Text

Deficiency Rept Re Main Steam Safety Valve Ring Setting. Procedure 1021, Test Procedure for Wyle High Flow Steam Sys Safety/Relief Valves Recertification/Acceptance/Evaluation Testing & Test Rept 47447-0 Encl
	ML20137P496
Person / Time
Site:	Seabrook
Issue date:	02/27/1985
From:	Devincentis J; PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	Gregg H; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20136F709	List: ML20136F707; ML20137P496;
References
	RTR-NUREG-0933, RTR-NUREG-933 1049, SBN-772, NUDOCS 9704090262
	Download: ML20137P496 (2)
	v • d • e

{{#Wiki_filter:_ 0 tL T W 7 h* #'# IEABROOK STATION l l A i 4 C_./ %~Ggi$P ff p V February 27, 1985 O d* SBN-772 T.F. H1.1.28/G1.1.11 Now Hompshire Yonkee Division i United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention: Mr. Harold Gregg References (a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNH Letter SBN-751, dated January 17, 1985, " Interim 10CFR50.55(e) Report, Main Steam Safety Valve Ring Setting Deficiency", J. DeVincentis to R. W. Starostecki

Subject:

Additional Documentation; SeIbrook Main Steam Safety Valve Ring) [ Setting Deficiency ~ f

Dear Sir:

f Per your request, we have enclosed the following documentation regarding the subject 10CFR50.55(e) item (Reference (b)]: A. Test Procedure for Wyle High Flow Steam System Safety / Relief Valves Recertification/ Acceptance / Evaluation Testing, Procedure No.1021, September 17, 1981 B. Test Report for Full Flow Testing of 16, 18, and 20-Inch Main Steam Safety Valve Vent Stacks for Yankee Atomic Electric Company, Report No. 47447-0 s Note that the last three x-y plots, dated December 1, 1984, of the Test Report, graphically depict the Crosby valve ring setting deficiency. We have previously discussed these results in telephone conferences. If further discussion or data is required, please contact us. Very truly yours, /d.~c J. DeVincentis, Director Engineering and Licensing Enclosures f ( l cc Atomic Safety and Licensing Board Service List t 9704090262 050205 PDR NUREC 0933 C PDR l P.O. Box 300 a 5@ccA.NH03874. Telephone (603)474-9521

= William S. J:rdan, III Diane Curran . Marihon, Elss r Jorden Brentwood Board of falectmen 20001 S Street N.W. I RED Dalton Road Suite 430 Brentwood, New Hampshire 03833 Washington, D.C. 20009 Robert G. Perlis i Office of the Executive Legal Director Edward F. Meany U.S. Nuclear Regulatory Commission Designated Representativt of Washington, DC 20555 the Town of Rye i 155 Washington Road l Robert A. Backus, Esquire Rye, NH 03870 116 Lowell Street F.C. Box 516 Calvin A. Canney Mancoheter, NH 03105 City Manager City Hall i Philip Ahrens, Esquirr 126 Daniel Street Assistant Attorney General Portsmouth, NH 03801 Department of the Attorney General Augusta, ME 04333 Dana bisbee, Esquire Assistant Attorney General Mr. John B. Tanzer Office of the Attorney General Designated Representative of 208 State House Annex the Town of Hampton Concord, NH 03301 4 5 Morningside Drive l Bampton, NH 03842 Anne Verge, Chairperson Board of Selectmen j Roberta C. Fevear Town Hall l Designated Representative of South Hampton, NH 03642 the Town of Hampton Falls Drinkwater Road Patrick J. McKeon 1 Nampton Falls, NH 03844 Selectmen's office 10 Central Road Mrs. $sedra Cavutis Rye, NH 03670 Designated Representative of the Town of Kensington Carole T. Kagan, Esq. RTD 1 Atomic Safety and Licensing Board Panel East Kingston, NH 03827 U.S. Nuclear Regulatory Commission Jo Ann Shotwell, Esquire Assistant Attorney General Mr. Angie chiros Environmental Protection Sureau Chairman of the Board of Selectmen Department of the Attorney General Town of Newbury One Ashburton Place 19th Floor Newbury, MA 01950 Boston, MA 02108 Town Manager's Office Senator Gordon J. Humphrey Town Hall - Friend Street U.S. Senate Amesbury, Ma. 01913 Washington, DC 20510 (Atta Tom Burack) Senator Gordon J. Humphrey 1 Pillsbury Street Diana P. Randall Concord, NH 03301 70 Collins Street (Attn: Herb Boynton) SEsbrook, NH 03874 l Richard E. Sullivan, M4yor Donald E. Chick City Hall Town Manager Newburyport, MA 01950 p Town of Exeter ( 10 Pront Street Exeter NH 03833 l

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APPROVED BY FOR: PROJECT MANAGER: 6 T. os b-' / 9VED BY: APPPOVED BY FOR: QU ALITY ENGINEER-MI PREPARED BY APPROVED BY: ' FOR: O -w -* Nb ~ o' PROJECT ENGINEER: ~ (/ J. R. 'Na'ph c REVISIONS ,0,,, os..,,..,,, l REV. bO. DATE PAGES AFFECTED BY A P P' L. DESCRIPTION OF CH ANGES I I I I I r I-I COPVEIGHT BY wvLE LABORAT083E5. THE RIGHT TO REPRODUCE. COPY, ExHlali. OR OTHERW!5E UTILIZE ANY OF THE MAT' RIAL CorJTAINED HEREIN E WITHOL'T THE EXPRESS PRICR PEF'.*l5$10N OF WYLE LABORATORIE515 PROM 161TED. THE ACCEPTANCE OF A PURCHASE ORDER IN C0tJNECTION WITH THE CATER;AL C0bf AINED mERf!!. SHALL EE EQUlVALENT TO EAPRESS FRIOR PERMISSION.

. ~.. ' l* oACE NO iI TEST Pr.00EDJ8.E No. - 1021 TABLE OF CONTENTS Page No. 1 1.0 PURPOSE 1

2.0 REFERENCES

I 30 TEST EQUIPMENT AND INSTRUMENTATION 2 4.0 PERSONNEL CERTIFICATION 2 50 STORAGE 2 6.0 REQUIREMENTS AND PROCEDURES APPENDlX i - HIGH FLOW STEAM LOOP DESCRIPTION 5 b\\v) ( b /'N WYLE LABORATORIES 50Ru 1054 7 ne, oct is Huntsveile Facehty

nGE NO I TEST PROCEDLC.E NO. 1021 .0 PURPOSE The purpose of this test procedure is to present the methods and procedures used in testing safety and safety relief valves on the Wyle full flow steam test system. It is very generalized in nature and can be modified to satisfy each customer's requirements.

2.0 REFERENCES

2.1 ASME Boiler and Pressure Vessel Code, as applicable. 2.2 American National Standard N45.2, " Quality Assurance Program Requirements for Nuclear Power Plants." 2.3 American National Standard ANSI /ASME PTC 25.3-1976, " Safety and Relief Valves." 2.4 Nuclear Regulatory Commission Regulation 10 CFR 50, Appendix B. 2.5 Nuclear Regulatory Commission Regulation IO CFR 21. 2.6 Customer's Purchase Order and Special Instructions. .0 TEST EQUIPMENT AND INSTRUMENTATION Q).1 Calibration of Test Equipment and System Calibration All test equipment and instrumentation used in the performance of this test program shall be calibrated in accordance with Wyle Laboratories' Quality Assurance Policies and Procedures Manual, which conforms to the applicable portions of ANSI-N45.2, 10 CFR 50/ Appendix B, and Military Specification HIL-C-45662A. Standards used in performing all calibrations are traceable to the National Bureau of Standards. All test equipment is calibrated on a periodic basis and the calibration c. Interval is displayed on a decal. This decal is affixed to the equipment indicating the last calibration date, the next calibration due date, accuracy, and by whom calibrated. In addition to individual component calibration, prior to and immediately following test, an end-to-end system calibration is performed on equipment used to establish valve set pressure. 3.2 Heasurements and Tolerances l Unless specified otherwise, the maximum allowable tolerance on test condi-t tion measurements shall be as follows: I Pa rame te r A. Tempe ratu re . +/- 4'F r[O l B. Pressure: Heise Gauge +/- 0.1% F.S. t Deadweight Tester +/- 0.05% Pressure Transducer +/- 1.0 psi e WYLE LABORATORIES '0"8 ' 854 7 A" k' i' Huntsv.Ue Facihty

PAGE NO. 2 TEST PAOCEDURE NO. 1021 .0 PERSONNEL CERTIFICATION Wyle certifies that all personnel assigned to the steam valve facility are qualified for the tasks assigned. Personnel qualification is achieved by personnel education levels, vocational training, and practical experiences as outlined in ANSI-N45.2. 5.0 STORAGE During any. prolonged non-testing period, the test specimens shall be stored in a controlled storage area. The storage area shall be maintained in accordance with good laboratory practices, i.e., being properly protected from grease, oil, solvents, and any surface dirt that could influence the results of the test program. The storage area will be in compliance with ANSI-N45.2.2, Level C. 6.0 REQUIREMENTS AND PROCEDURES '6.1

System Description

6.l.1 The Wyle high flow system is described in more detail in Appendix 1, but consists basically of two accumulators with a volume of approximately 950 cubic feet and is capable of storing a mass of steam at 1400-1550 psig. This steam is released through a servo-(9 controlled valve system into a secondary accumulator of approxi-( / mately 450 cubic feet of volume upon which the test article, a safety relief valve, has been thermally conditioned to simulate in plant conditions. 6.1.2 The pressure rise in the secondary accumulator can be controlled from a low of approx!mately 15 psi /sec to over 200 psi /sec to simulate a reactor system experiencing an overpressure condition. 6.1.3 A normal test sequence is to install the test article, usually a safety relief valve, on the mounting flange of the secondary accumulator. Saturated steam shall be slowly admitted to the secondary ac,- mulator until a pressure of 1000 +/- 10 psig of set pressure is attained. This pressure shall be maintained until thermal stabilization is achieved. Thermal stabilization is defined as no more than 4*F change in 15 minutes on any of the thermocouples attached to the valve. 6.1.4 in some Instances, an environmental chamber shall be installed around the test article to provide an ambient temperature of 135* +/- 5'F, or as otherwise specified by the customer, to best simulate In-service conditions. 6.1.5 Steam tracing of the valve spring and insulation blankets may be [] used if elevated temperature is desired. + WYLE L.ABORATORIES Huntsnile Facil81Y

r DAGE NO. 3 =. TEST PFOCEDUAL No. 1021 6.0 REQUIREMENTS AND PROCEDURES (CONTINUED) i 6.2 Instrumentation The valve lift shall be monitored with a linear voltage differential 6.2.1 transforcer (LVDT). The valve lift shall be recorded simultaneously with the valve inlet pressure on a X-Y recorder. The inlet steam temperature, ambient temperature, body surface 6.2.2 temperature and upper and lower bonnet surface temperatures shall be monitored using thermocouples. The temperatures shall be recorded on a digital recorder at one (1) minute intervals. The valve inlet pressure shall be monitored with a pressure transducer 6.2.3 The valve inlet pressure, as monitored and a Helse pressure gage. by the pressure transducer, shall be recorded simultaneously with the valve lift on the X-Y recorder. (Prior to each set pressure pop, the pressure transducer reading shall be adjusted as necessary to agree with the pressure gage reading.) The pressure transducer and the pressure gage shall be calibrated against a deadweight tester prior to and subsequent to test. f ~s 6.2.4 The thermocouples on the valve shall be attached by banding or spot welding as directed by the customer. (x i 6.3 Leak Testing 6.3.1 Mirror Leak Test HIrror leak testing shall be conducted at the beginning and completion of testing or as otherwise 'di rected by the customer. The leakage test shall be performed as follows. 6.3.1.1 A cold (< 100*F) mirror about 2 inches square and 1/8 inch thick shall be passed around the disc to seat interface and the mirror inspected. If no moisture or a faint fogging is detected, it may be concluded that essentially zero steam leakage is present. If the mirror surface shows condensa-tion droplets, the leakage is unacceptable and the valve must be repaired per Reference 2.6. If in doubt about whether the condensation is leakage or faint fogging, holding the mirror at the suspect area for a longer period of time will produce increased condensation droplets if steam leakage exists. The mirror shall not be allowed to heat up. o !k i WYLE LABORATORIES Huntsvine Facdity l

Pt.GE NO 4 TEST PCtOCEDuBE NO 1021 .0 REQUIREMENTS AND PROCEDURES (CONTINUED) 6.3 Leak Testing (continued) 6.3 2 Quantitative Leak Testing 6.32.1 if so desired, quant!tative leak testing may be conducted, but normally only when the normal west-facing tailpipe is connected. The coined blankoff plate in the Daniel Senior Orifice will be installed to isolate approximately 10 feet of tallripe downstream of the test valve and a condenser will be used to condense steam leakage.

6. 3. 2. 2 1.eakage shall be collected in a graduated cylinder for three 5-minute periods and recorded.

Acceptance / rejection criteria will be as dictated by individual customers. 6.4 Set Pressure Verification 6.4.1 Set pressure verification shall normally be under full flow conditions using the servo V-1 and V-2 controls. Blowdown will also be determined under these conditions, but may or may not be considered as acceptance / rejection criteria. Ramps shall be from 2 to 250 pst and may be varied to determine ramp sensitivity. A minimum of 10 g t j minutes shall elapse between runs. To exercise the valve and obtain V data in a rapid fashion, V-1 only runs may be performed (essentially full lif t, short duration). 6.4.2 If the measured set pressure is not within +/- 1% of 5.he nameplate set pressure, or as otherwise directed by the customer, the valve shall be adjusted and actuated again. 6.4.3 The 4 valid test runs shall be within +/- 1% of the nameplate set pressure, or as otherwise directed by the customer, and shall not exhibit a trend in either the increasing or decreasing direction. A trend is defined as a variation of more than 1.5% of nameplate set pressure from first valid run to last valid run and the inter-f vening valid test runs are each successively higher than the pre-ceding runs or lower than the preceding runs. For valve certifi-cation, ramp rates shall be controlled within the range specified by the customer. i 6.5 Blowdewn it has been found that for some valves blowdown is a function of system backpressure. If desired, different sized orifices may be installed in the discharge pipe to superimpose various backpressures. These back-pressures and acceptance limits must be provided by individual customers m / h and may be added to this procedure as an approved appendix.

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.? - HIGH FLOW STEA'(LOOF DESCRIPTIO 1. i ~ Introduckioni The Wyle'High Flow Steam Facility has the capabilities for valve operability l All test equip-l qualification per NRC Regulatory Guide l.48 or. ANSI 278-2.4. ment and instrumentation used in conducting the test programs comply with the .l requirements' cf the Wyle Laboratories Ouality Control !!anual which conforms to MIL-C-45662A and the applicable portions of ANSI fl45.2 and 10CFR50, Appendix E. l i [ System

Description:

The Wyle High. Flow Steam Facility-(Figure 1) was designed to detemine the [ operating ~ characteristics of GE-BWR-NPP Safety Relief Valves under full flow l and full lift conditions. Steam for the High Flow System is provided by two Holman boilers thatLcan be l operated independently or in parallel. The boilers,are usually fired by. natural' gas, but in times of natural gas shortages are operated on a propane n. . Each boiler can provide saturated steam at a fMw rate of i' standby system. . Accumulation fer High Flow 15,000.lb/hr at a maximum pressure of 1700 psig. is provided by two 454 cubic accumulators (denoted as A1) which a re connected i- ) i: to a third accumulator-(A2) of 450 cubic feet. These accumulators are shown in' Figure 1 along.with the associated valving. Principal valves in the system with their associated function are as follows: i r Size Desionation Function -3" V1 Servo actuated control valve between Al and A2 and in parallel with V2. .l t 10" V2 Main line servo actuated control valve between Al and A2. i Servo actuated drain valve on bottom of A2. 2" V3 3" V4 Servo actuated bleed valve on A2. 10" V5 Air motor controller isolation valve []I between Al and A2. 1" V6 Manual valve. The servo controlled valves V1 and V2 control the inlet pressure ramp to the test valve-and can be adjusted to deliver inlet ramos from 2 to 200 psi /sec. Typical system operation, after appropriate calibrations and temoerature sta-s ( bilizations, is to hold A2 at a pressure (approximately 1000 psig) which is dependent upon the type and set' pressure of the relief valve under test and with V1 is then actuated to a partially Al at a-higher pressure (1350-1500 psig). ]- At a open position to give the desired rate-of pressure increase in A2. predetemined pressure, less than the relief valve set pressure, V2 is prograrr.ed. sL'O ~ h ]3

., 5: a partially c;en position to inc* ease the steam fici and rate of pressure j ' increase. At a predeteminec time, Y2 is ocer.ed an additicnal arount, usually to'100%,' to provice full flow to the test valve. During this time the inlet steam pressure has reached the specimen " set" pressure.and opened; As 1.he ] system pressure decays, the relief valve closes at its resent pressure. < j During the full flow portion of the valve cycle, discharge pipe restrictors develop the appropriate backpressure. Also,. during this time the inlet pressure is decaying at a relatively constant rate decending upon the test i valve size, flow rate and test objective. b k i ? l i 4 ) I ) J 2 i i e s 4 i 4 i i l l

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.9 t, L,.. ni 1 r-b -'lL i f' TEST REPORT [' FOR I FULL FLOW TESTING OF 16, 18, AND 20-INCH '(' ) MAIN STEAM SAFETY VALVE VENT STACKS FOR ) y' 7 YAKEE ATOMIC ELECTRIC COWANY !{- ~ 5.) \\ ' r'

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2.0 REFERENCES

1 3.0 TEST EQUIPMENT AND INSTRUMENTATION 1 s 4.0' PERSONNEL CERTIFICATION 2 '{ ( 5.0 TEST SPECIMEN DESCRIPTION 2 [* 6.0 TESTS-2 6.1 16-Inch Vent Stack 2 6.2 18-Inch Vent Stack 3 6.3 20-Inch Vent Stack 3 l-6.4 20-Inch Vent Stack with 90* Elbow 3 { 7.0 - DATA 3 '8.0 DISPOSITION 3 1 j-FIGURES t 1. I I. INSTMKF TATION LOCATIONS (16,18 AND 20-INCH VENT STACKS) 4 2. INSTRUMENTATION LOCATIONS (90* ELBOW /20-INCH VENT STACK) 5 t

I TABLES L.

I TEST DATA SHEET, YANKEE ATOMIC J/N 47447, OCTOBER 17, 1984, VALVE TAG NUMBER 1-MS-V25,16-INCH VENT STACK 6 T~ II TEST DATA SHEET, YANKEE ATOMIC J/N 47447, OCTOBER 19, 1984, 4 r VALVE TAG NUMBER 1-MS-V25, 18-INCH VENT STACK 7 ii III TEST DATA SHEET, YANKEE ATOMIC J/N 47447, NOVEMBER 28, 1984, 4 VALVE TAG NUMBER 1-MS-V25, 20-INCH VENT STACK 8 i r lU IV TEST DATA SHEET, YANKEE ATOMIC J/N 47447, NOVEMBER 30, 1984, VALVE TAG NUMBER 1-MS-V25, 20-INCH VENT STACK (90* ELBOW) 9

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. TEST DATA SHEET, YANKEE ATOMIC J/N 47447 DECEMBER 1, 1984, VALVE TAG NUMBER 1-MS-V53, 20-INCH VENT STACK (90* ELBOW) 10 )). a l wns LamonaTomas 2 j~ noni in. F.esniv. l %.'

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Page No. iii Report No. 47447-0 k l( r-TABLE OF CONTENTS (Continued) Page No. PHOTOGRAPHS l 1 OVERALL VIEW,16-INCH VENT STACK 11 2 SAFETY VALVE, TAILPIPE, DRIP PAN, & ELBOWS 12 r -- 3 SAFETY VALVE, TAILPIPE, DRIP PAN, & ELBOWS 13 '\\ APPENDIX I INSTRUMENTATION EQUIPMENT SHEETS 14 i i e ki . fs I 1. F 44 4 V a i... 1 i en0M*'* j Mumswe Feesmy

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2.0 REFERENCES

e, 'l-2.1 Wyle Laborttories' Quotation No. 544/2044-1/CP. ,L

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2.2 Wyle Laboratories' Test Plan No. 47447, Revision A. I 'L 2.3 Yank'ee Atomic Electric Company Purchase Order No. 104359 ) r 2.4 DRAVC0 Corporation Sketch No. E-2936-IC-14. 1 j j 2.5 DRAVC0 Corporation Sket'ch No. E-2937-IC-639. 2.6 American National Standard ANSI /ASME N45.2-1977, " Quality Assurance Program Requirements for Nuclear Facilities." t j' 3.0 TEST EQUIPENT AND INSTRISENTATION s. All instrumentation, measuring, and test equipment used in the performance i' of this test program were calibrated in accordance with Wyle Laboratories' iL Quality Assurance Program which complies with the requirements of Military i Specification MIL STD-45662. Standards used in performing all calibra-y, tions are traceable to the National Bureau of Standards by report number and date. When no national standards exist, the standards are traceable to international standards or the basis for calibration is otherwise docu-mented. b-The Instrumentation Equipment Sheets are presented in Appendix I. )I l g* g, g a gn },, _P"OLN.O",f.Z"T74"f,," I T W. Dysart TEST SY NUCLEAR PLANT SERVICES k-

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8 a. ~ ~-~~~~~-- ~~- ~ ^' M 's [. Page No. 2 -[ Report No. 47447-0' ] 4.0 PERSONNEL CERTIFICATION (, Wyle certifies that all personnel assigned to the steam valve facility are qualified for the tasks assigned. Personnel certification is achieved through personnel education levels, vocational training, and practical experitnce as outlined in ANSI-N45.2.6. 5.0 TEST SPECDEN DESCRIPTION 5.1 The initial. test specimen was fabricated in accordance with the configura-tion shown on References 2.4 and 2.5. The tailpipe was 10-inch Schedule ~. 80 pipe and fittings, and the vent stack was 16-inch Schedule 30 pipe and fittings. This duplicated the vent stack presently installed in the pl ant. (~ j 5.2 A. second vent stack, fabricated from 18-inch Schedule 10 pipe and fittings, was fabricated as a backup test specimen should the 16-inch vent stack prove to be inadequate. [ I 5.3 A third vent stack was subsequently fabricated from 20-inch Schedule 20 ) pipe and fittings. L 5.4 The fourth configuration used the 20-inch vent stack with the elbow removed. The 10-inch tailpipe was replaced with another section of 10-inch pipe and a 90* elbow Wiich discharged into the vent stack. 6.0 TESTS l 6.1 16-Inch Vent Stack + j_ The 16-inch vent stack,10-inch tailpipe, and 24-inch drip pan were fabri-cated and assembled in accordance with References 2.4 and 2.5, and instru-l mented as shown in Figure 1. A 6R10 Style.HA 75FN Crosby main steam 4 safety valve was used to supply steam to the vent stack. < e-l The system was pressurized with saturated steam and the valve was allowed i" to heat for a period of time. Since the valve was not being tested, no j '.- specific stabilization requirements were used. The data from the initial j actuation of the valve indicated that it only stroked 0.56 inches. Full stroke should be approximately one inch. The instrumentation and recording equipment was checked and the LVDT calibration verified. No problems were found. The valve was actuated a second time with the same results. It was j[ decided to remove the valve (Tag No.1-MS-V53) and install a second valve (Tag No.1-MS-V25). While the second valve was being installed, the valve manufacturer was contacted and apprised of the problem. It was recom-ir mended that the guide'(upper) ring be lowered 150 notches, which would Q, place it at the zero position. i b i wvts Lamonamass .l Muntevene Peculty h

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L., 'p Page No. 3 Report No. 47447-0 8.0-TESTS (Continued) 6.1 16-Inch Vent Stack (Continued) The second valve was allowed to heat and then actuated. The stroke was 'O.52 inches..Therefore, the upper ring was lowered 150 notches and the valve actuated a second time. The stroke was 1.04 inches. Visual obser-vation showed that there was significant blowback from the vent pipe. Some aspiration occurred den the valve disc dropped to the one-half open .I position. The valve was then adjusted and actuated at set pressures of 1238,1220,1203, and 1185 psig + 1 percent. In each case, the valve stroked fully; however, blowback-~from the vent pipe was observed. A video tape of the testing was furnished to the customer. p 6.2 18-Inch Vent Stack I '~ The second vent stack (18-inch) was then installed and the test repeated. In each case, the valve stroked fully; however, blowback from the vent 1 i stack was noted. t 6.3 20-Inch Vent Stack It was then decided to test' the 20-inch vent stack described in Paragraph 5.3. The test _ results were essentially the same. Blowback appeared to be +r less, but was still unacceptable. i 6.4 20-Inch Vent Stack with 90* Elbow ~ 0 The 20-inch vent stack configuration was then modified as shown in Figure i 2 and the tests repeated. The test results were the same. The first safety valve was installed in the system to determine if any valve !) problems existed. The results were the same after the upp_er ring was !L adjusted. ~ q 7.0 DATA I The tabulated data from 5 test series are shown in Tables I through V. p-The actual X-Y plots and oscillograph recordings will be stored in Wyle's { contract files. ) L Photographs of the 16-inch vent stack test setup are shown in Photographs { 1) 1, 2 and 3. 8.0 DISPOSITION { L The test program was placed "on hold" by the customer. The 20-inch vent j stack with a 90* elbow was left in place. The safety valve was covered i p with polyethylene and the other valve was placed in storage, j L-I y M .me. Huniewue reenny l

p~.__. ~.... = l + l '{7,~ Page No. 4 i p... Report No. 47447-0 . r iG ( i i ~ b i l , e-L VENT STACX (P, T ) i S S i DISCHARGE TEMPERATURE & PRESSURE a I ir

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} g 4.. A ii} d" TAILPIPE INLET TEMPERATURE & PRESSURE l . c.

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'i ~~ t, Page No. 5 I Report No. 47447-0 \\ / 9 '( i v .i )

I i

VENT STACK DISCHARGE (P, T ) S S c-i 20-INCH VENT STACK } [, (APPROXIMATELY 40 FEET LONG) 'l 1 ~_ - r-l C VENT STACK INLET (P, T ) 4 4 B. i 6" o I 6" A i n a 18" TAILPIPE DISCHARGE (P, T ) 3 3 i (~ j 10-INCH ASA ELBOW l ~ l o j -[ TAILPIPE INLET (P, T ) 2 2 i ) r' INLET STEAM (P), T)) L. a 3 1/2' \\ I d t f p FIGURE 2.- INSTRUMENTATION LOCATIONS (90* ELBOW /20-INCH VENT STACK) L.. I~O i I l 1

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y <6 s TABLE I TEST DATA SHEET, YANKEE ATOMIC J/N 47447, OCT08ER 17,1984 VALVE TAG NUMBER 1-MS-V25 16-INCH VENT STACK K HUN SET VALVE TEMP. ('F) PRESSURE (PSIG) TEMPERATURE ('F) LIFT RESEAT MAX. BLOW-1 NO. TIME PRESS. STEAM BODY SPRING P P P P T T T T (IN) PRESS. PRESS. DOWN ACCIM. 2 3 4 5 2 3 4 5 I 1 1328 1255 56? 262 83 <100 <100 28 12 295 285 280 235 0.52 1181 1300 5.9 3.5 * -~, p ' ~ t j 2 1404 1241 561 278 97 146 145 38 28 330 335 290 270 1.04 1161 1247 6.4 0.5 i. i 3 1441 1233 561 286 115 163 140 44 40 340 345 285 275 1.06 1156 1255 6.2 1.8 i 4 1523 1261 561 285 130 170 145 44 39 335 350 285 275 1.06 1176 1274 6.7 1.0 5 1558 1221 555 295 138 167 138 43 37 335 345 285 270 1.06 1140 1231 6.6 0.8 gy > 1 31 6 1619 1200 547 295 147 170 140 42 37 330 330 285 270 1.04 1125 1215 6.3 1.2 3 g 7 1635 1185 560 291 154 172 137 43 37 330 330 285 270 1.04 1112 1202 6.2 1.4 .Ih 1 f O i i i t l f~ % k liW I NOTES: 1) Moved upper ring down 150 notchesQafter Run No.1.h

4) Adjusted 1 flat counterclockwise after Run No. 5 and No. 6.

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2) Adjusted 1 3/4 flats clockwise after Ron'Nor f

3) Adjusted 21/2 flats counterclockwise after Run No. 4.

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'f .-.a f ~ ' ^ ~ '~ ^f ' '.. y v-3 ~ ~) 4 g e.~ ) ~* T j) }l, y ~! .aEV a, TEST DATA SHEET, YANKEE ATOMIC J/N 47447 DECEMBER 1, 1984 ~j 2,3 2 )/" VALVE TAG NUMBER 1-MS-V53 20-INCH VENT STACK (90* ELBOW) s NUN SET VALVE TEMP. ("F) PRESSURE (PSIG) TEMPERATURE (*F) LIFT RESEAT MAX. BLOW-NO. TIME PRESS. STEAM BODY SPRING P P P P T T T T (IM) PRESS. PRESS. DOWN ACCT 94. 2 3 4 5 2 3 4 5 1 1014 1237 560 279 49 186 154 6 10 362 370 180 225 i.10 1160 >1325 6.2 r h6.6 (Q-l 2 1027 1243 555 269 33 84 63 r3 -2 310 290 200 200 M 1158 1289 6.8 (3.7 IN 3 1105 1234 562 285 55 176 154 N/D 10 360 335 240 228 1.10 1143 1258 7.4 1.9 EE ER A E E' ',, 8 5t.6 NOTES: 1) P4 at position "C" for Runs No. I and No. 2. Only achieved half lift on Run No. 2.

2) P4 moved to position "A" for Run No. 3.

P4 malfunctioned. Upper ring moved down 150 notches to zero posit 1on. 7 $~ g(g 6 (, /fOf l 3 ! 'i .) 5 W "m h a' y, \\ .a n I ocus L..-.- ~- '~ ~ ' - ~ ^ ~ ~ ' ~ ~ ^ ~ ~ ...i-.---k

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.,.g pq p. r --. r-r-, 3 +--, - -] .- i ) 4-d ,.[', TABLE IV 'i .I' TEST DATA SHEET, YANKEE ATONIC J/N 47447, NOVEMBER 30, 1984 VALVE TAG NUMBER 1-MS-V25 i 20-INCH VENT STACK (90* ELE 0W) '~ .y LIFT!-; PRESS. 1 ~ NUN SET VALVE TEMP. 1'F) PRESSURE - PSIG) TEMPERATURE (*F) tESEAT MAX. BLOW-1 i NO. TIME PRESS. STEAM BODY SPRING P P P P T T T T (III) PRESS. DOWN ACCIM. 2 3 4 5 2 3 4 5 1 1025 1225 555 248 82 164 149 42 10 360 348 248 232 1.14 1137 1264

7. 2, 3.1 j

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-6 1342 1200 556 305 160 154 1 31 4 10 358 330 179 230 1.1 1125 1221 6.2 1.7 l

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.N '. i Ot 7' o i ~ t i r l NOTES: 1) P4 in "A" position for Runs 1-5, moved to "C" position for Run 6. ' ? S I: ' " 2) Rewoved drip pan for Runs 3-6. For Runs 3 and 5, facility valve didlnot open. l 3) No accianulation was obtained. ~

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pj p [-i p 1- (s gj ^, r- -1 r- -7 -1 r7 l 7 ,k-TABLE III TEST DATA SHEET, YANKEE ATOMIC J/N 47447, NOVEMBER 28, 1984 VALVE TAG NUMBER 1-MS-V25 20-INCH VENT STACK r I RUN SET VALVE TEMP. ('F) PRESSURE LPSIG) YEMPERATURE (*F) LIFT RESEAT MAX. BLOW-1 l' NO. TIME PRESS. STEAM 80DY SPRING P P P P T T T T (1N) PRESS. PRESS. DOWN ACCtM. l. 2 3 4 5 2 3 4 5 I 1210 1268 553-306 57 166 145 40 12 355 315 265 240 1.12 1176 1274 7.2 0.4 2 1236 1265 557 321 40 161 147 41 12 370 320 270 243 1.16 1176 1279 7.0 1.1 .g, 3 1338 1251 558 313 51 159 137 41 12 370 N/D 292 242 1.16 1162 1270 7.1 1.5 l, I 4 1415 1232 559 300 104 158 145 41 12 368 330 268 242 1.12 1145 1257 7.1 1.9 S 1444 1214 557 306 118 157 143 40 13 370 325 270 242 1.14 1130 1247 6.9 2.6 E7 E2 A g g. O2 ? o i l I NOTES: 1) Mjusted 1/2 flat counterclockwise after :un No. 3.

2) Mjusted I flat counterclockwise after Ru No. 4.

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.m ['--) O -- 7 (7 F )_ ( 1 17 P: f; 7 f" '] F1 ~i 1n "'] 7-F ) TABLE II TEST ORTA SHEET, YANKEE ATOMIC J/N 47447, OCTOBER 19, 1984 VALVE TAG NUMBER 1-MS-V25 ) 18-INCH VENT STACK ~ t 1 ~ NUN SET VALVE TEMP. ("F) PRESSURE

PSIG)

TEMPERATURE ('F) LIFT RESEAT MAX. BLOW-1 ~L NO. TIME PRESS. STEAM BODY SPRING P P P P T T T T (IN) PRESS. PRESS. DOWN ACCtM. 2 3 4 5 2 3 4 5 I-MIS 1198 557 245 107 184 140 39 32 345 335 300 250 1.16 1116 1225 6.4 2.2 i! ? 0935 1194 555 264 119 188 140 54 33 350 330 300 250 1.12 1116 1226 6.5 2.6 3 0957 1207 559 271 130 188 138 63 33 345 330 300 250 1.18 1125 1232 6.8 2.0 -4 1011 1205 557 270 129 193 142 67 32 350 320 300 250 1.12 1126 1256 6.5 '4.IN ~ 5 1044 1228 561 290 118 191 140 64 32 345 325 310 245 1.18 1139 1240 7.2 0.% 6 1057 1216 558 288 115 194 142 67 32 350 330 305 250 1.12 1134 1250 '6.7 2.7 E2 I ~ 32 7 1118 1238 563 279 129 1% 145 70 32 345 325 300-250 1.16 1148 1254 7.3 1.3-A g, y. e 8 1135 1235 563 290 139 194 146 68 32 345 320 300 250 1.12 1150 1266 6.9 2.4 w 9 1206 1259 566 288 145 198 150 70 30 345 330 300 250 1.22 1164 1279 7.5 1.6 10 1217 1250 563 292 156 196 146 69 32 350 335 300 250 1.14 1162 1276 7.0 2.0 b I NOTES: 1) Mjusted I flat clockwise after Run No. 2.

2) Mjusted I flat clockwise af ter Run No. 4.

Verified calibration of P4.

3) Mjusted I flat clockwise af ter Run No. 6.

4) Mjusted 1 1/4 flats clockwise after Run No. 8.

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