ML20238C625
| ML20238C625 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/03/1987 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8709100258 | |
| Download: ML20238C625 (13) | |
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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374o1 SN 157B Lookout Place SEP 031987 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of
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Docket Nos. 50-327
. Tennessee Valley Authority
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50-328 SEQUOYAH NUCLEAR PLANT (SQN) - UNITS 1 AND 2 - REVISION TO INSERVICE PRESSURE TEST PROGRAM In response to an April 14, 1980 letter from Charles E. Murphy to H. G. Parris, TVA submitted its Inservice Pressure Test Program for SQN units 1 and 2 by an August 18, 1983 letter from L. M. Mills to J. P. O'Reilly.
This program was first revised by a March 10, 1986 letter from R. Gridley to Dr. J. Nelscn Grace. Enclosed is an additional revision to the Inservice Pressure Test Program for SQN units 1 and 2.
(See enclosure with asterisks indicating where changes were made.) This program applies to the first 10-year interval and is based on the 1977 Edition, Summer 1978 Addenda, of
.Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.
This revision reflects changes in TVA's corporate organization in which the Inservice Inspection (ISI) Programs Section was moved under the Division of Nuclear Engineering (DNE). Other changes resulted from a technical review of the program's implementing instructions.
These changes include:
(1) the deletion of the ethylene glycol system from the hydrostatic test schedule (see section 8.0), and (2) a clarification of the intent in the wording of the program instructions concerning termination of a test when leakage is found (see section 6.0).
This revision to SQN's Inservice Pressure Test Program is being submitted to you for your review. No new rellaf requests have been added by this submittal.
If you have any questions, please telephone D. V. Goodin at (615) 870-7462.
Very truly yours, TENNESSEE VALLEY AUTHORITY b.
AR. Gridley, Director Nuclear Safety and Licensing Enclosure cc: See page 2 d
870910025e 870903 Ni PDR ADOCK 05000327 p
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An Equal Opportunity Ernployer
1 U.S. Nuclear Regulatory Commission 0 3 1887 I
cc (Enclosure):
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Mr. G. G. Zech, Assistant Director for Inspection Programs Of fice of Special Projects
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U.S, Nucicar Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. J. A. Zwolinski, Assistant Director for Projects Division of TVA Projects Office of Special Projects U.S. Nuclear Regulatory Commission 4350 East-West Highway EWW 322 Bethesda, Maryland 20814 Sequoyah Resident Inspector Sequoyah Nucicar Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 1
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ENCLOSURE INSERVICE SYSTEM PRESSURE TEST PROGRAM FOR FIRST 10-YEAR INTERVAL i
I SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 1
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1 Inservice Pressure Test Program Cover Sheet i
Owner:
Tennessee Valley Authority Address of Corporate Office: Office of Nuclear Power
-1 1101 Market Street Chattanooga, Tennessee 37402-2801 Name and Address of Nuclear Power Plant:
Sequoyah Nuclear Plant 1
P.O. Box 2000 Soddy Daisy, Tennessee 37379 l
l Applicable Nuclear Power Units:
Sequoyah Nuclear Plant, Units 1 and 2 Commercial Operation Date: Unit 1 July 1, 1981 Unit 2
' July 1, 1982
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E TLE OF CONTENTS l
1.0 STATEMENT OF APPLICABILITY j
l 2.0 PURPOSE l
3.0 INSPECTION INTERVALS AND INSPECTION PERIODS l
4.0 CODES OF RECORD l
5.0 METIIOD OF IMPLEMENTATION AND RESPONSIBILITIES l
6.0 DOCUMENTATION OF SYSTEM PRESSURE TEST RESULTS 7.0 REQUESTS FOR RELIEF I
8.0 TENTATIVE SCHEDULE I
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1.0 STATEMENT OF APPLICABILITY i
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This program outlines requirements for performing the first 10-year interval system pressure tests of Sequoyah Nuclear Plant units 1 and 2, American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components containing water, steam, or radioactive material (other than radioactive waste management systems). This program has been organized to fulfill inservice pressure test requirements of Nuclear Quality Assurance Manual, Part II, Section 5.1, and Program Procedure 1402.02 and to comply as practical with the requirements of Section XI of the ASME Boiler and Pressure Vessel Code.
The requirements of this program are applicable starting at the date of commercial operation of the unit.
4 Specifics concerning performance of system pressure tests are not a part of this program but are included in plant surveillance instructions.
2.0 PURPOSE W
The 7nservice Pressure Test (IPT) Program shall be used for planning inspections and pressure testing Sequoyah ASME Class 1, 2, and 3 j
components for the first intceval.
3.0 INSPECTION INTERVALS AND INSPECTION PERIODS The inservice pressure tests required by ASME Section XI shall be performed during each 10-year interval of service (inspection interval).
3 The inspection intervals represent calendar years after the unit has been
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placed into commercial service.
The commercial operation date for unit 1 is July 1, 1981, and the date for unit 2 is June 1, 1982. The first 10-year interval may be decreased or extended by as much as one year.
If the unit is out of service continuously for six months or more, the inspection interval may be extended for an equivalent period.
The inspection interval shall be separated into three inspection periods--calendar years of plant service, at three, seven, and ten years.
J 4.0 CODES OF RECORD This program was prepared to meet the requirements of the 1977 Edition, Summer 1978 Addenda, of Section XI of the ASME Boiler and Pressure Vessel Code.
In accordance with 10 CFR 50.55a(g)(4)(IV), identification of test pressurization boundaries shall be in accordance with subarticle IWA-5220 of the 1980 Edition, Winter 1981 Addenda, of ASME Section XI.
In accordance with the ASME Section XI 1980 Edition, Winter 1981 Addenda, paragraph IWA-5224(a), the boundary subject to test pressurization during i
a system hydrostatic test IWA-5211(D) shall be defined by system boundary (or each portion of the boundary) within which the components have the same minimum required classification and are designed'to the same primary pressure rating as governed by the system function and the internal fluid
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operating conditions respectively.
Therefore, when design pressure and temperature within the test boundary differ and isolation valves and
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relief valves are not present, the hydrostatic test pressure shall be j
I determined by the component within the test boundary with the lowest design pressure.
During system leakage tests, IWA-5211(a), on Class I components, the pressure retaining boundary shall be defined as shown in footnote 1 for examination category B-P in Table IWA-2500-1 of the 1980 Edition, Winter 1981 Addenda, of ASME Section XI.
5.0 METHOD OF IMPLEMENTATION AND RESPONSIBILITIES l
The IPT Program preparation is the responsibility of the Divivion of Nuclear Engineering (DNE), Inservice Inspection (ISI) Program 8 Section.
Any requests for relief or revisions initiated by other groups shall be submitted to the ISI Programs Section for approval before incorporation into this program.
The ISI Programs Section shall submit the IPT Program to NRC for approval via the Director Division of Nuclear Safety and Licensing, Office of Nuclear Power.
The plant has the responsibility for preparation of the general plant f
instruction that implements the IPT Program. This instruction includes j
j requirements for system pressure tests and references all implementing
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instructions by instruction number.
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l Plant management shall notify the Authorized Inspection Agency (AIA) i (Authorized Nuclear Inservice Inspector [ANII) if he is onsite) reasonably in advance of when system pressure tests are scheduled to be
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performed.
Normally, the ANII will witness component hydrostatic 1
pressure tests.
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The plant manager shall assign personnel to perform system pressure tests I
and visual examination (VT-2) during the tests. The Plant Quality l
Assurance Staff shall be responsible for certifying that individuals l
l performing VT-2 visual examinations are qualified in accordance with l
l Program Procedure 0202.14.
1 6.0 DOCUMENTATION OF SYSTEM PRESSURE TEST RESULTS 6.1 Upon completion of system pressure tests, personnel responsibAr for the tests shall prepare a data sheet form.
As a minimum, each data sheet shall include:
6.1.1 Temperature. pressure, and duration of pressure before: visual examination is performed.
6.1.2 The number and location of any leaks found.
6.1.3 The action taken (if any).
6.1.4 Signature of individual who performed the test and data when the test was performed.
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6.1.5 Cognizant etigineer review signature and date.
6.1,6 Statement indicating that pressure gauges were verified to be properly calibrated.
6.1.7 Identification of test boundaries.
6.1.8 Identification number of measuring and test equipment.
Each data sheet will be made available to the ANII for review and acceptance. The ANII will sirp snd date the data sheet to document his acceptance.
Leakage detected, which is determined to be unacceptable and I
prevents completion of the test, shall require termination of the test and corrective action initiated.
Following corrective action and before service, the system or component shall be retested.
Where components 1. ave been repaired, replaced, or undergone maintenance-type corrective action and are isolable within a portion j
of the system, only that portion needs to be retested. Repair and replacement activities shall be performed in accordance with program procedure 1402.02.
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7.0 REQUESTS FOR RELIEF
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System:
Aux!11ary Feedwater'
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5 TVA IN awing: 4h'803-2 3g
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y' les) Requirement Syst'emhydrostpticpressuret.estfinAccordancewith subarticle find-S210a of ASMP,' Section,KI,1977 Edition, t
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Summej 1978 Addenda-Component:
Auxiliary feedwater piping between the following valves'.
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1-LCV-3-172,1-3-871)
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2-LCV-3-172, 2-3-871
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1-LCV-3-173, 1-3-872
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2-LCV-3-173, 2-3-872 s
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1-LCV-3-174, 1-3-873) a i C t
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2-LCV-3-174, h3-873 #
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1-LCV-3-175 /1-3-874 j,.
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2-LCV-3-175, 2-3-874 9.
1-LCV-3-14il,,1-LCV-1CdA., 1-3-830 10.
2-LCV-3-148, 2-U/Y-14BA, 2-3-830
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1-LCV-3-150, 1-1CVL156A, 1-3-631 12.
2-LCV-3-156; 2-LCV-156A, 2-3-831 13.
1-LCV-3-164,'7-LCV-164A, 1-3-83.2
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2-LCV-3-164, 2-LCV-16'4A, 2-3-832
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1-LCV-3-171, 1-LCV-171A., 1-3-833 16.
2-LCV-3-171( 2-LCV-171Af 2-3-833 Class:
TVA Safety class C
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Basis for Relief:
The auctie-9 nted piping sections cannot be hydrostatically '
system-pret mre testei.tithout overpressurizing downstream components because of design pressure changes and inability to isolate the safety
' class C (PDES = 1,650 psi) piping i' rom the safety class B (PDES = 1,085 psi) piping pressure boundary c
Alternate Inspection:. #erform hydrostatic system pressure test in aAcordance
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'Jwith the TVA safety class B pressure boundary (1.25 x
- ,., i lowest rcilef valve setting, Psv, Pov = 1,050 psig).
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