.7.4 SNUBBERS.
B 3/4 7-2 3/4.7.5 SEALED SOURCE CONTAMINATION... M.O..............
B 3/4 7-3 1
3/4.7.6 FIRE SUPPRESSION SYSTEMS.
B 3/4 7-3 3/4.7.7 FIRE RATED ASSEMBLIES....
B 3/4 7-4 3/4.7.8 AREA TEMPERATURE MONITORING....A.f.9.............
B 3/4 7-4 3/4.7.9 SPENT FUEL STORAGE POOL TEMPERATURE..h. N......
B 3/4 7-4 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, A.C. SOURCES, D.C. SOURCES and ONSITE POWER and DISTRIBUTION SYSTEMS........................f.@
B 3/4 8-1 3/4.8.3 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES...D.S..
B 3/4 8-3 l
i
)
GRAND GULF-UNIT 1 xv e
b
i INDEX BASES SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH..............N.N.i.h.P,$..
8 3/4 9-1 3/4.9.2 INSTRUMENTATION..........................W.h...
B 3/4 9-1 3/4.9.3 CONTROL R00 POSITION....................h.8 $...
B 3/4 9-1 3/4.9.4 DECAYTIME..............................b@.@...
B 3/4 9-1 3/4.9.5 COMMUNICATIONS......
B 3/4 9-1 3/4.9.6 REFUELING PLATFORM..
B 3/4 9-1 3/4.9.7 CRANE TRAVEL-SPENT FUEL AND UPPER CONTAINMENT FUEL STORAGE P00LS................. h 5.h BA9.
8 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL AND UPPER CONTAINMENTFUELSTORAGEP00LS.......BSS.S.E@..
B 3/4 9-2 3/4.9.10 CONTROLRODREM0 VAL.....................$.f.@...
8 3/4 9-2 3/4.9.11 RESIDUAL HEAT REMOVAL AND CCOLANT CIRCULATION..
B 3/4 9-2 3/4.9.12 HORIZONTALFUELTRANSFERSYSTEM.........b).O...
B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS j
3/4.10.1 PRIMARY CONTAINMENT INTEGRITY /ORYWELL INTEGRITY.
B 3/4 10-1 3/4.10.2 R00PATTERNCONTROLSYSTEM..........h.i.@.......
S 3/4 10-1 3/4.10.3 SHUTDOWN MARCIN DEMONSTRATIONS...... b.P.9.......
B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS..................h.S. $......
B 3/4 10-1 1
3/4.10.5 TRAINING STARTUPS..
B 3/4 10-1 GRAND GULF-UNIT 1 xvi
(
1 INDEX e
t BASES SECTION
- PAGE 3/4.11 RADIACTIVE EFFLUENTS 3/4.n.1 LIQUIDEFFLUENT5......................D.C.9.....B3/411-1 3/4.H.2 GASEOUS EFFLUENIS.....................D. 9.9..... B 3/4 n-2
~
3/4.11.3 SOLID RADI0 ACTIVE WASTE...............U U..... B 3/4 11-5 3/4.u.4 TOTAL 00SE............................E N.... B 3/4 U-5 3/4.12 RADI0 ACTIVE ENVIRONMENTAL MONITORING 3/4.12.1 MONITORINGPROGRAM......................8E6....B3/412-1 3/4.12.2 LANDUSECENSUS..........................$.D6...B3/412-1 3/4.12.3 INTERLABORATORYCOMPARISONPROGRAM.......E93...B3/412-1 I
i l
GRAND GULF-UNIT 1 xvii
._.._.m.
,r,,_,.,___-
m.,.,
m y
4 INDEX DESIGN FEATURES SECTION PAGE 4
5.1 SITE
~
Exclusion Area.......
5-1 Low Population Zone..
5-1 i
5.2 CONTAINMENT Configuration.......................................D....
5-1 Design Temperature and Pres sure......-...............cs s 5-1 SecondaryContainment...............................C90....
5-1 i
5.3 REACTOR CORE Fue l As s emb l i es.....................................C P S 5-5 l
Contro l Rod Assembl i e s..............................C,P S...
5-5 5.4 REACTOR COOLANT SYSTEM DesignPressureandTemperature....................D.D...
5-5 Vo1ume.............................................. $....
5-5 5.5 METEOROLOGICALTOWERLOCATION......................M.T.9...
5-6 5.6 FUEL STORAGE C ri ti cal i ty....................................... f.'. 9.....
5-6 D ra i nage.......................................... 9 5 0 5-6 Capaci ty....................................R. S..S.
C.. P..S.....5 o-5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT...
5-6 2
GRAND GULF-UNIT 1 xviii
INDEX ADMINISTRATIVE CONTROLS PAGE SECTION 6.1 RESPONSIBILITY............................................
5-1 6.2 ORGANIZATION 0FFSITE.................................... 9(6(3....
6-1 6.2.1 UNIT 5.TAFF.................................5b.h.Ch....
6-1 6.2.2 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP Function............................
6-2 Composition..........................................
6-2 Responsibilities.....................................
6-6 Authority............................................
6-6 1_6. 2. 4 SHIFT TECHNICAL ADVISOR..
6-6 1
UNIT STAFF QUALIFICATIONS......................hk]D.Ch....
6-6 6.3 T RA I N I NG.............. /........................ fb.k S.....
6-6
(
6.4 6.5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY REVIEW COMMITTEE (PSRC)
Function.............................................
6-6 Compo si ti o n..........................................
6-7 6-7 Alternates............................
6-7 Meeti ng Frequency.....................
6-7 Quorum...............................
Responsibilities.....................
6-7 6-8 Authority............................
6-8 Rccords..............................
6.5.2 S.\\FETY REVIEW COMMITTEE (SRC) 6-9 Function.............................
C ampo s1 ti on..........................................
6-9 6-9 Alternates.............,..............
6-10 Co ns ul tants..........................
6-10 Meeting Frequency....................
6-10 Quorum...............................
GRAND GULF-UNIT 1 xix
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE
. SAFETY REVIEW COMMITTEE (SRC) (Continued)
Review................................
6-10 Audits................................
6-11 Authority.............................
6-12 Records...............................
6-12 6.5.3 TECHNICAL REVIEW AND CONTROL Activities................................... N.@.
6-12 6.6 REPORTABLE OCCURRENCE ACTI0N......................h.k.h..
6-13 6.7 SAFETY LIMIT VIOLATION............................S M..
6-13 bD9 EC3 S m 6'.8~'PRdCE0lfRf5 AND PROGRAMS,........ 9 9 A.4.9.S.....
6-14 4
6.9 REPORTING REQUIREMENTS h Tse. E.AG Routine Reports And Reportable Occurrences....'.......
5-15 Startup Reports......................................
5.15 Annual Reports.......................................
5-16 Annual Radiological Environmental Operating Report...
6-17 Semi-Annual Radioactive Effluent Release Report......
6-17 Monthly Operating Reports............'................
5-19 Reportable Occurrences...............................
6-19 Prompt Noti fication With Written Followup............
6-19 Thirty Day Written Reports...........................
6-21 Special Reports......................................
6-22 6.10 R ECO RD RETENTIQW........... :.................... 8.9 0...
6-22 RADI ATION PROTECTION P R0GRkM.....................bf)h..
6-23 6.11 6.12 HIGH RADI ATION AREA............................. b9.6..6-23
\\,
6.13 PROCESS PROGRAM CONTROL (PCP)...................D.5 7.9..
6-25 GRAND GULF-UNIT 1 xx
INDEX k,
ADMINISTRATIVE CONTROLS SECTION PAGE 6.14 0FFSITE DOSE CALCULATION MANUAL (00CM)........ hKT S...
6-25 6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATEMENT SYSTEMS....
6-26 METS p
GRAND GULF-UNIT 1 xxi
O e
ENCLOSURE 3 DETAILED RESULTS OF DSI RE-REVIEW 0F GRAND GULF TECHNICAL SPECIFICATIONS
g# "U%
UNITED STATES h
A*t NUCLEAR REGULATORY COMMISSION g
WASHINGTON, Q. C. 20555 MAR 121984 MEMORANDUM FOR:
R. Wayne Houston, Assistant Director for Reactor Safety Division of Systems Integration FROM:
Brian W. Sheron, Chief Reactor Systems Branch Division of Systems Integration
SUBJECT:
GRAND GULF UNIT 1 TECHNICAL SPECIFICATIONS Reactor Systems Branch has reviewed the Grand Gulf Technical Specifications revised.thr'ough Amendment 12. lists the sections which we reviewed. provides our comments.
Brian W. Sharon, Chief Reactor Systems Branch Division of Systems Integration
Enclosures:
As stated cc:
D. Hoffman RSB Section 8 Members R. Mattson R. Capra 9
e I
,,e
S ll ENCLOSURE 1 TECHNICAL SPECIFICATIONS, BASES AND.DEF.INI,UONS REVIEWED BY THE REACTOR SYSTEMS BRANCH FOR GRAND GULF UNIT 1 I.
Definition
- 1. 3.
Average Planar Linear Heat Generation Rate i
1.8 Critical Power Ratio i'
1.13 End-of-Cycle Recirculation Pump Trip System Response Time 1.12 Emergency Core Cooling System (ECCS) Response Time 1.21 Linear Heat Generation Rate 1.24 Minimum Critical Power Ratio i
II.
Safety Limits and Limiting Safety System Settings i
2.1.1 Thermal Power, low Pressure or Low Flow f
2.1. 2-Thermal Powar, High Pressure and High Flow 2.1.3 Reactor Coolant System Pressure 2.1.4 Reactor Vessel Water Level j
2.2.1 Reactor Protection System Instrumentation Setpoints III.
Limitina Conditions for Operation and Surveillance Recuriements
{
3 / 4.a.:
me s,m t t.au w u =.., was o-m.. aus 3/4.2.2 APRM Setpoints i
3/4.2.3 Minimum Critical Power Ratio 3/4.3.1 Reactor Protection System Instrumentation 3/4.3.2 Isolation Actuation Instrumentation 3/4.3.3 Emergency Core Cooling System Actuation Instrumentation 3/4.3.4 Recirculation Pump Trip Actuation Instrumentation /ATWS 3
j Recirculation Pump Trip System Instrumentation 4
3/4.3.5 Reactor Core Isolation Cooling System Actuation Instrumentation 3/4.3.7.4 Remote Shutdown Monitoring Instrumentation 3/4.3.7.5 Accident Monitoring Instrumentation 3/4.3.8 Plant Systems Actuation Instrumentation 3/4.4.1 Recirculation System 3/4.4.2 Safety Valves 3/4.4.6.2 Reactor Steam Dome 3/4.4.7 Main Steam Isolation Valves 3/4.4.9 Residual Heat Removal 3/4.5 Emergency Core Cooling System 3/4.7.3 Reactor Core Isolation Cooling System 3/4.9.8 Refueling Operations; Water Level - Reactor Yessel l'
3/4.9.11 Refueling Operation; Residual Heat Removal and Coolant Circulation 1
i 3/4.10.4 Special Test Exceptions; Recirculation Loops l
s.%
- h. ser C u.:v nm IV.
Bases Bases for all the areas identified in Sections II and !!! above.
i I
ENCLOSURE 2 COMMENTS ON GRAND GULF UNIT 1 TECHNICAL SPECIFICATIONS 9
1) 2.2.1 Reactor Protection System Instrumentation Setpoints Table 2.2.1-1 Item 3, " Reactor' Vessel Steam Come' Pressure-High;" The allowable value should be less than er equal to 1045 psig (Reference page.5-5oftheSER).
2)
Ba~ses 2.1.2 Thermal Power. High Pressure and High Flow The last paragraph of the text lists a GE report number as NED0-203040. The correct report number is NEDO-20340.
3) 3.4.2.2 APRM Setpoints The time constant for the thermal power monitor needs to be included in the LCO's and surveillance requirements.
(Reference page 15-4 of Grand Gulf SER).
4) 3/4.3.3 Emergency Core Coolina System Actuation Instrumentation 1.
Table 3.3.3-2 item B.2.e "LPCI Pump B and C Discharge Pressure -
High" should have the same allowable value as item A.2.f "LPCI Pump A Discharge Pressure - High" which is 115-135 psig, increasing.
2.
Table 3.3.3-3 " Emergency Core Cooling System Response Times" gives the LPCI A & B Pump response time as < 45 seconds.
Table 6.3-1 of the FSAR states that LPCI rated flow is achieved in < 40 seconds for the DBA analysis. The specifi-cation should be changed to read < 40 seconds.
O e
6 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 5 WB4 g
MEMORANDUM FOR:
R. W. Housto'n, As'sistant Director for Reactor Safety Division of Systems Integration FROM:
Faust Rosa, Chief, Instrumentation & Control Systems Branch Division of Systens Integration
SUBJECT:
RE-REVIEW OF GRAND GULF TECHNICAL SPECIFICATIONS
Reference:
Memorandum from F. Rosa to C. Thomas, dated October 31,1983,
Subject:
Grand Gulf-Unit 1 ;
ICSB Review of Technical Specifications.
The Instrumentation and Control Systems Branch (ICSB) has re-reviewed the Grand Gulf technical specifications to verify that the technical spa cifications were properly derived from the analyses and evaluation inci, ded in the FSAR as reviewed in the staff's SER.
As Enclosure 1. I am providing our comments and recommendations for changes resulting from our, review. As Enclosure 2, I am providing a list of the technical specifi-cations reviewed by the ICSB.
Of the 14 items included in Enclosure 1,13 were previously identified in the referenced memorandum.
Items numbered 3 4 and 9 have been modified to 3
reflect additional information received subsequent to the issuance of the referenced memorandum.
It is our understanding that the 13 items are cur-rently being reviewed by the licensee, however, none have been reso1'ved and/or included in the Grand Gulf Technical Specifications to date.
Item number 14 is new, having evolved from our review of a technical specifica-tion change requested by the applicant.
With the exception of the items identified in Enclosure 1, the ICSB has determined that the Grand Gulf-Unit 1 Technical Specifications are accep-table.
4 Faust Rosa, Chief Instrumentation & Control Systems Branch Division of Systems Integration
Enclosures:
As stated cc:
R. Capra e
M.
ICSB COMMENTS AND RECOMMENDED CHANGES FOR THE GRAND GULF-UNIT 1 TECHNICAL SPECIFICATIONS
~
1.
By memorandum dated December 3'0, 19'82, from R. Mattson to D. Eisenhut the ICSB proposed technical specification changes to address the opera-bility'of the remote shutdown systens required under the provisions of GDC 19.
These changes impose limiting conditions for operation and surveillance requirements on transfer switches, control circuits and both channels of monitoring instruments for the remote shutdown system.
It was recommended in the December 30, 1982, memorandum that these changes be implemented immediately on OL reviews. Therefore, Section 3/4.3.7.4 of the Grand Gulf-Unit 1 Technical Specifications should be modified to include these recommendations.
2.
By memorandum dated October 12, 1983, from R. Mattson to D. Eisenhut the ICSB proposed technical specification changes to address the opera-bility of the post accident monitoring instrumentation required under the provisions of NUREG-0737 Supplement #1.
These changes update the Standard Technical Specifications to reflect the Regulatory Guide 1.97, Revision 2 graded approach to operability requirements depending on the importance to safety of the measurement of a specific variable.
It was recommended in the October 12, 1983, memorandun that these changes be im-pienented immediately on OL reviews. Therefore, Sections 3/4.3.7.5 and 6.8.3 of the Grand Gulf-Unit 1 Technical Specifications should be modified to include these recommendations.
, 3.
Current surveillance requirements for the reactor protection system (i.e.,
I reactor trip, engineered safety features actuation and supporting features)
~
and the reactor core isolation cool'ing system specify testing of the final
{actuationlogic(i.e.,theANDfunctionoftheone-out-of-twotakentwice i
logic: A. or C AND B or D) at refueling outage intervals. This actuation 3/4 3 1 treuitry (including the circuits associated with supporting features)
WO l
should be tested more frequently (e.g., semi-annually) commensurate with 3/y 3. 5 1 the importance of the safety functions perfonned by these systems.
By letter dated October 13, 1983 from A. Schwencer (NRC) to J. P.
McGaughey (MP&L) the NRC staff requested additional information re-j garding the frequency of testing actuation circuitry.
By letter dated l
February 17, 1984 from G. F. Dale (MP&L) to H. Denton (NRC) the licensee l
proposed to provide additional information on test intervals by March 2, l
1984.
The completion of the ICS8's review of the technical specifications is pending receipt and review of this information.
4.
The ICSB has identified deficiencies in the method used to establish 2,,1 the protection system trip setpoints and allowable values contained in the technical specifications for recent BWR OLs. The licensee is currently participating in a BWR Owners Group study on instrument i
setpoints and will be providing a setpoint methodology position state-
~
3 ment. At this time we have identified one deficiency in the setpoint methodology used for Grand Gulf involving the treatment of trip unit drift. The numerical difference between the technical specification's trip setpoints and allowable vilues,should be that quantity of the in-strument uncertainty allotted for the trip unit drift and calibration ac-curacy., The numerical difference between the trip setpoints and allowable g
values for Grand Gulf include both trip unit drift and sensor drift. This
+
insufficient drift allowance at the allowable value could permit continued 3/431 operation with instrtment channels that would not actuate safety systems to 1
terminate transients or mitigate accidents within the bounds specified in the FSAR analyses. Therefore, the Grand Gulf-Unit 1 Technical Specifica-tion's tri,p setpoints and allowable values should be revised to include an allowance for only the drift associated with that portion of the instrument channel tested at 31 day intervals (i.e., trip unit) and an allowance for trip unit calibration inaccuracy between the trip setpoint and the allow-able value.
Additional changes to the Grand Gulf-Unit 1 Technical Speci-fications may be required following our review of the licensee's method-ology position statement.
5.
By letter dated October 11, 1983 from J. McGaughy (MPAL) to H. Denton 3/4. 3. =
(NRC) the licensee proposed changes to the Grand Gulf-Unit 1 Technical Specifications that address the RCIC_ actuation instrumentation. We have reviewed the proposed changes and found them acceptable.
A discussion on the proposed changes is contained in the ICSB input to Supplement No. 5 of the SER.
The Grand Gulf-Unit 1 Technical Specifications should be revised accordingly.
. 6.
By letter dated October 14, 1983 from L. Dale (MP&L) to H. Denton the licensee committed to propose revisions to the Grand Gulf-Unit 1 Tech-l nical Specifications. The proposed, changes will require more frequent y4,3,7 calibrations of camponents in the containment isolat, ion actuation instru-mentation. We have reviewed the proposal and found it acceptable. A discussion on the proposal is contained in the ICS8 input to Supplement No. 5 of the SER.
The Grand Gulf-Unit 1 Technical Specifications should T
be revised accordingly.
7.
The Bases Section for Specification 3/4.3.1 entitled " Reactor Protection j
System Instrumentation" includes the following statement: "The system meets the intent of IEEE 279 for nuclear power plant protection systems".
"sM 8:
We recomend that this statement be deleted. A detailed discussion on f
the conformance of the Grand Gulf-Unit 1 design to the NRC's regulatory requirements is contained in the SER.
8.
Technical Specification 3/4.3.8 entitled " Plant Systems Actuation Instrumentation" includes the requirements applicable to the. containment spray system. By letter dated Septa ber 12, 1983, from L. Dale to H.
Denton the licensee identified a potential problem with regard to the minimum operable channels requirments of the Grand Gulf-Unit 1 Technical Specifications that address this systen.
It appears that the requirements
i '
address only one-half of the instruments provided. The licensee has stated that the worst case single failure,would be limited to the disabling of the initiation of one spray loop.when. operating with one-half of the instruments provided. The system has been designed such that any single failure within the actuation instrumentation will not prevent actuation at the systems level when all of the actuation instruments provided are operable. There-fore, to enhance plant safety we recommend that the minimum channels oper-able requirement for the drywell pressure high, containment pressure high and reactor vessel low actuation signals be revised from the present one per trip system to two per trip system and that an appropriate action statement be developed to address operation with one or more channels per trip system inoperable.
9.
Specification 3/4.3.1 entitled." Reactor Protection System Instrumentation" and Specification 3/4.9.1 entitled " Reactor Mode Switch" address the oper-ability requirements and surveillance requirements for the reactor mode switch. The requirements address only those circuits associated with the shutdown and refuel position. The mode switch is provided to select the protective functions appropriate for each mode of reactor operation -
shutdown, refueling, startup and power operations.
In addition to the protective functions of reactor trip (six trip inputs) and primary con-tainment isolation (one trip input) the mode switch enables / bypasses
. control rod blocks, operation of the suppression pool makeup system, re-fueling interlocks and monitoti.ng functions which are provided to con-trol operations within prescribed bounds. Therefore, we recommend that the Grand Gulf-Unit 1 Technical Specifications include limiting condi-tions for operation and surveillance requirements that include consider-ation of the other safety-related functions accomplished by the mode switch.
- 10. Specification 3/4.7.1 entitled " Service Water Systems" addresses the surveillance requirements for the standby service water (SSW) system.
These requirments include a periodic demonstration of the operabil-ity of the circuits that automatically reposition valves servicing safety-related equipment. The SSW system (including the SSW pumps, SSW cooling tower fans and automatic system valves) is initiated auto-matically upon occurrence of a LOCA or startup of any of the ESF sys-tens it serves.
In addition, the SSW systen is initiated automat-ically on a loss of offsite power through the associated load sequenc-ing circuits. Currently the Grand Gulf-Unit 1 Technical Specifica-tions address only those circuits associated with the SSW systan's valves. To ensure the operability of the automatic actuation of the SSW system pumps and cooling tower fans we recommend that Specifica-tion 4.7.1.1 be revised to include periodic testing of the actuation circuitry for these components.
- 11. Specification 3/4.6.3 entitled " Suppression Pool" addresses the opera-bility requirements and surveillanc'e requirements for the suppression pool. This specification does not address the suppression pool make-up system. The suppression pool makeup systen provides water from the upper containment pool to the suppression pool by gravity flow after a LOCA and is classified as an ESF system at Grand Gulf.
The system is automatically initiated 30 minutes after a LOCA is detected or on a low-low suppression pool level following a LOCA.
The suppression pool makeup system consists of two independent and redundant subsystems.
The ' actuation logic for each subsystem is a one-out-of-two arrangement of level sensors. We recommend that appropriate Grand Gulf-Unit 1 Techni-cal Specification limiting conditions for operation and surveillance requirements be developed to address this ESF system.
- 12. Specification 3/4.7.3 entitled " Reactor Core Isolation Cooling System" addresses the operability of the reactor core isolation cooling system (RCIC). The design of the RCIC system includes protective features to automatically shut down the turbine by tripping the trip and throttle valve closed if any of the following conditions are detected: turbi ne overspeed, high turbine exhaust pressure, RCIC isolation signal from logic A or B, or low pump suction pressure. To ensure the reliability of these features, the availability of RCIC system and to enhance plant
safety these features should be included in the operability and surveil-lance requirements.
- 13. The high pressure / low pressu syskem interlocks prevent overpressuriza-tion of the low pressure systems that connect to the reactor coolant pressure boundary. Specification 3/4.4.3.2 entitled " Reactor Coolant System Leakage" address the operability of the isolation valves with respect to leak-tight integrity and the instrumentation provided to monitor valve leakage, however, this specification does not address the valve interlocks.
The following valves are interlocked to prevent valve opening until pressure permissives are satisfied: E12-F009, E12-F008, E12-F053, E12-F023. E12-F087, and E38-F001. To ensure the reliability of these features and to enhance plant safety we recommend that appropriate limiting conditions for operation and surveillance re-quirements be included in the Grand Gulf-Unit 1 Technical Specifications.
- 14. By [[letter::AECM-83-0508, Updated RO 83-052/1:on 830523,fire-rated Penetrations Opened to Implement Design Change Package Per Tech Specs. Penetrations Resealed.Last Penetration Restored on 830829|letter dated September 12, 1983]] from A. Schwencer (NRC) to J. Mc Gaughey (MP&L) the NRC staff requested additional information to re-s 3(3[
solve concerns regarding the minimum number of operable instrument 3/930 channel requirements contained in the Grand Gulf Technical Specifica-tions, and additional information regarding the licensee's interpreta-tion of the definition of the terms " trip functions", " channel" and
" trip systems" contained in the Grand Gulf technical specifications.
By [[letter::AECM-83-0508, Updated RO 83-052/1:on 830523,fire-rated Penetrations Opened to Implement Design Change Package Per Tech Specs. Penetrations Resealed.Last Penetration Restored on 830829|letter dated September 12, 1983]] from L. F. Dale (MP&L) to H. Denton
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GRAND GULF - UNIT 1 TECHNICAL SPECIFICATIONS SECTIONS REVIEWED BY ICSB 1.0 Definitions --
2.2.1 Reactor Protection System Instrumentation 3/4.1.3.5 Control Rod Position Indication 3/4.1.4.2 Rod Pattern Control System 3/4.3.1
, Reactor Protection System Instrumentation 3/4.3.2 Isolation Actuation Instr'umentation 3/4.3.3
. Emergency Core Cooling System Actuation Instrumentation 3/4.3.4 Recirculation Pump Trip Actuation Instrumentation 3/4.3.5
/ Reactor Core Isolation Cooling System Actuation Instrumentation 3 /4.3.6 Control Rod Blo:k Instrumentation 3/4.3.7.4 Remote Shutdown Monitoring Instrumentation 3/4.3.7.5 Accident Monitoring Instrumentation 3/4. 3.7. 6 Source Range Monitors 3/4.3.7.7 Traversing In-Core Probe System 3/4.3.8 Plant Systems Actuation Instrumentation 3/4.6.3.1 Suppression Pool 3/4.7.1 Service Water Systems 3/4.7.3 Reactor Core Isolation Cooling System 3/4.4.3 Reactor Coolant System Leakage 3/4.4.2.2 Safety Relief Valves Low-Low Set Function 3/4.9.1 Reactor Mode Switch to 8.3 P r oceou ecs + 7<cv ans
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UNITED STATES t
NUCLEAR REGULATORY COMMISSION
{..
WASHINGTON, D. C. 20555'
. (.....j MAR 7 1984 MEMORANDUM FOR:
R. Wayne Houston, Assistant Director for Reactor Safety, DSI FROM:
Walter R. Butler, Chief, Containment Systems Branch, DSI
SUBJECT:
CSB RELATED INPUT RE:
RE-REVIEW OF THE GRAND GULF, UNIT 1 TECHNICAL SPECIFICATIONS (TAC 754185)
Reference:
- Memorandum from R. J. Mattson to R. W. Houston et al, dated February 27, 1984 The Containment Systems Branch (CSB) has cogleted its re-review of the Technical 1
Specifications. (TS) for Grand Gulf, Unit 1.
The objective of the re-review was to verify that the TS were properly derived from the analyses and evaluations included in the FSAR.
The CSB review was focused on TS Section 3/4.6 as it compares with FSAR Section 6.2.
Enclosure (1) identifies the specific TS sections that were reviewed by the CSB.
Enclosure (2) identifies differences between the TS and FSAR.
Enclosure (3) contains our recommended changes for the Grand Gulf TS, assuming the recommenda-i tions from our last TS review (November 1983) will be adopted. These prior c,hanges have not been incorporated in the present version of the TS.
We consider the most significant finding from our TS re-review to be the non-implementation of our prior recommendations.
Another, item that was uncovered during the re-review is an apparent discrepancy in the acceptance value of the inleakage for the secondary containment.
TS Surveillance Requirements Section 4.6.6.1.b.2 indicates a flow rate of 4000 cfm.
Based on conversations with the AEB, the flow rate.should be changed to 2300 cfm to be consistent with the AEB evaluation. This item will be discussed further
(
with the applicant and AEB to assure proper implementation into the TS of the more conservative value.
There also were several numerical discrepancies as identi-l fied in Enclosure (2). We consider these differences to have no impact on containment response analyses and therefore no changes to the TS are recommended.
- The CSB has also reviewed the TS basis section which summarizes the reasons for the specifications.
The TS basis section is not part of the TS.
However, for
. completeness, we had reviewed this section which correspends to the topics in i..
Enclosure (1).
Certain parameters in basis Sections 3/4.6.1.7, 3/4.6.2. 5 and 3.4.6.3 do not appropriately reflect the main TS sections. Accordingly, we recommend the following changes:
CONTACT:
A. Notafrancesco I
x29486 N
R. Wayne Houston (1)
Regarding basis section 3/4.6.1.7, the containment to auxiliary building differential pressure is limited to -0.1 and 1.0 psid rather than -2.0 to 0. psid.
(2)
Regarding basis section 3/4.6.2.5, the maximum external drywell pressure differential is limited to 0.1 psid rather than 1.0 psid.
(3)
Regarding basis section 3/4.6.3, the minimum suppression pool volume should be 135,291 cubic feet rather than 136,146 cubic feet.
Walter R. Butler, Chief Containment Systems Branch Division of Systems Integration
Enclosures:
As stated cc:
R. Capra D. Houston D. Hoffman J. Read T. Quay A. Schwencer l
l ENCLOSURE (1)
GRAND GULF, UNIT 1 - TECHNICAL SPECIFICATIONS:
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS THE CONTAINMENT SYSTEMS BRANCH SCOPE OF REVIEW:
3/4.6.1 PRIMARY CONTAINMENT 3.6.1.1 Primary Containment Integrity 3.6.1.2 Containment Leakage 3.6.1.3 Containment Air Locks 3.6.1.5 Feedwater Leakage Control System 3.6.1.6 Containment Structural Integrity 3
3.6.1.7 Conta'inment Internal Pressure 3.6.1.8 Containment Average Air Temperature 3.6.1.9 Containment Purge System 3/4.6.2 DRYWELL
- 3. 6. 2.1 Drywell Integrity 3.6.2.2 Drywell Bypass Leakage 3.6.2.3 Drywell Air Locks 3.6.2.4 Drywell Structural Integrity 3.6.2.5 Drywell Internal Pressure 3.6.2.6 Drywell Average Air Temperature 3/4.6.3 DEPRESSURIZATION SYSTEMS
- 3. 6. 3.1 Suppression Pool 3.6.3.2 Containment Spray 3.6.3.3 Suppression Pool Cooling
.i 3.6.3.4 Suppression Pool Makeup System I
3/.4.6.4 CONTAINMENT AND DRYWELL ISOLATION VALVES 3/4.6.5 DRYWELL POST-LOCA VACUUM BREAKERS 3/4.6.6 SECONDARY CONTAINMENT 3.6.6.1 Secondary Containment Integrity 3/4.6.7 ATMOSPHERE CONTROL 3.6.7.1 Containment and Drywell Hydrogen Recombiner Systems 3.6.7.2 Containment and Drywell Hydrogen Ignition System 3.6.7.3 Drywell Purge System
- 5. L c e wT m, w %T
ENCLOSURE (2)
GRAND GULF TECHNICAL SPECIFICATIONS /FSAR COMPARISON 3 /4. 6.3 (1) Maximum suppression pool water volume:
Tech.' Spec. Page 3/4 6-20
/
FSAR Table 6.2-50 138,851 cubic feet 138,701 cubic feet (2)
Max / Min equivalent suppression pool water level:
Tech. Spec. Page 3/4 6-20
/
FSAR Table 6.2-50 18'10" 18'9-3/4" 18'4-3/4" 18'4-1/12" o
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