ML20133A960

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Responds to 840227 Memo Re re-review of Tech Specs Including Applicable Bases Section in Power Sys Branch Areas of Responsibility.Tech Specs Acceptable W/Noted Exceptions
ML20133A960
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 03/08/1984
From: Rubenstein L
Office of Nuclear Reactor Regulation
To: Mattson R
Office of Nuclear Reactor Regulation
Shared Package
ML19276B572 List: ... further results
References
FOIA-84-459 NUDOCS 8507200199
Download: ML20133A960 (10)
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  1. 'n NUCLEAR REGULATORY COMMISSION l; *

/.t WASWNGTON, D. C. 20555 +.... March 8, 1984 MEMORANDUM FOR: Roger J. Mattson, Director Division of Systems Integration FROM: L. S. Rubenstein, Assistant Director for Core and Plant Systems, DSI

SUBJECT:

RE-REVIEW OF GRAND GULF TECHNICAL SPECIFICATIONS As requested by your memorandum dated February 27, 1984 we have re-reviewed the following sections of the Grand Gulf Technical Specifications, including the applicable bases section, which are in the Power Systems Branch (PSB) j areas of primary responsibility. TABLE 3.3.3-1 ENERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION D. LOSS OF' POWER TABLE 3.3.3-2 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS D. LOSS OF POWER TABLE 4.3.3.1-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS D. LOSS OF POWER 3/4.8.1 A.C. SOURCES 3/4.8.2 D.C. SOURCES 3/4.8.3 ONSITE POWER DISTRIBUTIDN SYSTEMS 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES The Technical Specifications as written do not include the surveillance requirements for the turbine overspeed protection system. It is our understanding that these Technical Specification requirements were inadvertently deleted fram the original Grand Gulf Technical Specifications Contact. S. Rhow, x28698 R. Giardina, x24953 8507200199 850515 PDR FOIA BELL 84-459 PDR

March 8,19@4 Roger J. Mattson : issued in June,1982. Therefore, we require that these Technical Specifications be reinstated into the Plant Technical Specifications. Because of the unique-ness of the Grand Gulf Turbine Generator system, the wording of the turbine overspeed protection system surveillance requirements should be the same as the Commanche Peak turbine overspeed surveillance requirements which has the same type of turbine generator system. Based on our review, we conclude that the Grand Gulf Technical Specifications are acceptable except as noted above and in the attached marked up sectionfof the Technical Specification. Enclosed are copies of those specifications I which have been marked with the appropriate corrections to bring them into conformance with the Standard Technical Specification and the FSAR. n tW stant Director R for Core and Plaht Systems Division of Systems Integration Enclosure : As stated cc w/

Enclosure:

R. Capra M. Srinivasan J. E. Knight A. Ungaro R. Giardina S. Rhow 

)

TABLE 3.3.3-1 (Continued) EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION 8 MINIMUM OPERA 8LE APPLICABLE G, CHANNELS PER ,0PERATIONAL-TRIP, FUNCTION,) CONDITIONS ACTION g a TRIP FUNCTION z U C. DIVISION 3 TRIP SYSTEM 1. HPCS SYSTEM i a. Reactor Vessel Water Level - Low, Low, Level 2 4 1,2,3,4*,5* 33 l 1 b. Drywell Pressure - High## 4 1, 2, 3 33 2(gc) 1, 2, 3, 4 *, 5* 31 c. Reactor Vessel Water Level-High, Level 8 2(d) 1, 2, 3, P, 5* 34 i d. Condensate Storage Tank Level-Low d) e. Suppression Pool Water Level-High 2 1, 2, 3, 4*, 5* 34 l f. Manual Initiation ## 1/ system 1, 2, 3, 4*, 5* 32 D. LOSS OF POWER + i -1i Olvision 1,and 2.gn.4 3. m) a. 4.16 kV Bus Undervoltage 4 1, 2, 3, 4**, 5** 30 (Loss of Voltage) m4 b. 4.16 kV Bus Undervoltage 4 1, 2, 3, 4**, 5** 30 (BOP Load Shed) m c. 4.16 kV Bus Undervoltage 4 1, 2, 3, 4**, 5** 30 -l (Degraded Voltage) i <2r Divrsion-3 kY de af g(L ss.o ltygdf D.'vidon 3 S houlol h a v4.

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5"" M i prolelNe i V ag 4bne undervoit. e t yt,lm s, s a ni<. as tw. i e' a.s (a) A channel may be placed in an inoperable status for up to 2 hours during periods of required i g surveillance without placing the trip system in the tripped condition provided at least one g other OPERABLE channel in the same trip system is monitoring that parameter. i Q (b) Also actuates the associated division diesel Generator. 4 l, g (c) Provides signal to close HPCS pump discharge valve only. (d) Provides signal to HPCS pump suction valves only. j g: (e) One out-of-two taken. Appilcable when the system is required to be OPERABLE per Specification 3.5.'2 or 3.5.3., t Required when ESF equipment is required to be OPERABLE. om f Not required to be OPERABLE when reactor steam done pressure is less than or equal to 135 psig. i ,o Prior to STARTUP following the first refueling outage, the injection function of Drywe11 Pressure - High and Manual Initiation are not required to be OPERA 8LE with indicated reactor vessel water level on the wide range instrument Dreater than Level 8 setpoint coincident with the reactor pres sure less than 600,eia. p pg ~.... ~,.

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GRAND GULF-UNIT 1 3/4 3-29 M.endment Nc. S l Novem::er IS,1982 3+- w,%e- --+<-y-. m- ~ - - + - - - - - - ---s t--- + - - - - - - - - -

~ I t TABLE 4.3.3.1-1 (Continued) ~ EMERGENCY CORE COOLING SYSTEM AC10AT10N INSTRUMENTATION SURVEILLANCE REQUIREMENTS h CHANNEL OPERATIONAL CilANNEL IUNCTIONAL CilANNEL CONDITIONS FOR WillCil c,p TRIP FUNCTION CilECK TEST CALIBRATION SURVEILLANCE REQUIRED T B. OlVISION 2 TRIP SYSTEM (Continued) l E 2. AUTOMATIC DEPRE$$URIZATION SYSTEM

  • 1 TRIP SYSTEM "a"#

g a. Reactor Vessel Water Level - R,,) 1, 2, 3 g Low Low Low, Level 1 S M g) b. Drywell Pressure-liigh 5_ M R 1, 2, 3 c. ADS Timer NA M Q 1, 2, 3' l d. Reactor Vessel Water Level - I R *) 1, 2, 3 i Low, level 3 S M e. LPCI Pump 8 and C Discharge i Pressure-liigh 5 M(b) R(,) 1, 2, 3 f. Manual Initiation NA R NA 1,2,3 C. DIVISION 3 TRIP SYSTEM 1. IIPCS SYSTEM w1 a. Reactor Vessel Water Level - II R(*a) 1, 2, 3, 4*', 5* Low Low, Level 2 S M l w /, b. Drywell Pressure-liighf# 5 M R *) 1, 2, 3 I c. Reactor Vessel Water S H R 1, 2, 3, 4 *, 5* Level-liigh, Level B d. Condensate Storage Tank Level - Low S M Rf*) 1, 2, 3, 48, 5* e. Suppression Pool Water I) Level - liigh S M(b) R 1, 2, 3, 4 *, 5* l f. Manual Initiation ## NA R NA 1, 2, 3, 4 *, S* D. LOSS OF POWER 1. Division 1 e8d 2 ctws/ J l 3, I M *I R 1, 2, 3, 4**, 5** 2 a. 4.16 kV Bus Undervoltage NA R (Loss of Voltage) M *) R 1, 2, 3, 4**, 5** l I 2 h. 4.16 kV Bus Undervoltage NA f. (B0P Load Shed) i z c. 4.16 kV Bus Undervoltage NA M(*) R 1, 2, 3, 4**, 5** i Degraded Voltage) P D[vis'(ion 3' 2. -y oo ~ /a./ 4.16 kV B d Un'd rvaltape, 'lA ~~ ^ NA,~ 'R 1, 2, 3;'4T5** .t; (Loss of Vo!i.a e)' O %dp bNo f( u,wAc,oseIa.gg prog,ej,gg Te I A 'l ?. 54e,ge as D,t/. I a. <4 3 f.[~R.-.f5hQ

3/4.8 ELECTRICAL PCWER SYSTEMS 3/4.8.1 A.C. SOURCES A.C. SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE: a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system, and b. Three separate and independent diesel generators, each with: 1. Separate day fuel tanks containing a minimum of 220 gallons of fuel. 2. A separate fuel storage system containing a minimum of: a) 48,000 gallons of fuel each for diesel generators 11 and 12, and b) 39,000 gallons of fuel for diesel generator 13. 3. A separate fuel transfer pump. APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. ACTION: a. With either one offsite circuit or diesel generator u or 12 of the above required A.C. electrical power sources inoperable, demonstrate the OPERASILITY of the remaining A.C. sources by performing Surveil-lance Requirements 4.8.1.1.1.a with'- ---L jind 4.8.1.1.2.a.4, f:r r.; di t :1 r iw * ;; - ti g within and at least once per 8 hours therafter; restore at least two offsite circuits and diesel generators n and 12 to OPERABLE status within 72 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours. b. With one offsite circuit and diesel generator u or 12 of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by perfoming Surveillance Requirements 4.8.1.1.1.a wi nin.cn-V nd 4.8.1.1.2.a.4, & di;;el gweui.~ ime, within ( OEf and at least once per 8 hours thereafter; restore at least one of the inoperable A.C. sources to OPERABLE status within 12 hours or be in at least HOT SHUT-DOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours. Restore at least two offsite circuits and diesel genera-tors n and 12 to OPERABLE status within 72 hours from time of initial loss or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours. b"h "f h in a ce.rda.ve.d rh %* r " % d ~.f*'- GRAND GULF-UNIT 1 3/4 8-1 Amendment No. 8, 9

ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) h,At least oncf per 92 day F nd from n oil prior to addition to the j Vstor ge tanks by veri,fyi that a,s'am e obtaji e6 in accordan'ce with ld a ki,56 dime t cont (nt o)f less th'anfo AS -0270-19'75 has,4 wat jMg7 ' and to.05' voldme perient af cvisedsitys40*f/ofgreaterthan nema M or eq'ual,t'o 1.9 w th ASTM-097,/6ut less thd1 or ual,td 4.1ess+festedinacondance hen f 4 h~g q 4 ,e/100/ml. hen testVin accor an with TM-2274-70, cept (that 77, and ao/ mpuri le 1 of i an 2 mg. insolubles the test new fuel for impurity evel sh 1 e performed within\\7 days after a ition of the new fuel to the storage tank.

e. f.

At least once per 18 months, during shutdown, by: f Subjecting the diesel to an inspection in accordance with pro-1. cedures prepared in conjunction with its manufacturer's recom- ~ mandations for this class of standby service. 2. Verifying the diesel gene capability to reject a load of o greater than or equal to (LPCS Pump) for diesel generator 11, greater than or equal to kW (RHR B/.C Pymp) for ciesel e 0 of generator 12, and greater than or equal to 2585 kW (HPCS Pump) -2 p$o wI for diesel generator 13 while maintaining less than or equal to e

  • i 75% of the difference between nominal speed and the overspeed

~~ o trip setpoint, or 15% above nominal, whichever is less. [s 3. Verifying the diesel generator capability to reject a load of 7000 kW for diesel generators 11 and 12 and 3300 kW for diesel 7 of D generator 13 without tripping. The generator voltage shall not i$ exceed 5000 volts during and following the load rejection. Simula'tYnN loss of offsite power by itself, and: 4.

  • f a)

For Diviisions 1 and 2: ~5 ' 1) Verifying deenergization of the emergency busses and + load shedding from the emergency busses. 2) Verifying the diesel generator starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the auto-connected shutdown loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After ener-giration, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 416 volts and 60 1.2 Hz during this test. b) For Division 3: 1) Verifying de-energization of the emergency bus. 2) Verifying the diesel generator starts on the auto-start signal, energizes the emergency bus with the loads within 10 seconds and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After energization, the steady state voltage and frequency of the emergency bus shall be maintained at 4160 416 volts and 60 1.2 Hz during this test. GRAND GULF-UNIT 1 3/4 8-4 Amencment No. 8, 9

o' J ELECTRICAL POWER SYSTEMS (dSURVEILLANCEREQUIREMENTS(Continued) 4 C. 8. Verifying that all automatic diesel generator trips cre '] automatically bypassed upon an ECCS actuation s gnal except: a) ForDivisions1and2,engineoverspeedgenerator j differential current, 5: hi..l,,,,....,......_ 2 g" g - d : .. z... -h b) For Division 3, engine overspeed and generator differential g,- current. f f (' 9. Verifying the diesel generator operates for at least 24 hours. el During the first 2 hours of this test, the diesel generator shall ?- be loaded to greater than or equal to 7700 kW for diesel gen- .51 erators 11 and 12 and 3630 kW for diesel generator 13 and during t 31 the remaining 22 hours of this test, the diesel generator shall . be loaded to 7000 kW for diesel generators 11 and 12 and 3300 kW for diesel generator 13. The generator voltage and frequency shall be 4160 1 416 volts and 60 2 1.2 Hz within 10 seconds after the start signal; the steady state generator voltage and frequency shall be maintained within these limits during this test. Within 5 minutes after completing this 24-hour test, perform Surveillance Requirement 4.8.1.1.2.d.7.a).2) and b).2)". 50. Verifying that the auto-connected loads to each diesel generator do not exceed the continuous rating of 7000 kW for diesel generators 11 and 12 and 3300 kW for diesel generator 13. 11. Verifying the diesel generator's capability to: Wi a) Synchronize with the offsite power source while the generator Y! is loaded with its emergency loads upon a simulated 4-restoration of offsite power, ff b) Transfer its loads to the offsite power source, and !fj c) Se restored to its standby status. d ' e.I 12. Verifying that with the diesel generator operating in a test mode and connected to its bus that a simulated ECCS actuation t ,g j+ signal,: -stC For Divisions 1 ant ( 2 -overrides the test mode by return-b+!. f v5 "eb. k

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he e w r e. 3,..m u t. 2.. c _c. e s c we If di d;1 ;;r,;r:. ton.Iutosufic_.tfips per Surveil) hee'Requi're-4,c. ment 4.8.1.1'.2.d{8.b). e+ s 3I Verifying that with all diesel generator air start receivers 13. pressurized to less than or equal to 256 psig and the compres-sors secured, the diesel generator starts at least 5 times from i ambient conditions and accelerates to at least 441 rpm for diesel generators 11 and 12 and 882 rpm for diesel generator 13 in less than or equal to 10 seconds. = 1 If Surveillance Requirement 4.8.1.1.2.d.4.a)2) or b)2) are not satisfactorily completed, it is not necessary to repeat the preceding 24 hour test.

Instead, the diesel generator may be operated at rated load for one hour or until operating tempera'.ures have stabilized.

GRAND GULF-UNIT 1 3/4 8-6 Amendment No. 8, 9 6

. ~ - -. - ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued l t i 14. Verifying that the fuel transfer pump transfers fuel from each fuel storage tank to the day tank of each diesel via the 1 installed lines. 15. Verifying that the automatic load sequence timer is OPERABLE with the interval between each load block within 210% of its j design interval for diesel generators 11 and 12. 16. Verifying that the following diesel generator lockout features prevent diesel generator starting and/or trip the diesel generator only when required: a) Generator loss of excitation, b) Generator reverse power. c) High jacket water temperature. d) Generator overcurrent with voltage restraint. e) Bus underfrequency (11 and 12 only). f) Engine bearing temperature high (11 and 12 only). g) Low turbo charger oil pressure (11 and 12 only). l h) High vibration (11 and 12 only). i) High lube oil temperature (11 and 12 only). j) Low lube oil pressure (13 only). k) High crankcase pressure, fE: At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting all three diesel generators simultaneously, during shutdown, and verifying that the three diesel generators accelerate to at least 441 rps for diesel generators 11 and 12 and 882 rps for diesel generator 13 in less than or equal to 10 seconds. g /. At least once per 10 years by: 1. Oraining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite or equivalent solution, and i 2. Performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection N0 of the ASME Code in accordance with ASME Code Section 11, Article IWD-5000. 1 4.8.1.1.3 Reports - All diesel generator failures, valid or non-valid, shall be reported to the Commission pursuant to Specification 6.9.1. Reports of diesel generator failures shall include the information recommended in Regu-i i latory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977. If the number of failures in the last 100 valid tests, on a per nuclear unit basis, is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977. GRAND GULF-UNIT 1 3/4 8-7 Amendment No. 8, 9

3 A ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS 4.8.2.1 Each of the above required 125-volt batteries and chargers shall be demonstrated OPERABLE: a. At least once per 7 days by verifying that: '1. The parameters in Table 4.8.2.1-1 meet the. Category A limits, and ' 2. Total battery terminal voltage is greater than or equal to 129-volts on float charge. b. At least once per 92 days and within 7 days after a battery discharge with battery terminal voltage below 110-volts, or battery overcharge with' battery terminal voltage above 150-volts, by verifying that: 1-The parameters in Table 4.8.2.1-1 meet the Category B limits, 2. There is no visible corrosion at either terminals or connectors, or the connection resistance of these items is less than 150 x 10 8 ches, and I 3. The average electrolyte temperature of every sixth connected cells is above 60*F. c. At least once per 18 months by verifying that: 1. The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, 2. The call-to-cell and terminal connections are clean, tight, i free of corrosion and coated with anti-corrosion. material, 3. The resistance of each cell and terminal connection is less than or equal to 150 x 10 s ohns, and 1 4. The battery charger will supply: a) For Divisions 1 and 2, at least 400 amperes at a minimum of M volts for at least t hours. /25 8 b) For Division 3, at least 50 amperes at a minimum of 105 volts for at least 2 hours. /25 Y ( l ' mcu h o d - u.F ik :.i ac c e,-4,a.::.e e 4 1, t 5,, { GRAND GULF-UNIT 1 3/4 8-11 Amendment No. 8, 9

ma an '/ ' ' og'o,, UNITED STATES 8 NUCLEAR REGULATORY COMMISSION d U L ~ g L y WASHINGTON, D. C. 20555 %,....../ MAR 8 1984 MEMORANDUM FOR: "R.'J.'Mattson, lems Integration, NRR Director 'DiiIisfon of 'Sys THRU: L. S. Rubenstein, Assistant Directo d for Core and Plant Systems, DSI I FROM: C. H. Berlinger, Chief Core Perfonnance Branch, DSI

SUBJECT:

RE-REVIEW OF GRAND GULF TECHNICAL SPECIFICATIONS

Reference:

1. Memorandum from R. J. Mattson to R. Houston, et al, dated February 27, 1984,

Subject:

Re-Review of Grand Gulf Technical Specifications. The Core Pe'rformance Branch has completed the re-review of Grand Gulf Technical Specifications as requested by Reference 1. Enclosed is a list of specifications reviewed. Those specifications listed for wnich no comments are enclosed are acceptable as is. (. l 'f su ~ ~ 4. H. Berlinger, hief Core Perfomance Branch, DSI

Enclosure:

As stated cc: L. Rubenstein D. Eisenhut T. Novak R. Capra D. Brinkman C. Thomas

Contact:

S. Sun, CPS:DSI X-29499 h

j l ENCLOSURE 1 Technical Specifications Re-Review By The Core Perfomance Branch for Grand Gulf Unit 1 I. Definitions: 1.2 Average Planar Exposure 1.3 Average Planar Linear Heat Generation Rate 1.7 Core Alteration 1.8 Critical Power Ratio 1.14 Fraction of Limiting Power Density 1.15 Fraction of Rated Themal Power 1.20 Limiting Control Rod Pattern 1.21 Linear Heat Generation Rate 1.23 Maximum Fraction of Limiting Power Density 1.24 Minimum Critical Power Ratio 1.28 Physics Tests 1.33 Rated Themal Power 1.36 Rod Density 1.38 Shutdown Margin 1.42 Themal Power II. Safety Limits 2.1.1 Thermal Power, low Pressure or low Flow 2.1.2 Themal Power High Pressure and High Flow 2.2.1 Reactor Protection System Instrumentation Setpoints (IRM and APRM only) III. Limiting Conditions for Operation and Surveillance Requirements 3/4.1.1 Shutdown Margin 3/4.1.2 Reactivity Anomalies 3/4.1.3.1 Control Rod Operability

., ~ 3/4.1.3.2 Control Rod Maximum Scram Insertion Times 3/4.1.3.3 Control Rod Scram Accumulators 3/4.1.3.4 Control Rod Drive Coupling 3/4.1.3.5 Control Rod Position Indication 3/4.1.3.6 Control Rod Drive Housing Support 3/4.1.4.1 Control Rod Withdrawal 3/4.1.4.2 Rod Pattern Control System 3/4.1.5 Standby Liquid Control System 3/4.2.2 APRM Setpoints 3/4.2.3 Minimum Critical Power Ratio 3/4.2/4 Linear Heat Generation Rate 3/4.3.1 Reactor Protection System Instrumentation (IRM and APRM only) 3/4.3.6 Control Rod Block Instrumentation 3/4.3.7.6 Source Range Monitors 3/4.3.7.7 Traversing In-Core Probe System 3/4.3.7.10 Loose-Part Detection System 3/4.4.1.1 Recirculation System 3/4.4.1.2 Jet Pumps 3/4.9.1 Reactor Mode Switch 3/4.9.2 Instrumentation 3/4.9.3 Control Rod Position 3/4.9.10.1 Single Control Rod Removal 3/4.9.10.2 Multiple Control Rod Removal 3/4.10.2 Rod Pattern Control System 3/4.10.3 Shutdown Margin Demonstrations

5. C.

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3-Comments 3/4.4 3.4.1.1 This Technical Specification, which provides limiting conditions (hours) for operation in natural circulation and with only one recirculation loop, is not sufficiently prescriptive to protect against the potential for thermal hydraulic instability. GE recently presented the staff with stability test data which denonstrated the occurrence of limit cycle neutron flux oscillations at natural circulation and several percents above the rated rod line. The oscillations were observable on the APRM's and were supressed with control rod insertion. It was predicted that limit cycle oscillations would occur at the operating condition tested, however; the characteristics of the observed oscillations were different than those previously observed at other stability tests. Namely, the test data showed that some LPRMs oscillated out of phase with the APRM signal and at an amplitude as great as six times the core average. GE is preparing a SIL for release soon to alert their plants of these new data and to reconnend actions to avoid and control abnonnal neutron flux oscillation. The applicant is required to change this specification to properly protect against the potential for thermal hydraulic instability. 3/4.2.3 3.2.3 No reference is given in the BASES for Figures 3.2.3-1 and 3.2.3-2. These curves are taken from NED0-24011, Revision 4 (January 1982) but no reference to this appears in the FSAR. wwwm-w w

TECHNICAL SPECIFICATIONS, BASES AND DEFINITIONS REVIEWED BY THE ACCIDENT EVALUATION BRANCH FOR GRAND GULF I. DEFINITIONS 1.9 Dose Equivalent I-131 1.11 E - Average Disintegration Energy 1.18 Identified leakage 1.30 Primary Containment Integrity 1.37 Secondary Containment Integrity 1.44 Ventilation Exhaust Treatment System II. LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3.7 Monitoring Instrumentation 3/4.4.3.2 Reactor Coolant System - Operational Leakage 3/4.4.5 Reactor Coolant System - Specific Activity 3/4.4.7 Reactor Coolant System - Main Steam Line Isolation Valves 3/4.6.1.2 Containment Systems - Primary Containment Leakage 3/4.6.1.4 Containment Systems - MSIV Leakage Control Systems 3/4.6.6.1 Containment Systems - Secondary Containment Integrity 3/4.6.6.2 Containment Systems - Secondary Containment Automatic Isolation Dampers / Valves 3/4.6.6.3 Containment Systems - Standby Gas Treatment System 3/4.7.2 Plant Systems - Control Roem Emergency Filtration System 3/4.9.4 Refueling Operations - Decay Time 3/4.9.7 Refueling Operations - Crane Travel 3/4.9.8 Refueling Operations - Water Level - Reactor Vessel 3/4.9.9 Refueling Operations - Water Level - Spent Fuel and Upoer Containment Fuel Storage Pools III. BASES FOR LIMITING CONDITIONS OF OPERATION AND SURVEILLANCE REQUIREMENTS Bases for all Limiting Conditions of Operations and Surveillance Requirements identified in Section II above. 9

e f'49 a ,&j jo UNITED STATES a, y, s,( 3 p, NUCLEAR REGULATORY COMMISSION L*{ j WASHINGTON, D. C. 20555 X.'.Cs4} MAR 08 E84 MEMORANDUM FOR: Roger J. Mattson, Director, DSI FROM: Daniel R. Muller, Assistant Director for Radiation Protection, DSI

SUBJECT:

RE-REVIEW 0F GRAND GULF TECHNICAL SPECIFICATIONS As directed by your February 27, 1984, and Harold Denton's February 24, 1984 memoranda, my staff has reviewed the Grand Gulf Technical Soecifica-tions to determine whether they were properly derived from the analysis and evaluation included in the applicant's FSAR and the staff's SER. I Each Branch verified the acceptability of the Specifications except for the following: 1. T.S. 3/4 7.2 Plant Systems - Control Room Emergency Filtration System is being reviewed by the AEB and METB staffs (TAC #51863). Post licensing tests indicated excessive leakage of the control room. Air flow needed to maintain the specified 1/4" differential pressure was high. In addition, the location of the air intake could result in excessive concentrations of radioactivity due to poor atmospheric diffusion. 2. An ambiguity exists between the surveillance requirements of T.S. 3/4 6.6.1 Containment Systems - Secondary Containment Integrity and T.S. 3/4 6.6.3 Containment Systems - Secondary Containment Standby Gas Treatment System. The Containment Systems Branch has the lead with AEB assisting (TAC #51956). The sections of the Technical Specifications reviewed by each Branch is attached. / Q p Daniel R. Muller, Assistant Director for Radiation Protection Division of Systems Integration

Attachment:

As Stated cc: LGHulman WPGammill FJCongel N Yd /@$ J'O

GRAND GULF TECHNICAL SPECIFICATIONS SECTIONS AND PORTIONS REVIEHED BY METEOROLOGY & EFFLUENT TREATMENT BRANCH I. DEFINITIONS 1.4 Channel Calibration 1.5 Channel Check 1.6 Channel Functional Test 1.16 Frequency Notation 1.17 Gaseous Radwaste Treatment (Off nas) Systen 1.25 Offsite Dose Calculational Manual 1.31 Process Control Pronram 1.32 Purge-Purging 1.39 Solidification 1.40 Source Check 1.44 Ventilation Exhaust Treatment S,vstem 1.45 Venting II. LIMITIN.G CONDITIONS FOR OPERATION AND SUR7EILLANCE REQUIREMENTS 3 f g 3,.3 nar m,a.m m, r n,., wa r 3/4 3.7.1 Monitoring Instrumentatton 3/4 3.7.11 Radioactive Liouid Effluent "onitoring Instrumentation 3/4 3.7.12 Radioactive Gaseous Effluent Monitoring Instrumentation 3/4 6.6.3 Standbv Gas Treatment System 3/4 7.2 Control Room Emeroency Filtration System 3/4 11 Radioactive Effluent III. BASES FOR LIMITING CONDITIONS OF OPERATION AND SURVEILLANCE.0,EOUIREMENTS Bases for all Limiting Conditions of Operations and Surveillance Requirements identified in Section II above, IV. DESIGN FEATURES 5.5 Meteorological Tower Location V. ADMINISTRATIVE CONTROLS 6.8 Procedures and Programs 6.4 Reportina Requirements 6.13 Process Control Pronram 6.14 Offsite Dose Calculational Manual A.15 Ma.ior Channes to Radioactive Haste Treatment Systens / ., f - ^

r:: Ei; CLOSURE 2 Technical Specifications, Bases and Definitions Reviewed by the Radiological Assessment Branch for Grand Gulf 1 1. Limiting Condition of Operation / Surveillance Requirements 3/4.3.7 Radiation Monitoring Instrumentation -3/4.7.5 Sealed Source Contamination ' 3/4.12 Radiological Environmental Monitoring 2. ADMIN 1ETRATIVE CONTROLS 6.2 Organization - 6.3 Unit Staff Qualification 6.4 Training 6.5 Review and Audit 6.5.3 Technical Review and Control 6.6 Reportable Occurrence Action 6.7 Safety Limit Violation 6.5 Procedures and Programs ] ' 6.9 Reporting Requirements 6.10 Record Retention 6.11 Radiation Protection Progra: 6.12 High Radiction Area u +4 9 g --wme-= =}}

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