ML20042G854
| ML20042G854 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/03/1990 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9005160179 | |
| Download: ML20042G854 (360) | |
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r .a - L var Vallsy Powtr Stition SNppingport, PA 15077-0004 ( fc7 prs. UIPuuci ,o,ou, " " " May 3, 1990 U. S. Nuclear Regulatory Commission Attn:- Document Control Desk Washington, DC 20555 l 7
Reference:
Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Potentially Invalid Leak Detection Tests Used- as an Alternative for Required ASME, Section XI Hydrostatic Tests ? s Gentlemen: > In response to your letter dated November 22, 1989 on the subject testing, Duquesne Light (DLC) has ' reviewed all the testing performed at- Beaver Valley Units 1 and 2 utilizing the Instrumented Inspection = Technique (IIT) methodology described in Topical Report HAFA 135 (P-A). . Our technical review found the tests (listed in attachment 1) Eto1 be in technical compliance with the testing requirements of-the Topical Report. However, review of these tests for compliance to the training- and qualification requirements specified in the Topical was found to be deficient. Subsequently, HAFA International was'
-evaluated .by our Quality Assurance organization and was found to be-deficient in their adherence to the requirements of'10CFR50 Appendix BLin several categories.
A summary of the audit is provided in Attachment II. As a 3
. result, Duquesne Light Company considers all-IIT testing performed at t the Beaver Valley Units 1 and- 2 to be invalid on the basis that
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significant- ' deficiencies existed in the areas of 'perscanel, certification and RAFA's overall adherence to its Quality Assurance-Program. IIT Testing was performed on the following systems at Beaver-Valley, We have performed operability assessments for the Beaver
' Valley Unit 1 systems and they are provided in Attachment III. 'The IIT testing performed on the Beaver Valley Unit 2 Service Water system is considered to be for information only and was not done as an alternative to ASME Section XI hydrostatic testing requirements.
Therefore, no Beaver Valley Unit 2 systems are affected by invalid 2 IIT' testing. i 0bCko'0000]34 PDC
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.4' LInvalid Lenk Detcction ASME, Section XI 'I Page 2 1 i
U I Systems Affected Chemical and Volume control System Residual Heat Removal System ' Safety Injection System. Gaseous Waste System
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Containment Depressurization System Main Steam System Feedwater System Steam Generator Blowdown System River Water System
. Reactor Plant Component Cooling System Unit 2 Service Water System Although Duquesne Light considers all HAFA testing performed to be invalid, the systems affected are considered to-be functionally. ,
operable based on the following activitiesiand surveillances:
- Repeatable and acceptable service of the systems over the past several years. -
-The acceptable testing of components and systems through the In-Service Inspection Non-Destructive Examination Program and the In-Service Testing Pump and Valve Program.
- The acceptable performance of the leak tests performed by DLC personnel, certified.as.VT-2 examiners, during the performance of IIT testing although the IIT testing personnel themselves could not- be verified as certified through audit. Additionally DLC personnel did directly supervise the performance of the IIT -1 testing and verified that the personnel-involved did execute.the '
procedures as written. The procedures themselves were also . evaluated by the DLC Engineering Group and found to be in I accordance with the requirements of the Topical Report. Duquesne Light has successfully completed OSTs (Operational y Surveillance Tests) on all the above systems except for the-u Gaseous Waste system and Steam Generator Blowdown system and-found the results to be acceptable. A review of the affected Unit 1 systems has noted that the ASME Section XI, End Of Interval Hydrostatic Testing requirements for l these systems have not been performed. These systems were examined i at or near the operating pressures rather than at the specified elevated pressures required by ASME Section XI. This condition while not being in full compliance with the ASME Code does not constitute a significant safety concern for the following reasons:
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>e 1 Invalid Lenk DetOction ASME, Scction XI Page 3 j
A significant number of the components and welds within these systems have been non-destructively tested in accordance with ASME- Section XI over the past 40 months and been found to be l structurally sound. Leakage examinations in accordance with ASME Section XI have been- l performed in addition to the leakage examinations performed during the IIT tests and no indications of any loss of structural , integrity was observed.
- Operational surveillance testing and the In-Service Test Program for Pumps and Valve have demonstrated the systems to be operable and reliable.
Since full compliance to the End Of Interval, ASME Section XI, Hydrostatic Testing requirements were not entirely met, the following corrective actions are being taken:
' 1. All HAFA IIT testing has been discontinued at Beaver Valley.
'2. We will perform the ASME Section XI required "End Of Interval" testing in accordance with the rules of the Code in effect for the current interval for each Unit.
- 3. We plan to increase the amount of non-destructive examinations performed on the systems affected by the invalidation of the IIT testing by 10% over the amount of regularly scheduled examinations for the current inspection Period of this Interval at BVPS Unit #1.
If_ you have any questions concerning this response, please contact my office. Very truly yours, l: b, --
. D. Sieber Vice President Nuclear Group
-Attachments I, II, III, IV Enclosure I cc: Mr. J. E. Beall, Sr. Resident Inspector (w/o enclosure I)
Mr. T. T. Martin, NRC Region I Administrator Mr. P. S. Tam, Sr. Project Manager (w/o enclosure I) Mr. R. A. McBrearty, NRC Region I Inspector
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ATTACHMENT 1 i HAFA TESTS PERFORMED AT UNIT 1 L DURING THE FIRST INSPECTION INTERVAL L TEST NO. DESCRIPTION TEST DATE 7.1 CHARGING PUMP DISCHARGE-PIPING TO.RCS 01/02/88
- i. 7.1.1 "C" CHARGING PUMP DISCHARGE TO CH-27 & 161 02/04/88 L 7.2 CHARGING PP. DISCHARGE TO REGEN. HX 01/03/88 1 7.2.1 CHARGING LINES THROUGH REGEN. HX 01/27/88 7.4 BORIC ACID XFR PP. DISCHARGE LINES 10/09/87 ;
7.5 RCP SEAL INJECTION LINES 12/22/87 7.5.1 1CH-174, 176 & PIPING (REPAIR / REPLACEMENT) 02/03/88 7.6 RCP SEAL PIPING 12/20/87
-7.8 REGEN & NON-REGEN HX CONNECTING LINES 12/28/87 7.9 CHARGING PP. SUCTION LINES 12/30/87-7.10 REGEN HX TO RCS LOOP B COLD LEG 05/30/87 7.11 REGEN HX TO PRESSURIZER 05/30/87 10.1 RHR LINES - (MOV-RH-701 TO 720A&B) 01/14/86 _,1 l 10.2 RHR PUMP DISCHARGE LINES 06/10/86 10.3 RHR DISCHARGE TO RWST 05/04/87 10.4 RHR PIPING BETWEEN MOV-RH-700 & 701 02/23/88 11.1 SI ACCUMULATOR DISCHARGE LINES 08/13/86 11.2 CHARGING & LHSI DISCHARGE TO RCS HOT LEGS 05/22/87 L CHARGIHG & LHSI DISCHARGE TO RCS COLD LEGS '
11.3 05/12/87 11.4.1 LHSI INTO RCS HOT LEGS 02/17/88 ! 11.4.2 CHARGING DISCHARGE LINES INTO RCS HOT LEGS 02/25/88 r 11.5.1 LHSI TO-RCS COLD LEGS 02/17/88- l 11.5.2 CHARGING PP. DISCHARGE LINES TO RCS COLD LEGS 02/25/88 ' 11.6 CHARGING PP. SUCTION FROM LHSI PUMP 1A 09/29/87 11.7 RWST SUPPLY TO LHSI 8 CHARGING PP. SUCTION 01/05/87 , 11.8 LHSI PUMP SUCTION 12/13/87 , 11.11 BORON INJECTION TANK PIPING 04/28/87 11.12 SI-P-3A,3B DISCHARGE PIPING 02/10/88 11.13 SI ACCUMULATOR TANK (SI-TK-1A) 12/16/87 11.14 SI ACCUMULATOR TANK (SI-TK-1B) 12/16/87 l 11.15 SI ACCUMULATOR TANK (SI-TK-1C) 01/06/88 ; 11.16 SI ACCUMULATOR FILL LINES FROM HYDRO TEST PUMP 12/14/87 l 13.1 QUENCH SPRAY PUMP 1A SUBSYSTEM 07/16/86 13.2 QUENCH SPRAY PUMP 1B' SUBSYSTEM 07/16/86 h 13.3 CHEMICAL INJECTION SUBSYSTEM 07/16/86 13.4 REFUELING WATER RECIRC PUMPS SUCTION 09/21/87 13.5 REFUELING WATER RECIRC PUMPS DISCHARGE 09/23/87 13.6 RECIRC SPRAY PUMP RS-P-2A SUCTION 01/29/88 13.7- RECIRC SPRAY PUMP RS-P-2B SUCTION 02/01/88
e i ATTACHMENT 1. continued ] TEST NO. DESCRIPTION TEST DATE
'15.1 COMPONENT COOLING WATER MAIN HEADER 01/22/88 15.2 CRDM SHROUD COOLING COILS 01/14/88 r 15.3 LINES FROM CONTAINMENT AIR RECIRC COOLING COILS 01/08/88 15.4 LINES TO CONTAINMENT AIR RECIRC COOLING COILS 01/08/88 ,
19.1 GASEOUS WASTE DECAY TANK 1A 07/25/86 i E19.2 GASEOUS WASTE DECAY TANK 1B 07/.26/86 19.3 GASEOUS' WASTE DECAY TANK 1C 07/26/86 i 21.1.1 FW-P-2 STEAM SUPPLY LINES 05/29/87 21.1.2 AE LEAK DETECTION ON MAIN STEAM PIPING - 02/23/88 21.1.3 AE LEAK DETECTION ON STEAM GENERATOR RC-E-1A 02/09/88-21.1.4 AE LEAK DETECTION ON STEAM GENERATOR RC-E-1B 02/06/88 21.1.5 AE LEAK DETECTION ON STEAM GENERATOR RC-E-1C 02/10/88 24.1.1 AUX FD PUMP SUCTION LINE [FW-P-2) . 04/10/87 24.1.2 AUX FD PUMP SUCTION LINE FROM RW [FW-P-2] 04/10/87 24.2.1 AUX FD PUMP 3A SUCTION LINEL 04/14/87 24.2.2 AUX FD PUMP 3A SUCTION LINE FROM RW 04/15/87 24.3.1 AUX FD PUMP 3B SUCTION LINE 04/14/87 24.3.2 AUX FD PUMP 3B SUCTION LINE FROM RW 04/14/87 24.4 AUX FD PUMPS SUCTION FROM RW SYSTEM 04/09/87 24.5 AUX FD PUMP 2 RECIRC LINE 04/16/87 24.6 AUX FD PUMP 3A RECIRC LINE 04/15/87 24.7 AUX FD PUMP 3B RECIRC LINE 04/14/87 24.9 AUX FD PUMPS DISCH TO LAST VALVE BEFORE S/G's' 05/19/87- , 24.10 AE LEAK DETECTION ON MAIN FEEDWATER PIPING 02/23/88 25.1.1 AE LEAK DETECTION ON STEAM GEN.' BLOWDOWN PIPING 02/23/88- , 25.2.1 S/G [RC-E-1A) BLOWDOWN PIPING 01/25/88 25.2.2 S/G [RC-E-1B] BLOWDOWN PIPING 01/14/88 25.2.3 S/G (RC-E-1C) BLOWDOWN PIPING 01/15/88 , 30.1 "B" RW HEADER 08/31/87 30.'2 "A" RW HEADER 09/03/87 30.4 BACKFLOW THROUGH CHECK VALVE [1RW-106] 01/13/88 30.5 BACKFLOW THROUGH CHECK VALVE [1RW-107) 01/08/88-30.6 CHARGING PP COOLER CH-E-7A RW LINES 09/14/87 30.7 CHARGING PP COOLER CH-E-7B RW-LINES 09/11/87 30.8 CHARGING PP COOLER CH-E-7C:RW LINES 09/10/87 30.9 RW LINES DISCH OF CH PP COOLERS & CR A/C COND. 01/06/88-30.10 "A" HEADER SUPPLY TO CHARGING PUMP COOLERS 10/01/87 30.11 "B" HEADER SUPPLY TO CHARGING PUMP COOLERS 09/15/87 30.15 RW PUMP 1A RECIRC LINE 09/08/87 30.16 RW PUMP 1B RECIRC LINE - 09/08/87 30.17 RW PUMP 1C RECIRC LINE 09/08/87
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30.18 RW SUPPLY TO CCR HX CC-E-1A 12/11/87 30.19 RW SUPPLY TO CCR HX CC-E-1C 12/07/87 1 30.20 RW SUPPLY TO CCR HX CC-E-1B 12/16/87 4 o
i., ATTACHMENT 1. continued HAFA TESTS PERFORMED AT UNIT 2 DURING THE FIRST INSPECTION INTERVAL: TEST NO. DESCRIPTION TEST DATE l 230.6 CHARGING-PUMP COOLER 2CHS-E25A 10/02/89 230.7 CHARGING PUMP COOLER 2CHS-E25B 10/05/89 I 230.8 CHARGING PUMP COOLER 2CHS-E25C 10/04/89 230.9 CONTROL ROOM A/C UNIT 2HVC-ACU201A 11/08/89
'230.10 CONTROL ROOM A/C UNIT 2HVC-ACU201B 10/11/89. j t
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ATTACHMENT II Summary of QA Audit Vend-90-03 Audit of HAFA International Inc. In response to : concerns addressed in NRC- letter dated 11/22/89, entitled "Potentially Invalid Leak Detection Test Used as an 1 Alternative for Required ASME Section XI Hydrostatic Tests", and at the request of Duquesne Light Company Nuclear Engineering Department i an audit was conducted of HAFA International, Inc. The audit was '
~ performed to support an engineering evaluation of the Instrumented Inspection Technigt.- (IIT)- Testing Methodology employed at Beaver valley Power Stat;.x=. IIT is an NRC approved alternative to >
Hydrostatic Testing as specified in ASME Section XI for Class 1,2, : and 3 components and systems. i The Engineering request stated that as a minimum, the audit should address the following area: A. Verification that HAFA training and certification procedure QAP 9.2 meets the requirements of ANSI N45.2.6 and specifies that' personnel shall be certified by written examination. B. Verification that the personnel performing'the IIT tests at Beaver Valley were properly certified to the appropriate level and discipline at the time of testing at' Beaver , Valley. C.. Verification that HAFA International Inc. operates in accordance with its established Quality Assurance program and is therefore considered a viable Appendix B supplier for i testing services. The . audit revealed significant deficiencies existed in all three areas c audited. Nine findings and five observations were identified. The findings are summarized as follows: r l L
- 1. Personnel certification procedure not meeting the intent of.
ANSI N45.2.6 as required.
- 2. Test personnel not certified by written examination as l required.
'3. Failure to notify DLC of the effects Finding'#1 and #2 above i have on the Testing performed at BVPS.
- 4. Issuing test reports without verification that M & TE has, passed Post-test Calibration.
- 5. Control and issuance of quality related documents.
- 6. Failure to identify and segregate nonconforming items.
- 7. Failure to perform audits of adhesive suppliers.
- 8. Control and retrieval of quality records.
a Att0 chm:nt II, continued'
- 9. Failure to conduct internal and' external audits as scheduled.
l The observations concerned the following:
- 1. Duties and responsibilities not corresponding to the revised organization chart.
2.- Reading lists not being revised / updated as required.
- 3. Receipt inspections not performed on quality related orders.
- 4. Closing of Discrepancy Reports without QA and Engineering review and approval.
- 5. Missing lead auditor certifications.
Based on the results of this audit, it was concluded that HAFA International Inc., is deficient in the implementation of a' Quality i Assurance Program that meets 10CFR50 Appendix B requirements. As a-result, HAFA _was placed on a Hold status and no category IA (Safety related) purchase orders may be issued until these deficiencies-are satisfactorily resolved. ii t i l l l 1 1 L
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't P ATTACHMENT III' ,
j. SYSTEM OPERABILITY ASSESSMENTS I l' l-I i
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Systca optrability Acc30casnt for the Beaver Valley Unit 1 Chemical and Volume Control System The following HAFA IIT tests were performed on the Beaver Valley Unit 1 (BV-1) Chemical and Volume Control' System (CVCS): TEST NO. DESCRIPTION 7.1 CHARGING PUMP DISCHARGE PIPING TO RCS-7.1.1 '"C" CHARGING PUMP DISCHARGE TO CH-27 & 161 7.2 CHARGING PP. DISCHARGE TO REGEN. HX 7.2.1 CHARGING LINES THROUGH' REGEN. HX 7.4 BORIC ACID XFR PP. DISCHARGE LINES 7.5 RCP SEAL-INJECTION LINES > 7.5.1 1CH-174, 176 & PIPING (REPAIR / REPLACEMENT) 7.6 RCP SEAL PIPING .
- i. 7.8 REGEN & NON-REGEN HX CONNECTING LINES 6 7.9 CHARGING PP. SUCTION LINES 7.10 REGEN HX TO RCS LOOP B COLD LEG 7.11 REGEN HX TO PRESSURIZER A Nuclear Engineering Department task force was established to review all of the HAFA IIT testing performed at Beaver Valley for. compliance ,
~ to ' HAFA Topical Report 135 (P-A). Ten criteria were established as the requirements for compliance to the Topical Report and are listed in Attachment IV. All of the HAFA IIT tests performed on the BV CVCS system were found to be in technical- compliance with the a requirements of the Topical Report with the exception of criterion 3 ;
which- concerned personnel qualification, und criterion 7 which required the test results to be reviewed by ANSI N45.2.6 certified personnel. l- Significant deficiencies were found in the area of personnel l qualification -during the QA Audit (Vend-90-03) of HAFA International l Inc. The results of the QA Audit are listed in Attachment II. 1 1Although DLC considers all HAFA testing at Beaver Valley to be invalid, the CVCS is considered _ to have maintained _ structural integrity and are functionally operable based on the -following j activities and surveillances: L - Almost the entire CVCS is pressurized to normal system operating
-pressure' during normal system arrangement or during routine system evolutions. Portions of the CVCS that are normally isolated would be pressurized when those portions of the system l
are-placed into service.
- Normal plant tours by Operations personnel are. performed on a 4 shift basis in all plant areas that the CVCS is located with the exception of the Containment Building. Any major pressure boundary leakage could in conjunction with installed instrumentation be detected during these tours.
Relief valves installed in the CVCS provide overpressurization protection and are tested according to ASME Section XI where required. l^
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. ATTACHMENT III, continued-Chemical and Volume Control System
- The CVCS is a radioactive system, therefore, any major pressure boundary leakage _ would result in an increase in airborne radioactive activity which would be detected by various plant area radiation monitors.
- All ASME Section XI pump and valve components in the CVCS are tested in accordance with the BV-1 In-Service Testing Program.
The In-Service Testing Program assures the operability of the CVCS pumps and valves.
- Portions of the CVCS are pressurized to system pressure during Operational Surveillance Testing (OSTs). OSTs have specific acceptance criteria which must be met and are based on Technical Specification surveillance requirements. The following OSTs test portions of the CVCS on a quarterly frequency:
QSI TITLE 1.7.1 Boric Acid Transfer Pump (1CH-P-2A) Operational Test 1.7.2 Boric Acid Transfer Pump (1CH-P-2B) Operational Test 1.7.4 Centrifugal Charging Pump Test (1CH-P-1A) 1.7.5 Centrifugal Charging Pump Test (1CH-P-1B) 1.7.6 Centrifugal Charging Pump Test (1CH-P-1C) The following OSTs test portions of the CVCS on a refueling outage frequency: Q1T TITLE 1.7.11 Charging System and Safety Injection System Operability Test 1.7.13 Boric Acid Transfer Pump (1CH-P-2A) Operational Test During Refueling 1.7.14 Boric Acid Transfer Pump (1CH-P-2B) Operational Test During Refueling
- Any CVCS pressure boundary leakage would end up in either the Primary Auxiliary Building, Safeguards Building or Containment <
Sumps which would result in increased sump levels or sump pump out rate.
- Nondestructive examinations required by ASME Section XI have been performed on the CVCS in accordance with the BV-1 In-Service Inspection Program.
- Leakage examinations are performed on the CVCS periodically as required by ASME Section XI. These examinations were performed by DLC personnel certified as VT-2 examiners.
1 , 1 ATTACHMENT III, continusd Chemical and Volume control System
- A set of color coded isometrica has been prepared for each-HAFA IIT test performed .at Beaver Valley Unit 1. These isometrics identify the following tests or examinations performed within the IIT test boundary according to color code:
Color DescriDtion i Blue HAFA-IIT Test Green Nondestructive Examination Pink Leakage Examination Orange BVT Yellow OST These isometrics are provided in Enclosure I. Based on the above, the CVCS has been determined to be structurally sound and functionally operable.
1 Syston op;rability-Acccccannt 4 for the Beaver Valley Unit 1 Residual Heat Removal System The following HAFA IIT tests were performed on the Beaver Valley Unit 1 (BV-1) Residual Heat Removal-(RHR) System. L 1 l TEST NO. DESCRIPTION h 10.1 RHR LINES (HOV-RH-701 TO 720 A&B) 10.2 RHR PUMP DISCHARGE LINES 10.3 RHR DISCHARGE TO RWST l 10.4 RHR PIPING BETWEEN MOV-RH-700 & 701 A Nuclear Engineering Department task force was established to review all of the HAFA IIT testing performed at Beaver Valley for compliance to HAFA Topical Report 135 (P-A). Ten criteria _were_ established as the requirements for compliance to the Topical Report and are listed in Attachment IV. All of the HAFA IIT tests performed on the BV-1
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system were found to be in technical compliance with the requirements of the Topical Report with the exception of the following:
- a. Criterion 3 -
All personnel are to be certified by written examination in accordance with ANSI N45.2.6 and HAFA Procedure 9.2.
- b. Criterion 5 -
All IIT tests are subject to a 2 hour hold time at operating pressure prior to the VT-2 walkdown.
- 1. A three foot section of insulated piping between MOV-RH-700. and MOV-RH-701 was not held the required 2 hours. This violation was not a basis for declaring the test invalid since this same section of line was held at operating pressure for four hours or more during the Mode 3 leakage walkdown performed prior to start-up,
- c. Criterion 7 - IIT test results are reviewed and accepted by ANSI N45.2.6 certified personnel.
Significant deficiencies were found in the area of personnel qualification during the QA Audit (Vend-90-03) of HAFA International Inc. The results of the QA Audit are listed in Attachment II. Although DLC considers all HAFA testing at Beaver Valley to be invalid, the RHR System is considered to have maintained structural integrity and is functionally operable based on the following activities and surveillances: _Almost the entire 'RHR System is pressurized to normal system operating pressure during Modes 5 and 6 while in normal system arrangement or during routine system evolutions. Portions of the RHR System that are normally isolated in Modes 1,2,3 and 4 would be pressurized when those portions of the system are placed into service.
- o' ATTACHMENT III, c::ntinuad
-Residual Heat Removal System Relief valves installed in the RHR System provide overpressurization protection and are tested-according to ASME Section XI where--required.
- The RHR System is a radioactive system, therefore, any major pressure boundary leakage would result in a increase in airborne radioactive activity which would be detected by the containment area radiation monitors.
All ASME Section XI pump and valve components in the RHR System are tested in accordance with the BV-1 In-Service Testing Program. The In-Service Testing Program assures the operability of the RHR pumps and valves. L
- Portions of the RHR System are pressurized to system pressure during Operational Surveillance Testing (OST). OSTn have L specific acceptance criteria which must be met and are based on Technical Specification surveillance requirements. OST 1.10.1
" Residual Heat Removal Pump Performance Test" pressurizes the majority of the RHR System in Mode 4 prior to entering Mode 5 on l a refueling frequency or any shutdown to Mode 5 unless completed E within the. previous quarter.
- While the RHR System is in operation, important RHR System operating parameters are checked each shift by Operating Log L L5-41.
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Any RHR System pressure boundary leakage would drain to the Containment Sump. The containment Sump' level is monitored and alarmed in the Control Room. > l Nondestructive examinations required by ASME Section XI have been l performed on the RHR System in accordance with the BV-1 l In-Service Inspection Program.
- Leakage examinations are performed on the RHR System periodically t as required by ASME Section XI. These examinations were
( performed by'DLC personnel certified as VT-2 examiners. 1 A set of color coded isometrics has been prepared for each HAFA IIT. test performed at Beaver Valley Unit 1. These isometrics identify the following tests or examinations performed within the IIT test boundary according to color code: Color Descriotion l Blue HAFA IIT Test Green Nondestructive Examination Pink Leakage Examination Orange BVT Yellow OST ,
bi . . ATTACHMENT III,,contiriutd . Residual Heat Removal. System
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-These isometrics.are provided in Enclosure I. :
Based on the above, the RHR System has been determined to be e
. structurally' sound and functionally operable.
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4 Syctsa Op3rtbility: Accosem2nt for the Beaver Valley Unit 1 : Safety Iniection System The following HAFA IIT tests were performed on the Beaver Valley Unit .
- (BV-1) Safety Injection (SI) System:
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TEST NO. DESCRIPTION 11.1 SI ACCUMULATOR DISCHARGE LINES 11.2 CHARGING & LHSI DISCHARGE TO RCS HOT LEGS ' 11.3 CHARGING & UC?T DISCHARGE TO RCS COLD LEGS 11.4.1 LHSI INTO RCS IiOT LEGS 11.4.2 , CHARGING DISCHARGE LINES INTO RCS HOT 12GS 11.5.1 LHSI TO RCS COLD LEGS 11.5.2 CHARGING PP. DISCHARGE LINES TO RCS COLD 1 LEGS 11.6 CHARGING PP. SUCTION FROM LHSI PUMP 1A , 11.7 RWST SUPPLY TO LHSI & CHARGING PP. SUCTION-11.8 LHSI PUMP SUCTION 11.11 BORON INJECTION TANK PIPING 11.12 SI-P-3A,3B DISCHARGE PIPING 11.13 SI ACCUMULATOR TANK.(SI-TK-1A) 11,14 SI ACCUMULATOR TANK (SI-TK-1B) 11.15 SI ACCUMULATOR TANK (SI-TK-1C) 11.16 SI ACCUMULATOR FILL LINES FROM HYDRO TEST PUMP i A Nuclear Engineering Department task force was established to review ~ all of the HAFA IIT testing performed at Beaver Valley for compliance to HAFA Topical Report 135 (P-A). Ten criteria were established as . the- requirements for compliance to the Topical Report and are listed 1 in Attachment IV. All of the HAFA IIT tests performed on the BV-1 SI system were found to be in technical compliance with the requirements of the Topical Report'with the exception of the following:-
- a. Criterion 3 -
All personnel are to be certified by written examination in accordance with ANSI N45.2.6 and HAFA Procedure 9.2. t
- b. Criterion 4 -- All IIT tests are to be performed at normal operating pressure.
- 1. IIT 11.4.1 and 11.5.1 had portions of the test boundaries pressurized at a level lower than normal operating pressures.
- 2. IIT 11.4.1 met the requirements for a ASME Section XI' Hydrostatic test and therefore meets the requirements of l the Code.
- 3. The portions of IIT 11.5.1 that were identified as being tested below the normal operating pressure of the system L (150 psi verses 2235 psi), were tested to the Class 1 hydrostatic testing requirements during the Mode 3 ASME Section XI Hydrostatic test performed during start-up.
Additionally, the high pressure lines in IIT 11.5.1 were tested to 2290 psi in IIT 11.5.2. l
6 ATTACHMENT III, continutd
- Safety Injection-System
- c. Criterion 7 - IIt testing are to be reviewed and accepted by ANSI N45.2.6 certified personnel.
Significant deficiencies were found in the area of personnel qualification during the QA Audit (Vend-90-03) of HAFA International Inc. The results of the QA Audit are listed in Attachment II. Although DLC considers all HAFA testing at Beaver Valley to be invalid, the SI System is considered to have maintained structural integrity and is functionally operable based -on the following activities and surveillances:
- Portions of the SI System, such as the Accumulator Subsystems and Boron Injection Tank Subsystems are pressurized to normal system operating pressure during normal system arrangement or during routine system evolutions. The majority of-the remaining portion of the SI System that are normally isolated would be pressurized when those portions of the system are tested.
- Normal plant tours by Operations- personnel are performed on a shift basis in all plant areas that the SI System is located with the exception of the Containment Building. Any major pressure boundary leakage could be detected during these tours or in '
conjunction with installed instrumentation.
- Relief valves installed in the SI System provide overpressurization protection and are tested according to ASME Section XI where required.
The SI System is a radioactive system, therefore, any significant pressure boundary leakage would result in an increase in airborne radioactive activity which would be detected by various plant area radiation monitors. All ASME Section XI pump and valve components in the SI system are tested in accordance with the BV-1 In-Service Testing program. The In-service Testing Program assures the operability of the SI System pumps and valves. Portions of the SI System are pressurized to system pressure during operational Surveillance Testing (OSTs). OSTs have specific acceptance criteria which must be met and are based on Technical specification surveillance requirements. OST 1.11.1
" Safety Injection Pump Test (1SI-P-1A)" and OST 1.11.2 " Safety Injection Pump Test (1SI-P-1B)" test the Low Head Safety Injection pumps portions of the SI System on a quarterly frequency. OST 1.11.14 " Safety Injection Full Flow Test" which is performed- on a refueling frequency demonstrates that the High Head Safety Injection (HHSI) pumps can take suction from the Low l Head Safety Injection (LHSI) pumps and that both HHSI and LHSI pumps can provide flow to the Reactor Coolant System from the l Refueling water Storage Tank.
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- 1BVT 1.11.02 " Safety Injection Recirculation Mode Leak Test" L pressurized portions of the SI System on a refueling frequency to l identify leakage from the SI system in the recirculation mode.
-ATTACHMENT III, continuOd Safety Injection System
- Any SI System pressure boundary leakage would end up in either I the Primary Auxiliary Building, Safeguards Building, or containment Sumps which would result in increased sump levels, sump alarms or. sump pump out rate.
- Nondestructive examinations required by ASME Section XI have been performed on the SI System in accordance with the BV-1 In-Service Inspection Program.
Leakage examinations are performed on the SI System periodically as required by ASME Section XI. These' examinations were performed by DLC personnel certified as VT-2 examiners. A set of color coded isometrics has been prepared for each HAFA IIT test performed at Beaver Valley Unit 1. These isometrics : identify the following tests or examinations performed within the IIT test boundary according to color code: Color Descriotion Blue. HAFA IIT Test Green Nondestructive Examination Pink Leakage Examination ' Orange BVT Yellow OST These isometrics are provided in Enclosure I. Based on the above, the SI System has been determined to. be l . structurally sound and functionally operable. l l l l
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.. 1 SystSm Op3rability A200ccCOnt j for the Beaver Valley Unit 1 '
Containment Deoressurization System t {. I The 'following HAFA IIT tests were performed on the Beaver Valley Unit 1 (BV-1) Containment Depressurization (CD) System
- TEST NO. DESCRIPTION q 13.1 QUENCH SPRAY PUMP 1A SUBSYSTEM 13.2 QUENCH SPRAY PUMP 1B SUBSYSTEM 13.3 CHEMICAL INJECTION SUBSYSTEM 13.4 REFUELING WATER RECIRC PUMPS SUCTION 13.5 REFUELING WATER RECIRC PUMPS DISCHARGE 13.6 RECIRC SPRAY PUMP RS-P-2A SUCTION 13.7 RECIRC SPRAY PUMP RS-P-2B SUCTION L A Nuclear Engineering Department task force was established to review i all of the HAFA IIT testing performed at Beaver Valloy for compliance '
l to HAFA Topical Report 135 (P-A). Ten criteria were established as the requirements' for compliance to the Topical Report and are listed in Attachment IV. All of the HAFA IIT tests performed on the BV-1 CD-system were found to be in technical compliance with the requirements of. the Topical Report with the exception of criterion 3 which concerned personnel qualification, and criterion 7 which required the test results to be reviewed by ANSI N45.2.6 certified personnel. I significant deficiencies were found in the area of personnel qualification during the QA Audit (Vend-90-03) of HAFA International Inc. The results of-the QA Audit are listed.in Attachment II. Although- DLC considers all HAFA testing at Beaver Valley to be invalid, the CD System is considered to.have maintained structural ; integrity and is functionally operable based on the following l activities and surveillances:
-Almost the entire CD System is isolated during normal operation since the CD System would only operate during a design basis loss of coolant accident. The majority of the CD System with the exception of the piping to the containment spray headers is pressurized to system operating pressure during testing. l Normal plant tours by Operations personnel are performed on a l shift basis in all plant areas that the CD System is located with '
the exception of the Containment Building. Any major pressure boundary leakage would be detected during these tours. Relief valves installed in the CD System provide overpressurization prntection and are tested according to ASME Section XI where requi r ed. l 1
.- . .- __ ~ . . - .
I ATTACHMENT III, continu2d i containment'Depressurization System l
The CD System is a radioactive system, therefore, any major pressure boundary leakage would result in an increase in airborne radioactive activity ~which would be detected by various plant area radiation monitors.
- All- ASME Section XI pump and valve components in the CD System are tested in accordance with the BV-1 In-Service Testing Program. The In-Service Testing Program assures the operability of the CD System pumps and valves.
- Portions- of the CD System are pressurized to system pressure during Operational Surveillance Testing (OSTs). OSTs have specific acceptance criteria which must be met and are based on Technical Specification Surveillance requirements. The following OSTs test portions of the CD System on a quarterly frequency:
QEI TITLE 1.13.1 Quench Spray Pump (1QS-P-1A) Test 1.13.2 Quench Spray Pump (1QS-P-1B) Test. 1.13.10A Chemical Injection System Valve and Pump Operability Check - Train A 1.13.10B Chemical Injection System Valve and Pump operability Check - Train 1B The following OSTs and BVTs test portions of the CD System on a refueling outage frequency: l QSI TITLE I 1.13.7 Recirculation Pumps Auto Start and Flow Test 1.13.11 Quench Spray System operability Test BYT TITLE 1BVT 1.13.04 Recirculation Spray Heat Exchanger Leck Detection Test 1BVT 1.13.05 Inside Recirculation Spray Pump Test L Any CD System pressure boundary leakage would end up in either L the Primary Auxiliary Building, Safeguards Building, or Containment Sumps which would result in increased sump levels or sump pump out rate.
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. Nondestructive examinations required by ASME Section XI have been performed on the CD System in accordance with the BV-1 In-Service Inspection Program.
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4 i 2 ATTACHMENT-III, continusd Containment Depressurization System Leakage examinations are performed on the CD System periodically as required by ASME Section XI. These examinations- were perferrmed by DLC personnel certified as VT-2 examiners.
- A set of color coded isometrics has been prepared for each HAFA IIT test. performed at Beaver Valley Unit 1. These isometrics identify the following tests or examinations performed within the IIT test boundary according to color code:
Color Descriotion Blue HAFA-IIT Test ' Green Nondestructive Examination Pink Leakage Examination Orange BVT Yellow OST These isometrics are provided in Enclosure I. Based on the above, the CD System has been determined to be-structurally sound and functionally operable. , L l-1-
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Syctca Opartbility AOctocacnt l for the Beaver Valley Unit 1 Reactor Plant' Component Coolina Water System 1 The . following HAFA IIT tests were performed on the Beaver Valley Unit
- 1- (BV-1) . Reactor Plant Component Cooling Water (CCR) system:
TEST NO. DESCRIPTION 1 15.1 COMPONENT COOLING WATER MAIN HEADER 15.2 CRDM SHROUD COOLING COILS 15.3 LINES FROM CONTAINMENT AIR RECIRC COOLING n COILS l' 15.4 LINES TO CONTAINMENT AIR RECIRC COOLING ; l COILS l A Nuclear Engineering Department task force was established to. review all of the HAFA IIT testing performed at Beaver Valley for compliance E to HAFA Topical Report 135 (P-A). Ten criteria were established as the. requirements for compliance to the Topical Report and are listed in Attachment IV. All of the HAFA IIT tests performed on the BV-1 CCR System were found to be in technical compliance with the requirements of the Topical Report with the exception of criterion 3 which concerned personnel qualification, criterion 7 which requried
-test results to be reviewed by ANSI N45.2.6 certified personnel and '
also no statement of impracticality was made for the CCR System. Significant deficiencies were found in the area of personnel qualification during the QA Audit (Vend-90-03) of HAFA International
-Inc. The results of the QA Audit are listed in Attachment II.
Although DLC considers all HAFA testing at Beaver _ Valley to be invalid, the CCR System is considered to have maintained. structural integrity and is functionally operable based on the following activities and surveillances:
*~ Almost the entire CCR System is pressurized to normal system.
operating pressure during normal- system arrangement or during routine system evolutions. Portions of the CCR-System that are normally isolated would be pressurized when those portions of the system are placed into service.
- Normal plant tours by Operations personnel are performed on a shift basis in all plant areas that the CCR System is-located 1 with the exception of the containment Building. Any major l pressure boundary leakage could be detected during these tours.
Leakage is also detectable through monitoring and alarms of the CCR System Surge Tank Level.
- Relief valves installed in the CCR System provide l overpressurization protection and are tested according to ASME ;
Section XI where required. ! All ASME Section XI pump and valve components in the CCR System are tested in accordance with the BV-1 In-Service Testing Program. The In-Service Testing Program assures the operability of the CCR System pumps and valves. 1 1
ATTACHMENT III, continutd Reactor Plant Component Cooling Water System i l
- Portions of the CCR System are pressurized to system pressure l during . Operational Surveillance Testing (OSTs). OSTs have L
specific acceptance criteria which must be met and are based on L Technical Specification Surveillance requirements. The following-l OSTs test portions of the CCR System on a quarterly frequency: QSI TITLE 1.15.1 Reactor Plant Component Cooling Water Pump (1CCR-P-1A) Quarterly Test 1.15.2 Reactor Plant _ Component Cooling Water Pump (1CCR-P-1B) Quarterly Test 1.15.3 Reactor Plant Component Cooling Water Pump (1CCR-P-1C) Quarterly Test
- Any CCR pressure boundary leakage would end up in either the Primary Auxiliary Building, Safeguards Building or Containment Sumps which would result in increased sump levels or sump pump out rate.
Nondestructive examinations required by ASME Section XI have been performed on the CCR System in accordance with the BV-1 In-Service Inspection Program. Leakage examinations are performed on the CCR System periodically l as required by ASME Section XI. These examinations were performed-by DLC personnel certified as VT-2 examiners. A set of color coded isometrics has been prepared for each HAFA IIT test performed at Beaver Valley Unit 1. These. isometrics identify the following tests or examinations performed.within the IIT test boundary according to color code: Color. Descriotion Blue HAFA IIT Test Green Nondestructive Examination Pink Leakage Examination 3 Orange BVT ' Yellow OST These isometrics are provided in Enclosure I. 1
-Based on the above, the CCR System has been determined to be structurally sound and functionally operable.
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s i Syctem Oparability A3cssensnt for the Beaver Valley Unit 1 Gaseous Waste System l The following HAFA IIT tests were performed on the Beaver Valley Unit 1 (BV-1) Gaseous Waste (GW) System: P TEST NO. DESCRIPTION I V 1 L 19.1 GASEOUS WASTE DECAY TANK 1A 19.2 GASEOUS' WASTE DECAY TANK 1B 19.3 GASEOUS WASTE DECAY TANK 1C 1 A Nuclear Engineering Department task force was established.to review all of the HAFA IIT testing performed at Beaver Valley for compliance to HAFA Topical Report 135 (P-A). Ten criteria.were established as the requirements for compliance to the Topical Report and are listed in Attachment IV. All of the HAFA IIT tests performed on the BV-1 GW System were found to be in technical compliance with the requirements of the' Topical Report with the exception of criterion 3 which concerned personnel qualification, and criteria 7 which required test results to be reviewed by ANSI N45.2.6. certified personnel. Significant deficiencies were found in the area of personnel qualification during the QA Audit (Vend-90-03) ~ of HAFA International Inc. The results of the QA Audit are listed in Attachment II. Although, DLC considers all HAFA testing at Beaver Valley to be- t invalid, the GW System is considered to have maintained structural integrity and is functionally operable -based on the following activities and surveillances. *
- Almost the entire GW System is pressurized to normal. system operating pressure during normal system arrangement or during routine system evolutions. Portions of the GW System that are normally isolated would be pressurized when those portions of the system are placed into service.
Relief valves installed in the GW System provide
-overpressurization protection.
The GW System is a radioactive system, therefore any major pressure boundary leakage would result in a increase in airborne radioactive activity which would be detected by various plant area radiation monitors. Leakage from the GW System is readily detectable through surveillance checks on the associated tank pressure indicators and radiation monitors.
- The above IIT testing performed on the GW System was performed for information only since the GW System was not part of the First Interval ASME Section XI Ten Year Plan.
- A set of color coded isometrics has been prepared for each HAFA IIT test performed at Beaver Valley Unit 1. These isometrics identify the following tests or examinations performed within the IIT test boundary according to color code:
' ATTACHMENT III,.continurd Gaseous-WasteLSystem Color Descriotion i
Blue- HAFA IIT Test [ Green Nondestructive Examination Pink- Leakage Examination-Orange BVT r Yellow OST These isometrics are provided in Enclosure I. ' Based on the above, the GW System has been determined to be structurally sound and' functionally operable. ; i.
Systcm Oparability AccocenOnt j for the-Beaver Valley Unit 1 ) Main Steam SysttB l The following HAFA IIT and Acoustic Emission (AE) tests were i performed on the-Beaver Valley Unit 1 (BV-1) Main Steam (MS) System: TEST NO. DESCRIPTION j 21.1.1 FW-P-2 STEAM SUPPLY LINES 21.1.2 AE LEAK DETECTION ON MAIN STEAM PIPING 21.1.3 AE LEAK DETECTION ON STEAM GENERATOR I RC-E-1A 21.1.4 AE LEAK DETECTION ON STEAM GENERATOR' RC-E-1B ' 21.1.5 AE LEAK DETECTION ON STEAM GENERATOR RC-E-1C A Nuclear Engineering Department task force was established to review l all of the HAFA IIT testing performed at Beaver Valley for compliance to 'HAFA Topical Report 135 (P-A). Ten criteria were established as the requirements for compliance to the Topical Report and are listed-in Attachment IV. All of the HAFA IIT tests performed on the BV-1 MS System were found to be in technical compliance with the requirements-of the Topical Report with the exception of criterion 3 which concerned personnel qualification, and criterion 7 which required test results.to be reviewed by ANSI N45.2.6 certified personnel. The acoustic emission only testing (tests 21.1.2, 21.1.3, 21.1.4 and 21.1.5) was performed in accordance with DLC to NRC letter dated January 15, 1988 and approved by NRC letter dated February.29, 1988. Significant deficiencies were _found in the area of personnel qualification during the QA Audit (Vend-90-03) of.HAFA International Inc. The results of the QA Audit are listed in Attachment II. Although- DLC considers all HAFA testing at Beaver Valley to be invalid, the MS System is considered to have maintained structural
~ integrity .and is functionally operable based on ~ the following activities and surveillances:
- Almost the entire MS System is pressurized to normal system operating pressure during normal system operation and heatup and cooldown evolutions. Portions of the MS System that are normally isolated would be pressurized when those portions of the system are placed into service.
- Normal. plant tours by Operations personnel are performed on a shift basis in all plant areas that the MS System is located with the exception of the containment Building. Any major pressure i boundary leakage would be detected during these tours.
Relief valves installed in the MS System provide overpressurization protection and are tested according to ASME L Section XI where required.
( 4 ATTACHMENT III, continutd Main Steam System l l l a- All ASME Section XI valve components in the MS System are tested l in accordance with the BV-1 In-Service Testing Program. The i In-Service Testing Program assures the operability- of the MS I System valves. ) A loss of structural integrity of the MS System would result in one or more of the following alarms:
- a. Low Steam Pressure / Rate which is monitored continuously i
- b. Low Steam generator Level also monitored continuously
- c. Containment Alarms for Pressure, Temperature, and Humidity, if the breach were in containment.
- d. Local heat actuating device actuation if the breach is in the Main Steam Valve Room.
- Nondestructive examinations required by ASME Section XI-have been performed on the MS System in accordance with the BV-1 In-Service Inspection Program.
- Leakage examinations are performed on the MS System periodically as required by ASME Section XI. These examinations were performed by DLC personnel certified as VT-2 examiners.
- A set of color coded isometrics has been prepared for each HAFA IIT test performed at Beaver Valley Unit 1. These isometrics identify the following tests or examinations performed within the IIT-test boundary according to color code:
-Color Descriotion Blue HAFA IIT Test Green Nondestructive Examination Pink Leakage Examination Orange BVT Yellow OST These isometrics are provided in Enclosure I.
Based on the above, the MS System has been determined to be structurally sound and functionally operable. I
3 Syct03 Opercbility A00000nOnt for the Beaver Valley Unit 1 Feed Water System The following HAFA- IIT and Acoustic Emission (AE) tests were performed - on the Beaver Valley Unit 1 - (BV-1) . Feed Water (FW) System: ,
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TEST NO. DESCRIPTION 24.1.1 AUX FD PUMP SUCTION LINE [FW-P-2) 24.1.2 AUX FD PUMP SUCTION LINE FROM RW (FW-P-2) 24.2.1 AUX FD PUMP 3A SUCTION LINE 24.2.2 AUX FD PUMP 3A SUCTION LINE FROM RW 24.3.1 AUX FD PUMP 3B SUCTION LINE 24.3.2 AUX FD PUMP 3B SUCTION LINE FROM RW < 24.4 AUX FD PUMPS SUCTION FROM RW SYSTEM 24.5 AUX FD PUMP 2 RECIRC LINE 24.6 AUX FD PUMP 3A RECIRC LINE 24.7 AUX FD PUMP 3B RECIRC LINE 24.9 AUX FD PUMPS DISCH- TO LAST VALVE BEFORE S/G's 24.10 AE LEAK DETECTION ON MAIN FEEDWATER PIPING 24.11 A AND C FW TRAIN PIPING A Nuclear Engineering Department task force was established to review all of the HAFA IIT testing performed at Beaver Valley for compliance to HAFA Topical Report 135 (P-A). Ten criteria were established as the requirements for compliance to the Topical Report and are listed in Attachment IV. All of the HAFA IIT tests performed on the BV-1 FW System' were found to be in technical compliance with the requirements of the Topical Report with the exception of criterion 3 which concerned personnel qualification, and criterion 7 which required test results to be reviewed by ANSI N45.2.6 certified personnel. The 1
-acoustic. emission only testing (tests 24.10 & 24.11) was performed in j accordance with DLC-to NRC letter dated January 15, 1988 as approved by NRC letter dated February 29, 1988.
Significant deficiencies were found in the area of personnel qualification during the QA Audit (Vend-90-03) of HAFA International Inc. The results of the QA Audit are listed in Attachment II. l Although DLC considers all HAFA testing at Beaver Valley to be invalid, the FW System is considered to have maintained structural integrity and is functionally operable based on the following activities and surveillances: Almost the entire normal FW System is pressurized to normal l system operating pressure during normal system arrangement or during routine system evolutions. The auxiliary Feed Water portions of the FW System that are normally isolated would be pressurized when those portions of the system are tested.
. Normal plant tours by Operations personnel are performed on a shift basis in all plant areas where the majority of the auxiliary FW System is located. Any major pressure boundary leakage would be detected during these tours. .
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ATTACNMENT III, continuOd Feed Water System All ASME Section XI pump and valve components in the FW System are tested in accordance with the BV-1 In-Service Testing Program. The In-Service Testing Program assures the operability of the FW System pumps and valves.
- Portions of the auxiliary FW System are pressurized to system pressure during operational Surveillance Tenting (OSTs). OSTs have specific acceptance criteria which must be met and are based on Technical Specification Surveillanco requirements. The following OSTs test portions of the FW System on a quarterly frequency:
QSI TITLE 1.24.2 Motor-Driven Auxiliary Feed Pump Test (1FW-P-3A) 1.24.3 Motor-Driven Auxiliary Feed Pump Test (1FW-P-3B) 1.24.4 Steam Turbine-Driven Auxiliary Feed Pump Test (1FW-P-2) 1.24.7 Dedicated Auxiliary feed Pump (1FW-P-4) Test The following OSTs test portions of the FW System on a refueling outage frequency: QsI TITLE 1.24.4 Auxiliary Feed Pump Auto Start Test
- 1. 2 4 . t', Motor-Driven Auxiliary Feed Pumps Check Valves and Flow Test 1.24.9 Turbine-Driven AFW Pump (1FW-P-2)
Operability Test Any FW System pressure boundary leakage would and up in either the Turbine Building, Service Building or Containment Sumps which would reuuit in increased sump levels or sump pump out rate.
- Nondestructive examinations required by ASME Section XI have been performed on the FW System in accordance with the BV-1 In-Service Inspection Program.
Leakage examinations are performed on the FW System periodically as required by ASME Section XI. These examinations were performed by DLC personnel certified as VT-2 examiners.
ATTACHMENT III, c ntinu:d l -Feed Water System l' l -
- A set of color coded isometrics has been prepared for each HAFA l IIT test performed at Beaver Valley Unit 1. These isometrics l identify the following tests or examinations performed within the l IIT test boundary according to color codet 1
color Descriotion Blue RAFA IIT Test I Green Hondestructive Examination l Pink Leakage Examination l orange BVT Yellow OST 1 1 These isometrics are provided in Enclosure I. Based on the above, the FW System has been determined to be structurally sound and functionally operable. l l l l l l . r
1 Sycten Opercbility Acc00 0:nt for the Beaver Valley Unit 1 Steam Generator Blowdown System i 4 The following HAFA IIT and Acoustic Emission (AE) tests were ' performed on the Beaver Valley Unit 1 (BV-1) Steam Generator Blowdown (BD) systems , i TEST NO. DESCRIPTION 25.1.1 AE LEAK DETECTION ON STEAM GEN. BLOWDOWN PIPING , 25.2.1 S/G [RC-E-1A) BLOWDOWN PIPING l 25.2.2 S/G [RC-E-1B) BLOWDOWN PIPING 25.2.3 S/G (RC-E-lC) BLOWDOWN PIPING , A Nuclear Engineering Department task force was established to review all of the RAFA IIT testing performed at Beaver Valley for compliance to HAFA Topical Report 135 (P-A). Ten criteria were established as the requirements for compliance to the Topical Report and are listed . in Attachment IV. All of the RAFA IIT tests performed on the BV-1 BD ; System were found to be in technical compliance with the requirements of the Topical Report with the exception of criterion 3 which . concerned personnel qualification, and criterion 7 which required test results to be reviewed by ANSI N45.2.6 certified personnel. The acoustic emission only testing (test 25.1.1) was performed in ; accordance with DLC to NRC letter dated January 15, 1988 as approved . by NRC letter dated February 29, 1988. l Significant deficiencies were found in the area of personnel qualification during the QA Audit (Vend-90-03)-of HAFA International Inc. The results of the QA Audit are listed in Attachment II. Although DLC considers all HAFA testing at Beaver Valley to be invalid, the BD System is considered to have maintained structural l integrity and is functionally operable based on the following ' activities and surveillances: l
- Almost the entire BD System is pressurized to normal system l operating pressure during normal system arrangement or during routine system evolutions. Portions of the BD System that are normally isolated would be pressurized when those portions of the system are placed into service.
- Normal plant tours by Operations personnel are performed on a shift basis in all plant areas that the BD System is located with the exception of the containment Building. Any major pressure boundary leakage would be detected during these tours.
- All ASME Section XI valve components in the BD System are tested in accordance with the BV-1 In-Service Testing Program. The In-Service Testing Program assures the operability of the BD System valves.
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l ATTACHMENT III, continu:d i Steam Generator Blowdown System t
. Leakage from the BD System piping-located inside containment is readily detectable through surveillance of containment temperature, sump pump out rate and various other instruments used for early detection of a high energy line leak. The pressure of this piping during power operation is also 200 psi lower than when the plant is in hot standby conditions (Mode 3).
Therefore, the integrity of the blowdown piping has been demonstrated through In-Service pressurization of the blowdown piping during the normal plant heat up evolution.
- Leakage examinations are performed on the BD System periodically as required by ASME Section XI. These examinations were performed by DLC personnel certified as VT-2 examiners.
- A set of color coded isometrics has been prepared for each HAFA IIT test performed at Beaver Valley Unit 1. These isometrics identify the following tests or examinations performed within the IIT test boundary according to color code:
Color Descriotion Blue HAFA IIT Test Green Nondestructiva Examination Pink Leakage Examination Orange BVT Yellow OUT l , These isometrics are provided in Enclosure I. Based on the above, the BD System has been determined to be structurally sound and functionally operable.
Syctem Opercbility A0;Occuent for the Beaver Valley Unit 1 : River Water System The following HAFA IIT tests were performed on the Beaver valley Unit 1 (BV-1) River Water (RW) System TEST NO. DESCRIPTION 30.1 "B" RW HEADER 30.2 "A" RW HEADER 30.4 BACKFLOW THROUGH CHECK VALVE (1RW-106) ! 30.5 BACKFLOW THROUGH CHECK VALVE (1RW-107) 30.6 CHARGING PP COOLER CH-E-7A RW LINE 30.7 CHARGING PP COOLER CH-E-7B RW LINE , 30.8 CHARGING PP COOLER CH-E-7C RW LINE 30.9 RW LINES DISCH OF CH PP COOLERS & CR A/C COND. 30.10 "A" HEADER SUPPLY TO CHARGING PUMP COOLERS 30.11 "B" HEADER SUPPLY TO CHARGING PUMP COOLERS 30.15 RW PUMP 1A RECIRC LINE 30.16 RW PUMP 1B RECIRC LINE 30.17 RW PUMP 1C RECIRC LINE 30.18 RW SUPPLY TO CCR HX CC-E-1A 30.19 RW SUPPLY TO CCR HX CC-E-1C < 30.20 RW SUPPLY TO CCR HX CC-E-1B 4 A Nuclear Engineering Department task force was established to review all of the HAFA IIT testing performed at Beaver Valley for compliance to HAFA Topical Report 135 (P-A). Ten criteria were established as the requirements for compliance to the Topical Report and are listed ' in Attachment IV. All of the HAFA IIT tests performed on the BV-1 RW System were found to be in technical compliance with the requirements of the Topical Report with the exception of criterion 3 which concerned personnel qualification, and criterion 7 which required test results to be reviewed by ANSI N45.2.6 certified personnel. Significant deficiencies were found in the area of personnel qualification during the QA Audit (Vend-90-03) of HAFA International Inc. The results of the QA Audit are listed in Attachment II. Although DLC considers all HAFA testing at Beaver Valley to be invalid, the RW System is considered to have maintained structural integrity and is functionally operable based on the following activities and surveillances:
- The majority of the RW System is pressurized to normal system operating pressure during normal system arrangement or during routine system evolutions. Portions of the RW System that are normally isolated would be pressurized when those portions of the system are placed into service. j Normal plant tours by Operations personnel are performed on a shift basis in all plant areas that the RW System is located with the exception of the Containment Building. Any major pressure boundary leakage would be detected during these tours.
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ATTACHMENT III, etntinu d River Water System
. Relief valves installed in the RW System provide I overprensurization protection and are tested according to ASME l Section XI where required. !
- All ASME Section XI pump and valve components in the RW System are tested in accordance with the BV-1 In-Service Testing Program. The In-Service Testing Program assures the operability of the RW System pumps and valves.
- Portions of the RW System are pressurized to system pressure during Operational Surveillance Testing (OSTs). OSTs have specific &cceptance criteria which must be met and are based on Technical Specification surveillance requirements. The following OSTs test portions of the RW System on a quarterly frequency:
QST TITLE 1.30.2 Reactor Plant River Water Pump 1A Test 1.30.3 Reactor Plant River Water Pump 1B Test 1.30.6 Reactor Plant River Water Pump 1C Test The following OSTs tests portions of the RW System on a refueling outage frequency: QST TITLE 1.30.8 Auxiliary River Water System Test l 1.30.12 Recirculation Spray Heat Exchanger Flow Test
- Nondestructive examinations required by ASME Section XI have been performed on the RW System in accordance with the BV-1 In-Service Inspection Program.
- Leakage examinations are performed on the RW System periodically as required by ASME Section XI. These examinations were performed by DLC personnel certified as VT-2 examiners.
- A set of color coded isometrics has been prepared for each HAFA IIT test performed at Beaver Valley Unit 1. These isometrics identify the following tests or examinations performed within the IIT test boundary according to color code:
Color Aggspiotion Blue RAFA IIT Test Green Nondestructive Examination Pink Leakage Examination Orange BVT Yellow OST
. ? .e: i ATTACHMENT III, c ntinutd River Water. System These isometrics are provided in Enclosure I. ;
Based on the above, the RW System has been determined to be structurally sound and functionally operable. t l'
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A_ ATTACHMENT IV criteria for Technical Review of MAFA Testina
- 1. A statement of impracticality must be made for the system or portion of the system to be tested.
- 2. The NRC must be notified and concur with the statement of impracticality.
- 3. All personnel utilizing the IIT equipment must be certified in accordance with ANSI N45.2.6 and MAFA procedure 9.2.
This certification must be by written examination.
- 4. All IIT tests are to be performed at normal operating pressures.
- 5. All IIT tests are subject to a 2 hour hold time at operating pressure prior to the VT-2 walk down.
- 6. All procedures must be reviewed and approved by the Onsite Safety Committee (OSC).
- 7. The IIT test procedure results must be reviewed and accepted by ANSI N45.2.6 certified personnel.
- 8. All IIT tests must include a VT-2 walk-down using ASME Section XI, IWA-2300, certified personnel to verify no or
. quantify any through wall leakage within the test L boundaries.
- 9. The instrumentation used must be by one or more of the
! following models or a statement / evaluation of equivalency provided: l A. Multi-Media Leak Testing _ Device (KMLTD) capable of 400 ; psig, with a range of measurement of 0.0001 to 0.06 gpm l 10.2% l B. Leak Measuring Devices (LMDs) , Model 10 with a range of 0.1 - 10.0 gpm 10.05% l Model 20 with a range of 0.03 - 60.0 gpm 10.05% Model 30 with a range of 0.03 - 3.0 gpm i0.05% C. AE Sensor Model 5120 ; NOTE: All calibration of flow meters and sensors must be traceable to the National Bureau of Standards. i
- 10. The test configuration must have an inlet LMD, and a l
selected set of the boundary valves are to be instrumented with LMDs and/or AE sensors for the purpose of identifying the locations of unaccounted for leakage coupled with a VT-2 inspection verifying and quantifying any external leakage.
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I I IS i I t DUQUESNE LIGHT COMPANY \ Beaver Valley Power Station PotentiallyInvalid Leak Detection Tests Used as an Alternative for l AMSE Section XI Hydrostatic Tests , I :
"O Letter dated May 3,1990 .
L \ Enclosure I : f
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