ML20087K834

Audit of Nuclear Plant Tech Specs

ML20087K834
Person / Time
Site:	Grand Gulf
Issue date:	03/31/1984
From:	Cook T, Fehringer J, Rockhold H EG&G, INC.
To:	Donohew J, Meyer G Office of Nuclear Reactor Regulation
References
CON-FIN-A-6816 EGG-EA-6542, TAC-54185, NUDOCS 8403260335
Download: ML20087K834 (18)

Text

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l EGG-EA-65C GRAND GULF NUCLEAP POWER Pt. ANT I AUDIT OF WUCLEAR PLANT TEC'clNICAt. SPECIFICATIONS I Docket No. 50-416 1 1AC No. 54185 l l

l_ Published March 1984

. J. H. Fehringer H. C. Rockhold T. L. Coot l

EC&G (daho, Inc.

Idaho falls, Idaho 83415 Responsible NRC Ir.dividual and Otvision:

[ J. H. Donohew/C. C. Heyer/Ofvision of Licensing

, Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555 under 00F Contract No. OE-AC07-761D01570 FIN No. A6816 l.

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I OfSCLAIMER

! TNs boot was pepwed at an arrnet of %crk stensored by an a0ency of the Untted l States Goveerwrect. Nattwo ifw IJnsiod States Govenment noe any agency thereof, not any of een employees, makes ecy wettenty, expcess or impised, ca assuma any legat hetsty or t . . Mi os l the ecomacy, completenses, et utstuiness of any WormeWon, apparatut, pemiuct or process dedosed, or tapresents that #fs use would not inhay povetesy ew.ed nghts, fteteronous heaev.i to any specsfic comrriercsei poduct, osocese, or senece try trede name, eradsunart. manufmuser, or othenwne, does not necocoonly contatute et imply ese endevoernee.t. recommend 4 hon, et favonng by yw Unned Staas Cowrunens et any agency twoof. The vwwe and cowwons of l

austsors expetsed fwain do not necessen4 state or reflect those of the Uruted States oowmment or any egencytheemos.

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ABSTRACT This report reviews the Grand Gulf Nuclear Power Plant Technical Specifications (T/S) to determine if selected. sections of the T/5 are l

consistant with the Grand Gulf Final Safety Analysis Report (FSAR) as i amended, and the Grand Gulf Safety Evaluation Report (SER) as supplemented. Inconsistencies, L f any, are listed in thi's report but no further evaluation was conducted to determine if the inconsistency was a:,

indication of..an error in any of the subject documents.

FORWARD This report is supplied as part of the " Audit of Nuclear Plant Itchnical Specifications" being condected for the U.S. Nuclear Regulatory Comnission, Office of Nuclear Reactor Regulation, Olvision of Licensing, :3y EG&G Idaho, Inc., NRC Licensing Support Section.

The U.S. Nuclear Regulatory Coanission funded the work under authorization %R 20 19 10 11 1 FIN No. A6816.

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CONTENTS ~ l l

1. INTRODUCTION ..............................................,, ,,, j i

2. AEVIEW CRITERIA ............ .. .................................. 2

3. DISCUSSION ....................................................... 5

4. CONCI.USIONS .............................................,,,,,,,,, 14 , ,

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5. REFERFNCES ..... ........................ ........................ 15 i

TABLES I. Plant Speci fic Technica l Specificat.fon Topics . . . . . . . . . . . . . . . . . . . . 3 i II. Plant Specific Technical Specification Consistency Sunwnary .. . . . . . 10 i

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g n AUDIT OF NUCLEAR PLANT TECHNICAL SPECIFICATIONS

1. INTRODUCTION The Grand Gulf Huclear Power Plant is a boiling water reactor (BWR) plant. It has been selected for an audit to determine if the Grand Gulf Technical Specifications (T/S) (Ref.1), are consistent with the Grand C if Final Safety Analysis Report (FSAR) as amended (Ref. 2). and the Grand G !i Safety Evaluation Report (SER) as supplemented (Ref. 3). The specific sections of the T/S selected for audit are itsted to Table 1.

Inconsistencties between these sections of the T/S and the FSAR and SER w;:1 be identified but no further evaluation was conducted to determine if the inconsistency was an indication of error in any of the subject documents, t

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2. REVIEW CRITERIA The T/S Limiting Conditions for Operation (LCOs) and Action Statements for each technical specification listed in Table 1 were compared to the FSAR and SER to determine if the T/S are consistent to the FSAR and SER.

Emphasis was on the T/S Operational Mode 1, power operation, with any exceptions to this noted in this report. Setpoints ar.d Itsts of valves, instruments, over current protective devices and electrical buses in the T/S were checked against lab?es in the FSAR and SER.

The SER was reviewed to determine that requirements in the SER were addressed in the T/S.

The T/S Bases and Surveillance requirements were not reviewed in this audit of the T/S.

An explanation of each inconsistency between the T/S and the FSAR and SER is included in this report.

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TABLE I. PLANT SPECIFIC lECHNICAf. SPECIFICATIDH AUDIT TOPICS SEC_11,0N If43 INSTRUMENTATION 3/4.3.2 ISOLA 7!ON ACTUATION INSTRUMENTATION l

3/4.3.3 EMERGENCY CORE C00LlHG SYSTEM ACTUATION INSTRUMENTATION 3/4.5. EMERGENCY CORE _C00LlHG SYSTEMS 3/4.5.1 ECCS - OPERA 11NG l 3/4.5.3 SUPPRES$10H CHAMBER 3/4.5 CONTAINMENT SYSTEMS l 3/4.6.1 PRIMARY CONTAINMENT Primary Containment integrity r

Primary Containment Leakage

. Primary Containment Air Locks Feedwater leakage Control System MSIV leakage Control System Primary Containment Structural Integrity Primary Containment Internal Pressure l

Primary Containment Purge System 3/4.6.2 DRYWEL,L Drywell integrity Drywell Bypass Leakage Drywell Air Locks Drywell Structural Integrity Drywell internal Pressure Orywell Average Air Temperature 3

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TABLE !. (Continued)

SECTION 3/4.6.3 OEPRESSURIZATION SYSTEMS  !

Suppression Chamber Primary Containment Spray '

suppression Pool Cooling Orywell-Suppression Chamber Olf ferential Pressure 3/4.6.4 CONTAINHENT AND ORYWELL ISOLA 110N VALVES 3/4.6.6 SECONDARY CONTAINMENT Secondary Containment Automatic Isolat.fon Dampers Standby Gas Treatment System 3/4.6.7 ATHOSPHERE CONTROL

. Containment,and Orywell Hydrogen Recombiner Systems Containment and Drywell Hydrogen Ignition System Drywell Purge System 3/4.8 ELECTRICAL POWER SYSTFMS 3/4.8.1 A.C. SOURCES A.C. Sources-Operating 3/4.8.2 ONSITE POWER O!STRIBUTION SYSTEMS 0.C. Distribut.fon - Operating Of stribution - Operating Primary cont.ainment. Penetration Conductor Overcurrent Protective Devices I

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3. DISCUSSION The overall results of the audit are given in Table II. The table gives each section of the T/S and the overall determination of consistency or inconsistency between the T/S and the FSAR and SER.

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i The concluston that a specific section of the T/S are not consistent with the FSAR and/cr the SER are documented in tabular form on the ,

following pages. Each of the following tables includes the T/S Limiting conditions for Operation or Action Statement, the related section in the FSAR and SER and an explanation of the inconsistency seen between the T/S

. and the FSAR and/or SER.

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- l A. Topic: 3/4/3 Instrumentation ,

T/S: 3/4/3/2 tsolation Actuation Instrumentation j Table 3.3.2-1 Item 5.m I I

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1. Explanation of Inconsistency a.

Table 3.3.2-1, item 5.m of 1/5 Ammendment 9 identifies Drywell Pressure-High concurrent with RCIC Steam Supply Pressure-Low, as a RCIC isolation signal which causes Valve Group 4 and Valve The FSAR does not address the Group 9 to close isolating RCIC. l Orywell Pressure-High isolation signal, or the required  !

Concutrence logic.

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l 8. Topic: 3/4.3 Instrumentation l I/S: 3/4.3.2 Isolation Actuation Instrumentation l 1. Explanation of Inconsistency

a. Table 3.3.2-1 Item 5.h of T/S refers to "Hain Steam Line Tunnel Temperature Timer" The timer is identified in the FSAR Figure 7.6-17 as l Instrument E-31R617. However, the FSAR does not address the function of this timer which is to delay RCIC isolation for ,

30 minutes (to allow the operator time to establish an alternate I

means of Reactor Vessel Level Control). Without an FSAR discussion, the timer identified in Figure 7.6-17 cannot be j yerified as the timer addressed in T/S Table 3.3.2-1 Item 5.h.

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b. Table 3.3.2-2 Item 2.d of T/S identifies the Main Steam Line l Flow-High setpoint as s 169 psid with an instrument rar}ge of

-5G/0/250. A 169 psid signal corresponds to 140% steam flow which is consistent with FSAR assumptions.

l However, the FSAR Table 7.3-10 identifies the setpoint as 5133.6 psid with an instrument range of -15/0/50 psid which Is inconsistent with the previous assumptions.

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C. Topic: 3/4I6ContainmentSystems l

T/S: 3.6.4 Containment and Drywell Isolation valves

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1. Explanation of inconsistency l

a. The following sections of the T/s Table 3.6.4-1 If sting of Containment and Drywell Isolation Valves identif tes valves that l cannot be found in the FSAR listings under Containment isolation Valves (Table 6.2-44) specifically.

t 3.6.4-1.2.b 3.6.4-1.2.b 3.6.4-1.3.b 3.6.4-1.4.b Several of the valves are IIsted in FSAR Tables; 7.6-12, Auxiliary Building Isolation System Actuated Equipment List; 6.2-48 Primary Containment integrated leakage Rate instrumentation, and Table 6.2-49 Reactor containment Penetratton l and Containment Isolation Valve leakage Rate Test List.

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- 0. Tople: 3/4.6 Containment Systems

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T/S: 3.6.6.5 Secondary Containment Automatic Isolation  !

Dampers / Valves i

1. Explanation of Inconsistency i

a. The adequacy of T/S Table 3.6.6.2-1 Secondary containment Isolation Dampers / Valves cannot be vertfled consistent with the FSAR Table 7.6-12, Auxiliary Butiding Isolation System Actuated Equipment List, because the spectfic Isolation Dampers are not ,

listed in Table 7.6-17. The Isolation Valves are listed.

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TABLE II. PLANT SPECIFIC TECHNICAL SPECIFICA110N CONSISTENCY

SUMMARY

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SECTION CONSISTENT INCONSISTENT 3/4.3 INSTRUMEljTAT10N 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION Inconsistent 3/4.3.3 ENERGENCY CORE COOLING SYSTEH Inconsistent j

ACTUATION INSTRUMENTATION F4 52 EMERG,ENCY CORE COOLING SYSTEMS l 3/4.5.1 ECCS - OPERATING Consistent

! 3/4.5.3 SUPPRESSION CHAMBER Consistent i  !

234.6 CONTAINMENT SYSTEMS

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3/4.6.1 PRIMARY CONTAINMEN1 Consistent Primary containment Integrity consistent Primary Containment Leakage Consistent Primary Containment Air Locks Consistent MSIV Leakage Control System Consistent Feedwater Leakage Control System Consistent Primary Containment Structural Consistent Integrity Primary Containment Internal Consistent Pressure Primary Containment Purge System Consistent.

l 3/46.2 ORYWELL Drywell Integrity Consistent Orywell Byass leakage Consistent Drywell Air Locks Conststent Drywell Structural Integrity Consistent Orywell Internal Pressure Consistent 10

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.SECTION CONSIST,E,NT/I,NCONSISTEH,T 3/4.6.3 DEPRESSURl2A110N SYSTEMS Suppression Chamber consistent Primary Containment Spray Consistent Suppression Poo1 Cooling Consistent

Orywe11-Suppression Chambee Consistent Of fferential Pressure 3/4.6.4 CONTAlHMENT AND ORYWELL ISOLATION Inconsistent VALVES 3/4.6.5 SECONDARY CONTAINMENT Secondary Containment Automatic Inconsistent Isolation Dampers / Valves Standby Gas Treatment System Consistent 3/4.6.7 A1MOSPNERE CONTROL Containment and Drywell Hydrogen Consistent Recombiner Systems

! Drywell Purge System Consistent 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Consistent i A.C. Sources-Operating Consistent 3/4.8.2/ ONSITE POWER OISTRIBUTION SYSTEMS 3/4.8.3 A.C. Olstributton - Operating Consistent 0.C. Distributton - Operating Consistent j 3/4.8.4 Primary Containment Penetration Consistent

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4. CONCLUSION l l

There are 4 technical specifications of the 32 reviewed in this audit '

of the Grand Gulf Technical Specifications (Ref.1) that were determined I inconsistent with the Grand Gulf FSAR as amended (Ref. 2) and the Crand Gulf SER as supplemented (Ref. 3). Inconsistencies were Identified but nu further evaluation was conducted to determine if the inconsistency was an Indication of an error in any of the subject documents. l 1

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5. REFERENCES i

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1. Grand Gulf Technical Specifications Rev. June 1982 f 1

2. Grand Gulf FSAA vp to Ammendment No. 57

3. Grand Gulf SER up to Ammendment No. 4 j i

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Docket No. 50-416 -

GRAND SULF AMINDMENT NO. I to '" ERATING LICENSE NO. NPF-13 DISTRIBUTIqll:

Ecument Co7 trol (50-416)

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