ML20087N810

Forwards Final Rept, Grand Gulf Nuclear Station Unit 1 Audit of Nuclear Plant Tech Specs. Rept Determined Inconsistencies Exist Between Tech Specs,Fsar & SER

ML20087N810
Person / Time
Site:	Grand Gulf
Issue date:	03/27/1984
From:	Leach L EG&G, INC.
To:	Sims F ENERGY, DEPT. OF
References
CON-FIN-A-6816 NUDOCS 8404050012
Download: ML20087N810 (1)

Text

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P.O. BOX 1625. IDAHO FALLS, loAHO 83415 i

March 27, 1984 Mr. F. L. Sims, Director Reactor Research and Technology 0ivision

. Idaho Operations Office - DOE Idaho Falls, ID 83401 TRANSMITTAL 0F. GRAND GULF, UNIT 1, REPORT A6816 - LPL-106-84 Ref: J. M. Fehringer, H. C. Rockhold and T. L. Cook, Audit of Nuclear plant Technical Specifications Grand Gulf Nuclear Station, Unit i, Occket tio. 50-416, EGG-EA-6542, Maren 1984

Dear Mr. Sims:

Enclosed is the referenced final report. This report determined that there are inconsistencies between three Technical Specification Sections, the Final Safety Analysis Report, and the Safety Evaluation Report for Grand Gulf Nuclear Station, Unit 1. This report issued under FIN A6816 completes Node 106-D1 on the FY1984 NRC Support Milestone Chart.

Very truly yours,

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L. P. Leach, Manager Reactor Evaluation Programs JMF:jh

Enclosure:

As Stated cci J. H. Donohew, NRC/DL (5) /. b ' #

G. C. -Meyer, NRC/DL J. 0.-Zane, EG&G Idaho (w/o Enc.) pfpp l r

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EGG-EA-6542 March 1984 AUDIT OF NUCLEAR PLANT TECHNICAL SPECIFICATIONS GRAND GULF NUCLEAR STATION, UNIT 1 DOCKET NO. 50-416 J. M. Fehringer H. C. Rockhold T. L. Cook 9

- 0N Prepared for the U.S. NUCLEAR REGULATORY COMMISSION Under DOE: Contract No. DE-AC07-761001570

-FIN No. A6816

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. s DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their emoloyees, makes any warranty, expressed or implied, or assumes any legal 11acility or responsibility for any third party's use, of any information, apparatus, product or process disclosed in this recort or represents that its use by such third party would not infringe Drivately owned rights.

EGG-EA-6542 GRAND GULF NUCLEAR STATION UNIT 1 AUDIT OF NUCLEAR PLANT TECHNICAL SPECIFICATIONS Docket No. 50-416 TAC No. 54185 Published March 1984 J. M. Fehringer H. C. Rockhold T. L. Cook EG&G Idaho, Inc.

Idaho Falls, Idaho 83415 Responsible NRC Individual and Division:

G. C. Meyer/ Division of Licensing t

Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Under DOE Contract No. OE-AC07-76ID01570

. FIN No. A6816 MN

e ABSTRACT

' This report documents the ' review' of the Grand Gulf Nuclear Station

.. Unit 1, Technical Specifications (T/S) to determine if selected sections of the T/S are consistent with the Grand Gulf Final Safety Analysis Report

.(FSAR) as amended,' and the Grand Gulf Safety Evaluation Report (SER) as supplemented. Inconsistencies are listed in this report but no further evaluation was conducted to determine if the incensistency was an iredication of an error in any.cf the subject documents.

FOREWARD

.This report is supplied as part of the " Audit of Nuclear Plant Technical Specifications" being conducted for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Licensing, by EG&G Idaho, Inc., NRC Licensing Support Section, o The U.S. Nuclear Regulatory Commission funded the work under authorization B&R 20 19 10 11 1 FIN No. A6816.

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I' CONTENTS

1. INTRODUCTION ..................................................... I

2. . REVIEW CRITERIA .................................................. 1

3. DISCUSSION ....................................................... 3

4. CONCLUSIONS ...................................................... 7

5. REFERENCES ....................................................... 7 TABLE .

I .- Grand Gulf-1 Technical Specification /FSAR/SER Consistency Summary .............................................. 4 P

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AUDIT OF NUCLEAR PLANT TECHNICAL SPECIFICATIONS

1. INTRODUCTION The Grand Gulf Nuclear Station Unit 1, (Grand Gulf-1) is a boiling water reactor. (BWR) plant. It has been selected for an audit to determine if the Grand Gulf-1 Technical Specifications (TfS)1 are consistent with the Grand Gulf-1 Final Safety Analysis Report (FSAR)2 as amended and the Grand Gulf-1 Safety Evaluation Report (SER)3 as supplemented. The specific sections of the T/S selected for audit and summary results are listed in Table I. Inconsistencies between these sections of the T/S and the FSAR and SER were identified but no further evaluation was conducted to determine if the inconsistencies were indications of error in any of the subject documents.

2. REVIEW CRITERIA The T/S Limiting Conditions .for Operation (LCOs) ano Action Statements for each technical specification listed in Table I (Section 3) were compared to the FSAR and SER to determine if the T/S are consistent with the FSAR and SER. Emph' asis was on the T/S Operational Mode 1, power operation, with exceptions noted in this report. Setpoints and lists of valves, instruments, overcurrent protective devices and electrical buses in the T/S were. checked against tables in the FSAR and SER.

The SER was reviewed to ensure 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 E SER is included in this report.

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3. DISCUSSION The following . inconsistencies were identified:

-1. T/S Section 3/4.3.2 (Isolation Actuation Instrumentation)

. a. T/S, Amendment 9, Table 3.3.2-1 (Isolation Actuation Instrumentation), Item 5.m, includes "Drywell Pressure-High

" concurrent with" RCIC Steam Supply Pressure-Low", as a signal which causes Valve Group 4 and Valve Group 9 to close isolating Reactor Core Isolation Cooling (RCIC).

.However, Chapter 5.4.6, Reactor Core Isolation Cooling System, (pages 5.4-15 and 5.4-16) of the FSAR does not identify "Drywell Pressure-High" concurrent with "RCIC Steam Supply Pressure-Low" as an RCIC isolation signal.

b. Item 5.h of T/S Table 3.3.2-1 (Isolation Actuation Instrumentation) identifies a " Main Steam Line Tunnel Temperature Timer". The function of the timer is to delay RCIC isolation for 30 minutes (to allow the operator time to establish an alternate means of Reactor Vessel Level Control).

A timer is identified in the Figure 7.6-17 (Leak Detection System) of the FSAR as Instrument E-31R617. However, the FSAR does not identify the function of this tim;r. Without an FSAR discussion, the timer identified in Figure 7.6-17 cannoc be verified as the timer in Table 3.3.2-1 Item 5.h. of T/S.

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c. Item 2.b of T/S Table 3.3.2-2 (Isolation Actuation Instrumentation Setpoints) identifies the " Main Steam Line Flow-High" setpoint as 5 169 psid. A 169 psid signal corresponds to 140% steam flow.

The FSAR identifies 140% steam flow as the required " Main Steam Line Flow-High" setpoint.

However, Table 7.3-10 (Containment and Reactor Vessel Control System Instrumentation Specifications) of the FSAR identifies the setpoint as s 133.5 psid.

d. Item 2.b of T/S Table 3.3.2-2 (Isolation Actuation Instrumentation Setpoints) requires an instrument with an indicating range of

-50/0/250 psid in order to indicate the s169 psid trip setpoint.

However, Table 7.3-10 (Containment and Reactor Vessel Control System Instrumentation Specifications) of the FSAR identifies an instrument with sn indicating range of -15/0/150 psid.

2. T/S Section 3/4.6.4 (Containment and Drywell Isolation Valves)

Sections 3.6.4-1.1'.b through 3.6.4-1.4.b of T/S Table 3.6.4-1 (Containment and Drywell Isolation Valves)a lists valves that are not

. identified as required in the FSAR Table 6.2-44 (Containment Isolation Valves).

3. T/S Section 3/4.6.6.2 (Secondary Containment Automatic Isolation Dampers / Valves)

The completeness of T/S Table 3.6.6.2-1, (Secondary Containment Isolation Dampers / Valves) cannot be verified by FSAR Table 7.6-12,

a. Some of the valves are listed 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 Penctration and Containment Isolation Valve Leakage Rate Test List).

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(Auxiliary Building Isolation System Actuated Equipment List), because the specific Isolation Dampers are.not listed in FSAR Table 7.6-12.

The Isolation Valves are' listed.

Table I contains a summary of the Grand Gulf Unit 2 T/S sections reviewed;-consistencies and inconsistencies with the FSAR and/or the -

SER are 'shown. -

TABLE I. GRAND GULF-1 TECHNICAL SPECIFICATION /FSAR/SER CONSISTENCY

SUMMARY

~SECTION CONSISTENT / INCONSISTENT 3/4.3 ! INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION ~ Inconsistent

.3/4.3.3 EMERGENCY CORE'C00 LING SYSTEM Consistent

~ ACTUATION INSTRUMENTATION 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ECCS - OPERATING Consistent 3/4.5.3 SUPPRESSION. CHAMBER Consistent 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY' CONTAINMENT Consistent Primary Containment Integrity Consistent JPrimary Containment Leakage Consistent Primary Containment Air Locks Consistent

'. .MSIV Leakage Control System Consistent i Feedwater Leakage Control System Consistent Primary Containment Structural Consistent Integrity Primary Containment Internal- Consistent Pressure t

Primary Containment Purge System Consistent 4

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SECTION ~. CONSISTENT / INCONSISTENT 3/4.6.2 DRYWELL

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Orywell Integrity _

Consistent -

Drywell Bypass LLkage Consistent Drywell Air Locks ', Consistent '

Orydell Structural Integrity ,

Consistent Orywell Internal Pressure , Consistent 3/4.6.3 DEPRESSURIZATION SYSTEMS ,

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. Suppression Chamber .

Consistent

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Primary Containment Spray Consistent 4

Suppression Pool Cooling- Consistent .-

Drywell-Suppression Chamber Consistent Differential Pressure -

3/4.6.4- ' CONTAINMENT AND ORYWELL ISOLATION Inconsistent VALVES ,

3/4.6.5 SECONDARY CONTAINMENT

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Secondary Containment Automatic Inconsistent ,

Isolation Dampers / Valves Standby Gas Trettment System Consistent 3/4.6.7 ATMOSPHERE CONTROL

~ Containment and Drywell Hydrogen Consistent ~

Recombiner Systems ~

Drywell Purge System Consistent 3/4.8 ELECTRICAL p0WER SYSTEMS

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3/4.8.1 A.C. SOURCES -

Consistent

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A.C. Sa'urces-Operating Consistent

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TA8LE I. (Cantinued)

SECTION CONSISTENT / INCONSISTENT 3/4.8.2 0NSITE POWER DISTRIBUTION SYSTEMS 3/4.8.3 A.C. Distribution - Operating Consistent 0.C. Distribution - Operating Consistent 3/4.8.4 Primary Containment Penetration Consistent Conductor Overcurrent Protective Devices

4. CONCLUSION lAsshowninTab1'eI,32technicalspecificationsectionswerecompared with.information in the FSAR and SER for Grand Gulf, Unit 1.

Inconsistencies were identified in three sections of the technical specifications shown in Table I. This review did not determine the significance of the inconsistency or which of the documents was in error.

5. REFERENCES ,

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1. Grand Gulf Technical Specifications Rev. June 1982

2. Grand Gulf FSAR up to Amendment No. 57

3. Grand Gulf SER up to Amendment No. 4

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