ML20206A462
| ML20206A462 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/26/1988 |
| From: | Atkinson P NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20206A455 | List: |
| References | |
| 3-88-135, PROC-881026, NUDOCS 8811150131 | |
| Download: ML20206A462 (36) | |
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TURBINE OVERSPEED PROTECTION h!AINTENANCE AND TESTING PROGRAh! - REVISION 0 l
S!!LLSTONE UNIT 3 NCCLEAR POWER STATION I
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r TURBINE OVERSPEED PROTECTION MAINTENANCE AND TESTING PROGRAM - REVISION 0-l MILLSTONE UNIT 3 NUCLEAR POWER 3TATION i
t ABSTRACT This document describes the basis for the Turbine Maintenancefand Testing l
Program for Millstone Unit 3.
This program ad. dresses the requirement of the l
Millstone Unit 3 Safety Evaluation Report Section 3.5.1.3.
The Turbine l
Maintenance and Testing Program modifies Technical Specification 3/4.3.4 "Turbine Overspeed Protection".
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Included are descriptions identifying all items subject to examination and testing, the type of examination or test, the periodicity of the examinations and tests, and the source (s) of the requirement (s).
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TABLE OF CONTENTS Cover Sheet / Approvals Abstract Table of Contents 1.
INTRODUCTION 1.1 General 1.2 References 1.3 Revisions and Changes 2.
DESCRIPTION OF INSPECTION PROGRAM 2.1 Main Valves 2.1.1 Main 2. trol Valves 2.1.2 Main. cop Valves l
2.1.3 Combined Intercept Valves i
2.2 Low Pressure Turbines 2.2.1 Rotors 2.3 High Pressure Turbine 2.3.1 Rotor 6 Year Inspection 2.3.2 Rotor 12 Year Inspection 2.4 Other Turbine / Generator Components 3.
INSPECTION EVALUATION CRITERIA 3.1 General 3.2 Main Valves 3.3 Low Pressure Turbines 3.4 High Pressure Turbine 4
INSPECTION
SUMMARY
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DESCRIPTIuN OF PERIODIC TESTING AND CALIBRATION PROGRAM 5.1 overspeed Protection System Control System Calibration and Testing 5.1.1 Weekly Tests 3.1.2 Refueling Outage Tests 5.1.5 Refueling Outage Calibrations l-11
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5.2 Overspeed Protection Systso Valve Testing 5.2.1 k'eekly Tests 5.2.2 Monthly Tests 5.2.3 Refueling Outage Tests 6.
RECORDS AND DATA MANAGEMENT 7.
FICL'RES AND ATTACHMENTS 7.1 Figures 7.1.1 Turbine Inspection Schedule 7.1.2 Main Valve Inspection Schedule 7.2 Attachments 7.2.1 Sumeary Tables of Missile Generation Probabilities Low Pressure Turbine 3 MSS-TIA 7.2.2 Summary Tables of Missile Generation Probabilities Lov Pressure Turbine 3 MSS-TIB 7.2.2 Summary Tables of Missile Generation Probabilities Low Pressure Turbine 3 MSS-TIC 111
1.
INTRODUCTION 1.1 General This document describes the basis for the Turbine Maintenance and Testing Program for Millstone Unit 3.
This program encompasses periodic tests and inspections to preclude generation of turbine missiles as a result of material defects or turbine overspeed.
Inspection and testing intervals are based on Millstone Unit 3 Final Safety Analysis Report (FSAR) (Ref. 1.2.1), the Hillstone Unit 3 Safety Evaluation Report (SER) (Ref. 1.2.3), the etnufacturer's recommendations containod in references 1.2.2, 1.7.5, 1.2.8 and 1.2.9 and on the manufacturer's ptibability summary tables contained in attachment 7.2.1.
Inspection schedules based on Section 2. Description of Inspection Program are contained in Figures 6.1.1, 6.1.2 and 6.1.3.
These figures will be updated periodically based on inspection results, but will continue to meet the criteria of Section 2.
A summary report of inspections perforrod in accordance with this program vill be written following each refueling outage and will be available for review.
1.2 References 1.2.1 Millstone Nuclear Power Station Unit 3 Final Safety Analysis Report, Section 3.5.1.3, "Turbine Missiles", 10.2.2.1, "Turbine-Generator Equipment" and 10.2.3.6 (Turbine)
"Inservice Insoection" and Question "Q430.139 (Section 10.2)".
1.2.2 Ceneral Electric Technical Information Letter 1008-3, "Inservice Inspection of 1500 and 1800 RPM Turbine Rotors,"
as transmitted to C. H. Clement Millstone Unit 3 Superintendent, frou J. J. Sullivan, General Electric Service Manager, September 8,1987.
1.2.3 Safety Evaluation Report rotated to the operation of Millstone Nuclear Power Station Unit No. 3, Docket No.
50-423 Northeast Nuclear Energy Company, July 1984. Section
- 3. 5.1. 3.
1.2.4 "Missile Generation Probabilities" as transmitted to P. C. Atkinson, Millstone Unit 3 Engineer, from S. J.
Spinarola, General Electric Service Supervisor, May 6,1988.
1.2.$
Ceneral Electric CEX-379378 "Valve Stude Tightining, Inspection & Replacerent Recorrendations" May 1982.
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1.2.6 Northeast Nuclear Energy Company Administrative Control Procedure ACP-QA-5.01, "Nonconforming Materials and Parts".
1.2.7 NUSCo Reliability Engineering Nondestruc-ive Examination Nuclear Turbine Procedure Manual.
1.2.8 General Electric GEK-46527B, "Periodic Operrtional Test Sucmary". February,1901 1.?,9 General Electric TIL 969, "Periodic Turbine Steam Valve Test
- Nuclear 1; nits", May 22, 1984.
1.3 Revisions and Changes l
Revisions to this program vill be performed in accordance with Technical Specification 4.3.4.2. which :*equires a 10CFR50.59 Safety Evaluation for each revisi,n or change.
2.
DESCRIPTION OF INSPECTION PROGRAM The folleving is a detailed description of the Inspection Program for each cc ponent to be examined.
2.1 Main Valves The main valve inspection intervals are based on meeting the require-ments of the M111stene Unit 3 SER (Ref. 1.2.3) and TSAR (Ref. 1.2.1) and on recommendations contained in Genatal Electric GEK-379373 (Ref.
1.2.5).
2.1.1 Main Control Valves l
Each of the Main Control valves 3 MSS-MCV1, MCV3, MCV2 and l
MCV4 vill be inspected at approximately 6 year intervals, j
corresponding to ence every 4th refueling outage.
Inspections will consist of visual and surf ace inspections of valve seats, discs and stems. Valve stand to body studs vill be ultrasonically tested. Valve bushings vill be T
inspected and cleaned and bore diameters will be checked for
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proper clearance.
2.1.2 Main Stop Valves Each of the Main Stop Valves. 3M55-M571, MSV2, MSV3 and MSV4 i
vill be inspe,ted at approuimately 6 year intervals, corresponding to once every 4th refueling outage.
Inspectione vill consist of visual and surf ace inspections i
of valve seats, discs and stems. Upper head to body studs 1
vill be ultrasonically tested. Yalve bushings will be inspected and cleaned and bore diameters vill be checked for l
proper clearance.
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2.1.3 Combined Intercept Valves Each of the Coebined Intercept Valves, 3 MSS-C1V1, C1V2, C1V3, C1V4, CIV5 and C1V6 vill be inspected at approximately 6 year intnrvals, corresponding to once every 4th refueling outage.
Inspections will consist of visual and surface inspections of valve seats, discs anu stems. L'pper head to body studs will be ultrasonically tested. Valve bushings will be inspected and cleaned and bore diameters will be checked for proper clearance.
2.2 Low Pressure Turbines The Low Pressure Turbine, 3 MSS-T2A, T2B and T2C inspection intervals are based on the manvfe:turers calculations of missile generat!sn probabilities (Attachment 7.2), the Millstone 3 SER (Ref. 1.2.3) and FSAR (Ref. 1.2.1) and recommenditions contained in General E*.ectric TIL 1008-3 (Ref. 1.2.2).
2.2.1 Rotors Each Low Pressure Turbine Rotor will bo inspected at approx-imately 6 year intervals, corresponding to every fourth refueling outage. The results of the inspection vill be used to calculate the next rotor inspection interval based on missile generation probabilities.
In no case vill the i
inspection interval exceed every fourth refueling outage.
The inspection will consist of the following:
A.
An ultrasonic inspection of the bore and teyway region of each shrunk on wheel and of the tangential entry bucket setachments and pins of the finger bucket attach =ents and of the last stage bucket attachment devnstream finger in the area of the upper pin hole.
B.
A visual and magnetic particle inspection of all accessible surfaces of wheels, thaft, buckets, covers, packings, joutnals, couplings and bull gear.
C.
A visual and ultrasonic inspection of idjacent coupling bolts.
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- f 2,3 High Pressure Turbine The High Pressure Turbine, 3 MSS-T1,1,upection intervals are based on the Millstone 3 SER (Ref. 1.2.3) and FSAR (Ref. 1.2.1) and recommends-tions in General Electric TIL 1008-3 (Ref. 1.2.2).
2.3.1 Rotor 6 Tear Inspection The High Pressure Turbine rotor will be inspected at approx-imately 6 year intervals, correspording to every 4th refueling outage.
The inspection will consist of the following:
A.
A visual and matt. etic particle inspection of all accessible surfaces of rotor body, shaf t, buckets, covers, ic kings, journals and couplings.
B.
A visual and ultrasonic inspection of adjacent coupling bolts.
2.3.2 Rotor 12 Year Inspection The High Pressure Turbine rotor will be inspectsd at approximately 12 year intervals, corresponding to every 8th refueling outage, starti,g with the 5th refueling outage.
The inspection will consist of the following:
A.
The inspections described in 2.4.1, "Rotor 6 Tear Inspection".
B.
An ultrasonic inspection of the rotor from the periphery and the bore.
C.
AL ultrasonic inspe; 'on of the tangential entry dovetails.
2.4 Other Turbas./ Generator Components 2.4.1 Other Turbine / Generator component inspections recommended by the manufacturer are incorporated into the Production Maintenance Msnagement System (PMMS) and Millstone 3 maintenance procedures, as applicable. These inspections are not governed by this maintenanca and testing program.
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3.
INSPECTION EVALUATION CRITERIA 3.1 General l
i Evaluation criteria for nondestructive examinations performed by Northeast Utilities Reliability Engineering personnel or contractors under the direction of Reliability Engineering personnel are delineated by the NUSCo Reliability Engineering Nondestructive Examination Nuclear Turbine Procedure Manual (Ref. 1.2.7).
Unacceptable examination results will be documented by Unresolved Indication Reports (UIRs) as delineated in the manual. The UIPs will be dispositioned by the Unit 3 Turbine Maintenance Engineer in conjunction with the manufacturer and NUSCo Engineering, as required.
Ultrasonic Inspections will be performed in accordance with the original manufacturer's standards.
Indications will be evaluated and recoczendations will be decemented in an inspection report.
3.2 Main Valves t
In addition to the criteria referenced in 3.1. "General" (Evaluation Criteria), the following criteria vill applyt j
l A.
If unacceptable flaws or improper clearances or excessive corrosion are found in a valve, all valves of that type vill be inspected.
5.
Unaccepta' ole flavs. ieproper clearances or excessive corrosion i
are defined as follows:
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Any flaw, improper clearance ;r corrosion which if uncorrected.
vould cause an incorrect valve operation that could result in a turbine overspeed o"er the next plant operating cycle.
C.
The determination of the acceptability of the Unresolved l
i Indication Report or incorrect clearance vill be documented by a Non-conformar.ce Report (NCR) in accordance with Northeast Nuclear i
I Energy Company Administrative Control Procedure ACP-QA-5.01 Non-conforming Materials and Parts (Ref. 1.2.6).
3.3 Low Pressure Turbines In addition to the criteria referenced in 3.1 "General" (Evaluation i
Criteria) the following criteria will applyt l
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Ultrasonic inspection results will be used to calculate the next inspection interval and recommend rotor repair /re.olacement based on missile generation probabilities. This infon
'on will be documented in an inspection report and will be used to update j
Tigure 7.1.1.
B.
Couplings and coupling bolen with unacceptable indications will be repaired or replaced.
i 3.4 High Pressure Turbine j
In addition to the criteria referenced in 3.1 "General" (Evaluation i
Criteria) the following criteria vill apply:
i A.
Ultrasonic inspection results will be used to recommend the next inspection interval and recommend rotor repair / replacement.
This information will be documented in an inspection report and will i
be used to update Figure 7.1.1.
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Couplings and coupling bolts with unacceptable indications will l
be repaired or replaced.
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INSPECTION
SUMMARY
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A sumary of the inspections performed in accordance with this program will 4
be written following the maintenance outage and will be available on file for review.
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5.
DESCRIPTION OF PERIODIC TESTING AND CAI.IBRATION PROGRAM 3
1 The following is a detailed description of the Periodic Testing and f
Calibration Program for the Overspeed Protection Control System and the Main Valves.
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5.1 Overspeed Protection System Control System Calibration and Testing I
The Overspeed Protection System Control System testing and calibration intervals are based on meeting the requirements of the Millstone Unit
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3 SER (Ref. 1.2.3), TSAR (Ref. 1.2.1), and on recommendations contained in General Electric CEK-46527B, "Periodic Operational Test Sunnary" (Ref. 1.2.8).
l 5.1.1 Weekly Tests i
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The following tests will be performed on a weekly bu is A.
A backup overspeed test at the EHC panel to test the l
two out of three logic circuits.
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B.
A mechanical overspeed trip test at the EHC panel to test for operation of the overspeed trip device and mechanical trip valve.
C.
A mechssical trip piston test (oil trip) at the EHC panel to test for electrical activation of the trip eechanism.
D.
An electrical trip test at the ERC panel to test for operation of the electrical trip valve.
5.1.2 Refueling Outage Tests l
The following tests vill be performed at approximately l
1.5 year intervals, corresponding to every refueling l
outage.
A.
An actual backup overspeed trip test vill be perforned, t
B.
An actual overspeed trip test vill be performed three consecutive times.
5.1.3 Refueling Outage Calibrations l
The following calibration vill be performed at approximately 1.5 year intervals, corresponding to every refueling outage.
l A.
A calibration of the backup cverspeed trip logic j
circuits corresponding to loop test diagrams 3TMB-172A,B&C.
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5.2 Overspeed Protection System Valve Testing f
The Overspeed Protection System valve testing intervals are based on meeting the requirements of the Millstone Unit 3 SER (Ref.
1.2.3) and the FSAR (Ref. 1.2.1) and on recommendations contained in General Electric TIL 969, "Periodic Turbine Steam Valve Test -
Nuclear Units" (Ref. 1.2.9) and General Electric CEK-46527B, "Periodic Operational Test Summa ;y" (Ref.1.2.8).
i 5.2.1 k'eekly Testing 5.2.1.1 The extraction steam nonreturn valves.
3ESS-NRV22A,B.C; NRV30A B.C;.'V39A,B.C; NRV48A B.C and NRV66A,B.C. vill be tested weekly for freedom of movement using the l
positive assist devices. !
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5.2.1.2 The following valves will be cycled through a complete cycle from running position on a weekly basist A.
The main stop valves. 3 MSS-MSV1, MSV2, MSV3 and MSV4 B.
The combined intercept valves, 3 MSS-C1V1, CIV2, CIV3, CIV4, CIV5 and
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C1V6.
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5.2.2 Monthly Testing l
The following testa vill te completed on a monthly l
basist l
A.
The main control valves. 3 MSS-McV1, MCV2, McV3 and MCY4 will be cycled through a complete cycle from running position. This will be verified by direct observation of valve movements through the complete cycle.
B.
Each of the valves listed in 5.2.1.2 will be i
cycled through a complete cycle from running l
position and this will be verified by direct l'
observation of valve movement through the complete cycle.
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l 5.2.3 Refueling Outage Testing The following tests will be completed approximately once every 1.5 years, corresponding to every refueling outage.
A.
A tightness test of the main stop valves, 3 MSS-MSV1, MSV2, MSV3 and MSV4.
B.
A tightness test of the main control valves.
3 MSS-MCV1, MCV2, McV3 and MCV4 6.
F.ECORDS AND DATA MANAGEMENT 6.1 Copies of inspection summaries and inspection reports from refueling outage inspections may be stored in Unic 3 Maintenance Department files. Original reports will be transmitted to Northeast Utilities Nuclear Records. Work Orders and non-conformance reports associated with inspections and periodic test data forms will be stored in Nuclear Records in accordance with existing Administrative Control Procedures.
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FIGURES AND ATTACHMENT 7.1 Figures 7.1.1 Turbine Inspection Schedule 7.1.2 Main Valve Inspection Schedule 7.2 Attachments 7.2.2 Summary Tables of Missile Generation Probabilities Low Pressure Turbine 3 MSS-TIA.
7.2.2 Suenary Tables of Missile Generation Probabilities Low Pressure Turbine 3 MSS-TIB.
7.2.3 Summary Tables of Missile Generation Probabilities Irv Pressure Turbine 3 MSS-TIC.
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I-IGUHi! 7.1.1 1 URIllNE INSPEG IONS YE ARS*
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CIVh CIV3 CIVh CIV3 27 p 2M $
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