ML20195H044

Forwards Addl Rev to Inservice Pressure Test Program for First 10-yr Interval.Rev Deletes Implementation Methods for Program Due to Duplication in QA Manuals

ML20195H044
Person / Time
Site:	Sequoyah
Issue date:	01/11/1988
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8801150004
Download: ML20195H044 (12)

Text

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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 5N 1578 Lookout Place JAN 111988 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 - REVISION TO IN-SERVICE PRESSURE TEST (ISPT) PROGRAM TVA submitted its ISPT Program for SQN units 1 and 2 by an August 18, 1983 letter from L. M. Mills to J. P. O'Reilly. This program has undergone two revisions in letters to NRC dated March 10, 1986, and September 3, 1987. Enclosed is an additional revision to the ISPT Program for SQN units 1 and 2. (See enclosure with vertical lines indicating where changes are 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) Boller and Pressure Vessel Code. The revision, contained in enclosure 1, deletes information that details the methods by which TVA implements the ISPT Program. This information is duplicate information, which is contained in TVA's Quality Assurance program manuals and implementing instructions.

The specific changes are as follows: (1) item 2.0 is revised to more correctly reflect the purpose of the ISPT Program; (2) item 4.0 is revised to more clearly identify the program areas that are in compliance <

with Code editions and addenda that are subsequent to the primary Code of Record; (3) items 6 and 7 have been deleted for the reasons stated above; and (4) the only request for relief to ISPT-1 has been revised to a more '

simplified format. This revision to SQN's ISPT Program is being submitted for your information. No new relief requests have been added by this submittal.

If you have any questions, please telephone D. V. Goodin at (615) 870-7460.

Very truly yours, ,

TENNESSEE VALLEY AUTHORITY

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$21500o4 88o111 R. Gridley, Direct gk\

P ADOCK 05000327 Nuclear Licensing and \

DCD Regulatory Affairs Enclosures cc: See page 2 An Equal Opportunity Employer I

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U.S. Nuclear Regulatory Commission 1B 1

cc (Enclosures):

Mr. K. P. Barr, Acting Assistant Director for Inspection Programs TVA Projects Olvision Office of Special Projects U.S. Nuclear Regulatory Commission

- Region.II 101 Harletta Street, NN, Suite 2900 Atlanta, Georgia 30323 Mr. G. G. Zech, Assistant Director for Projects TVA Projects Division Office of Special Projects U.S. Nuclear Regulatory Commission One White Fline, North 11555 Rockville Pike Rockville, Maryland 20852 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379

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,f TABLE OF CONTENTS 1.0 STATEMENT OF APPLICABILITY 2.0 PURPOSE 3.0 INSPECTION INTERVALS AND INSPECTION PERIODS 4.0 CODES OF RECORD 5.0 REQUESTS FOR RELIEF 6.0 TENTATIVE SCHEDULE t

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In-Service Pressure Test Program Cover Sheet Owner: Tennessee Valley Authority Address of Corporate Office Office of Nuclear Power 1101 Market Street Chattanooga, Tennessee 37402-2801 Name and Address of Nuclear Power Plant Sequoyah Nuclear Plant P. O. Box 2000 Soddy Daisy, Tennessee 37379 Applicable Nuclear Power Units: Sequoyah Nuclear Plant, Units 1 and 2 Commercial Operation Date Unit 1 July 1, 1981 Unit 2 June 1, 1982 d

1.0 STATEMENT OF APPLICABILITY This program outlines requirements for performing the first 10-year interval system pressure tests of Sequoyah Nuclear Plant (SQN) units 1 and 2 American Society of Mechanical Engineers (ASME) Code Class 1, 2, 3 components containing water, steam, or radioactive material (other than radioactive waste management systems). This program has been organized 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.

Specifies concerning performance of system pressure tests are not a part of this program but are included in plant surveillance instructions.

2.0 PURPOSE This In-Service Pressure Test (ISPT) Program is designed to meet the requirements of Title 10 of the Code of Federal Regulations, Part 50, paragraph 50.55a (g)(4), for the in-service pressure testing of ASME Code Class 1, 2, and 3 pressure retaining components.

3.0 INSPECTION INTERVALS AND INSPECTION PERIODS The in-service pressure tests required by ASME Section XI shall be performea during each 10-year interval of service (inspection interval).

The inspection intervals represent calendar years after the unit has been placed into commcreial 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 t.hree inspection periods, calendar years of plant service, at three, seven, and ten years.

4.0 CODES OF RECORD 4.1 This program was prepared primarily to meet the requirements of the 1977 Edition, Summer 1978 Addenda, of Section XI of the ASME Boiler and Pressure Vessel Code.

4.2 In accordance with 10 CFR 50.55a(g)(4)(iv), the following areas shall meet the requirements of the 1980 Edition, 1981 Addenda of Section XI of the ASME Code in lieu of the base code of record:

(1) System Hydrostatic Test Boundary (IWA-5224)

(2) Maximum Allowable Hydrostatic Test Pressurc (IWA-5265 (b))

(3) Hydrostatic Test Pressure for Class 1 (equivalent) Systems (IWB-5222 (a) & (b))

(4) System Leakage Test Boundary (IWA-5221 and footnote 1 for Examination Category B-P in Table IWB-2500-1)

(5) Nornal Reactor Operation (footnote 4 in IWB-1000)

(6) System Hydrostatic Test Pressure for Class 2 and 3 (equivalent) Components (IWC-5222 (a))

(7) Open-ended Systems and Components (footnote 1 in IWC-5000)

4.2.1 Identification of hydrostatic test pressurization boundaries shall be in accordance with paragraph IWA-5224 of the 1980 Edition, Winter 1981 Addenda. The boundary subject to test pressurization during a system hydrostatic test, IWA-5211(d), shall be defined by the 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 operating conditions, respectively. When the design pressure and tempercture within the test boundary differ and isclation valves and relief valves are not present, the hydrostatic test pressure shall be determined by the component within the test boundary with the lowest design pressure.

4.2.2 For the purpose of providing a maximum allowable hydrostatic test pressure, the requirements of IWA-5265 (b) of the 1980 Edition Winter 1981 Addenda, shall be met. Thus, the imposed pressure, including static head, on any component within the pressure boundary will not exceed 106 percent of the specified test pressure for the system.

I 4.2.3 During syatem hydrostatic tests on Class 1 (equivalent) l systems, the specified test pressure shall be determined in l accordance with paragraphs IWB-5222 (a) and (b) of the 1980 Edition, Winter 1981 Addenda.

4.2.4 The pressure retaining boundary for system leakage tests f shall be defined by paragraph IWA-5221 of the 1980 Edition, Winter 1981 Addenda. Also, during system leakage tests on Class 1 components, the pressure retaining boundary shall be defined as shown in IWA-5221 and as modified by footnote 1 for examination category B-P in Table IWB-2500-1 of the 1980 Edition. Winter 1981 Addenda, of ASME Section XI. Thus, during Class 1 leakage tests the test boundary shall correspond to the reactor coolant system boundary with all valves in the normal position, which is required for normal reactor operation startup.

4.2.5 The footnote 4 in IWB-1000 of the 1980 Edition, Winter 1981 Addenda, is used for the purpose of defining normal reactor operations for its use in ascertaining the Class 2 (equivalent) systems or components subjected to functional pressure testing.

4.2.6 The provision in paragraph IWC-5222(a) of the 1980 Edition, Winter 1981 Addenda, is used in conjunction with Class 2 and 3 (equivalent) systems to allow the substitution of design pressure P d, in place of the lowest relief valve set pressure, Psy, in the case where the pressure test boundary does not include any relief valves.

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. 3-4.2.7. For the purpose of cefining "open-ended" systems and ccaponents for Seneral use in the pressure test program, the footnote 1 reiarenced in IWC-5222(d) of article IWC-5000 of the 1980 Edition, 1981 Winter Addenda, is cited.

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5.0 REQUESTS FOR RELIEF

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REQUEST FOR RELTEF ISPT-1 Components: Auxiliary feedwater piping between the following valves:

(Reference TVA Drawing 47W803-2)

1) 1-LCV-3-172, 1-3-871

2) 1-LCV-3-173, 1-3-872

3) 1-LCV-3-174, 1-3-873

4) 1-LCV-3-175, 1-3-874

5) 1-LCV-3-148, 1-LCV-3-148A, 1-3-830

6) 1-LCV-3-156, 1-LCV-3-156A, 1-3-831

7) 1-LCV-3-164, 1-LCV-3-164A 1-3-832

8) 1-LCV-3-171, 1-LCV-3-171A, 1-3-833

9) 2-LCV-3-172, 2-3-871

10) 2-LCV-3-173, 2-3-872 ,

11) 2-LCV-3-174, 2-3-873

12) 2-LCV-3-175, 2-3-874

13) 2-LCV-3-148, 2-LCV-3-148A 2-3-83n

14) 2-LCV-3-156, 2-LCV-3-156A 2-3-831

15) 2-LCV-3-164, 2-LCV-3-164A, 2-3-832

16) 2-LCV-3-171, 2-LCV-3-171A, 2-3-833 Class: ASME Code Class 3 (Equivalent).

TVA Safety Class C Function: Provide flow path to steam generators for auxiliary feedwater Inspection Requirement: ASME Section XI, subarticle IWD-5210a, requires that all pressure retaining components specified in the examination categories of Table IWD-2500-1 be subjected to a hydrostatic pressure test at a pressure equal to 1.10 times the system pressure, Psv, for systems with design temperature of 2000F or less, and at least 1.25 times P sv for systems with design temperature above 2000F. Pys is the lowest pressure setting among the number of safety or relief valves provided for

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Inspection Requirement (Cont.): overpressure protecticn within the boundary of the system to be tested. In the absence of safety or relief valves within the boundary, the design pressure, Pd , will be used in place of the P sv-Basis for Relief: The subject piping sections are Class 3 (equivalent) piping that have a design pressure rating of 1,650 psig. and that are connected to Class 2 (equivalent) piping that have a design pressure rating of 1,085 psig.

The Class 2 piping is separated from the Class 3 piping by check valves that allow flow only from the Class 3 to the Class 2 piping. Because of this configuration, it is not possible to pressurize the Class 3 piping i'

in these sections without over-pressurizing the Class 2 piping.

Alternate Testing: The subject piping sections will be tested at the hydrostatic test pressure used for the Class 2 (equivalent) piping.

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