ML060120418
| ML060120418 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/21/2005 |
| From: | Kowal G Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-5963 EC-053-1012 | |
| Download: ML060120418 (138) | |
Text
PCAF 42004-1318 Page 4 of 4 NUCLEAR ENGINEERING CALCULATION COVER SHEET NEPM-OA-0221-1
- 1. Page t of 138 Total Pages 138 1'-2. TYPE:
CALC
>3. NUMBER:
EC-053-1012
>4. REVISION:
- >5. UNIT o
- >6. QUALITY CLASS:
0
>7. DESCRIPTION:
Assessment of SBLC System for Suppression Pool pH Control 0
- 8. SUPERSEDED BY:
- 9. Alternate Number:
NA
- 10. Cycle:
NA 1l. Computer Code/Model used:
NA
- 12. Discipline: M
>13. Are any results of this calculation described in the Licensing Documents?
o Yes, Refer to NDAP-QA-0730 and NDAP-QA-0731 0 No
>14. Is this calculation changing any method of evaluation described in the FSAR and using the results to support or change the FSAR? (Refer to PPL Resource Manual for Definition of FSAR}
o Yes, 50.59 screen or evaluation required.
E No
>15. Is this calculation Prepared by an External Organization?
O Yes 0 No EG771 Qualifications may not be required for individuals from extem rganizations (see Section 7.4.3).
_!r-9 I
I> 18. Prepared by:
George M. Kowal
-
9Qzi
.>17. Reviewed by:
>18. Verified by:
>19. Approved by:
>20. Accepted by:
r ae Print Name(EG771 Qualification Requird)7 ture Date Ronald A. Vaqubes g
/
0t~
Pinnt NsrmeEG771 Oualification Requlrf)f Dave G. Kostelnik 4
t
//
Print Name(Qualified per NEPM-OA-0241 and Signature Date comply with Se~cton 7.8 oftNEPM-a4-0221)
Print Name(EG771 Oualification Required) and comply with Section 7.9of NEPM-OA-0221 Signature Date ADD A NEW COVER PAGE FOR EACH REVISION FORM NEP-OA-0221-1, Revision 8. Page I of 1, ELECTRONIC FORM I
- Verified Fieds
> REQUIRED FIELDS V
PP&L CALCULATION SHEET PROJECT Calc. No.
E-453-13012 Assessment of SBLC Rev. No.
Designed By G Kawal System for Suppression Checked By Pool pH Control Sh. No.
2-of 138-TABLE OF CONATENTS Page No.
TABLE OF CONTENTS..................................................
2 1.0 OBJECTIVE..................................................
4 1.1 Background..................................................
4 1.2 Statement of Problem..................................................
4 1.3 System Overview..................................................
5 1.4 Quality Guidance in Support of AST................................
5 1.5 Reliability Requirements in Support of AST..................................................
6
2.0 CONCLUSION
S & RECOMMENDATIONS.................................................
8 0 0 ASSUMPTIONS/DESIGN INPUTS.................................................
8 4.0 METHODOLOGY..................................................
8 4.1 Quality Guidance of the SBLC System in Support of 10 CFR 50.67...................... 8 4.2 Reliability Requirements in Support of AST.................................................
15 4.3 All Active and Passive Components of the SBLC System.................................... 35 4.4 Critical Components Subject to Single Failure Criteria....
....................................... 35 4.5 Justification for Low Risk Failure Probability.
................................................ 38 4.5.1 CHECK VALVE - 1 (2)48F007....................
3.6..........
38 4.5.2 SBLC MANUAL INITIATION SWITCH, HS1(2)4804............................................. 39 4.5.3 STANDBY LIQUID CONTROL INJ ISO VALVE -1 (2)48F008; SBLC.................. 41 OB INJECTION VALVE HV1 (2)F006 4.5.4 SBLC STORAGE TANK ELECTRIC HEATERS A, B - 1(2)E219, 1(2)E220......... 42 4.5.4.1 Constant Heat Transfer Coefficient Analysis......................................................
47 5.0 RESULTS.......................................................
49
6.0 REFERENCES
50 TTACHMENTS Attachment No. 1 SBLC UNIT 1 AND UNIT2 COMPONENT LIST (8 Pages) 52 VTTAGHMENTS
PP&L CALCULATION SHEET PROJECT Calc. No.
E C05-14012 Assessment of SBLC Rev. No.
Designed By G Kowal System for Suppression Checked By Pool pH Control Sh. No.
o Of 138-Attachment No. 2 Attachment No. 3 Attachment No. 4 Attachment No. 5 EPIX, NPRDS VALVE DATA (44 Pages)
Susquehanna - Valve Operating Experience (14 Pages)
Input Data - Drawings (18 Pages)
EXCEL Sreadsheet Results (3 Pages) 60 104 118 136 V
PP&L CALCULATION SHEET Dept.
PROJECT CaIc. No.
E (053-1012 Date Assessment of SBLC Rev. No.
Designed By G Kowal System for Suppression Checked By Pool pH Control Sh. No.
4-of 138-1.0 OBJECTIVE
1.1 Background
With the eventual implementation of the Alternative Source Term (AST), 10 CFR 50.67, the Standby Liquid Control (SBLC) System is being considered for preventing re-evolution of iodine from the suppression pool in the event of a Design Basis Accident (DBA-LOCA). Specifically, NRC Regulatory Guide 1.183 states that the radiological consequence analysis should consider iodine re-evolution if the suppression pool liquid pH is not maintained greater than 7.
Maintaining the suppression pool liquid pH greater than 7.0 can be accomplished by the buffering action of boron released to the suppression pool from the SBLC System (see calculation EC-059-1041).
1.2 Statement of Problem It is proposed to inject boron to the suppression pool via the SBLC System to maintain basic pH in the suppression pool in order to minimize re-evolution of iodine from the suppression pool in the event of a Loss of Coolant Accident (LOCA). However, the system fails to meet all the requirements of a safety-related system in that SBLC is not designed for the single active component failure criteria. Therefore, a failure of a critical component would prevent the system from controlling suppression pool liquid pH by using the buffering action of boron injected to the suppression pool from the SBLC system (via the reactor vessel). The success of the SBLC system is necessary in order to take credit for this pH control function and prevention of iodine re-evolution. The NRC has provided review guidelines for the SBLC system that do not meet single failure criteria or that are not of the expected quality (safety related). This calculation will specifically demonstrate compliance with the requirements identified in the NRC review guideline document.
The evaluation will be accomplished in four steps, as follows:
a)
Provide overall assurance the SBLC System meets the quality guidelines (a)-(e) regarding the reliability, redundancy presented in Sections 1.4 and 1.5 below.
b)
Identify all active and passive components of the SBLC System under consideration.
U
PP&L CALCULATION SHEET Dept.
PROJECT Cal:. No.
EC-D53-1 012 Date Assessment of SBLC Rev. No.
Designed Byy G Kowal System for Suppression Checked By Pool pH Control Sh. No.
i of 138-c)
Screen for (and identify) critical components subject to single failure criteria. (Details are discussed starting in Section 4.3) d)
Substantiate a low risk failure probability for the identified components.
1.3 System Overview The SBLC System is an independent and diverse backup system to the Control Rod Drive (CRD) System. SBLC shuts down the reactor by injecting a neutron absorbing solution into the reactor coolant, which is circulated through the core.
The neutron absorber used in SBLC is an aqueous solution of sodium pentaborate decahydrate, Na2B13O 1
- 10H20. Sufficient solution is injected to bring the reactor from maximum rated power conditions to cold subcritical over the entire reactor temperature range, from maximum operating to cold shutdown conditions. SBLC is not required to scram the reactor, or to serve as a backup scram system. There is no requirement for SBLC to be capable of operation when the reactor is shut down by the CRD System.
The SBLC System is listed as a Nuclear Steam Supply System. Based on Regulatory Guide 1.70, the SBLC is identified as a safe shutdown system having a safety-related classification. Safety-related systems provide the actions necessary to assure safe shutdown of the reactor, to protect the integrity of radioactive material barriers, and/or to prevent the release of radioactive material in excess of allowable dose limits. Safe shutdown of the reactor is classified as a nuclear safety function, and thus, the SBLC is classified as having a safety-related function.
The SBLC System consists of two 100% capacity positive displacement triplex type (3-piston) injection pumps which when operating together are capable of delivering sodium pentaborate to the reactor vessel to meet 10CFR50.62 requirements, two 100% capacity explosive actuated injection valves, one storage tank, one test tank, and the piping, valves, instrumentation and controls necessary to inject the solution into the reactor and to test the SBLCS. All equipment in the SBLCS which comes in contact with the neutron absorbing solution is stainless steel for corrosion protection.
1.4 Quality Guidance In Supeort of AST To demonstrate that the SBLC System is able to perform its AST (10 CFR 50.67) function (injection of sodium pentaborate into the suppression pool), the System Ask should satisfy, as a minimum, the recommended guidelines listed below (NRC W
PP&L CALCULATION SHEET Dept.
PROJECT Calc. No.
EC-05'3-1012 Date Assessment of SBLC Rev. No.
Designed By.; Kowal System for Suppression Checked By Pool pH Control Sh. No.
i-of 138-review guidelines). Meeting these criteria, demonstrates reasonable assurance of the quality of the SSES SBLC System. These guidelines are as follows:
a) The SLC system should be provided with standby AC power supplemented by the emergency diesel generators.
b) The SLC system should be seismically qualified in accordance with Regulatory Guide 1.29 and Appendix A to 10 CFR Part 1 00.
c) The SLC system should be incorporated into the plant's ASME Code ISI and IST Programs based upon the plant's code of record (10 CFR 50.55a).
d) The SLC system should be incorporated into the plant's Maintenance Rule program consistent with 10 CFR 50.65.
e) The SLC system should meet 10 CFR 50.49 and Appendix A (GDC 4) to 10CFR 50.
Therefore, meeting the intent of these guidelines should provide reasonable assurance of the System's ability to support the pH controlling function. Each specific guideline, as it impacts and is supported by the SSES SBLC System, is addressed in detail in Section 4.1 of this evaluation.
1.5 Reliability Requirements in Sunnort of AST In addition to meeting the quality requirements of the NRC review guidelines, the SBLC system must also meet reliability requirements. The following criteria are provided in the NRC review guidelines if the SBLC system can not perform its AST function due to a single failure of an active component.
Acceptable quality and reliability of the non-redundant active components and/or compensatory actions in the event of failure of the non-redundant active components.
Under this approach, the licensee should provide the following information in justifying the lack of redundancy of active components in the SLC system:
(a) The licensee should identify the non-redundant active components in the SLC system and provide their make, manufacturer and model number. The staff
PP&L CALCULATION SHEET Dept.
PROJECT Catc. No.
EC-053--012 Date Assessment of SBLC Rev. No.
Designed By.r KowaL System for Suppression Checked By Pool pH Control Sh. No.
7 of 138-reviewer will compare this information with performance data for the component from industry data bases and other sources.
(b) The licensee should provide the design-basis conditions for the component and the environmental and seismic conditions under which the component may be required to operate during a design basis event. Environmental conditions include design basis pressure, temperature, relative humidity and radiation fields.
The staff reviewer will compare the environmental conditions associated with the design basis accident to conditions for which the component was designed to determine whether the component is capable of performing its intended function.
(c) The licensee should indicate whether the component was purchased in accordance with Appendix B to 10 CFR Part 50. If the component was not purchased in accordance with Appendix B, the licensee should provide information on the quality standards under which it was purchased. For the latter situation, information in the component would be reviewed by the appropriate technical review branch responsible for the component, as requested by the lead SPSB reviewer.
(d) The licensee should provide the performance history of the component both at the licensee's facility and in industry databases such as EPIX and NPRDS.
The staff reviewer will use this information to evaluate the reliability of the component relative to other components used in safety-related applications.
(e) The licensee should provide a description if its inspection and testing program including standards, frequency and acceptance criteria. The staff reviewer will use this information to evaluate the licensee's activities to monitor the component's performance at the facility. The information on the component would be reviewed by the appropriate technical review branch responsible for the component, as requested by the lead SPSB reviewer.
(f) The licensee should also indicate the potential compensating actions that could be taken within an acceptable time period to address the failure of the component. An example of a compensating action might be the ability to jumper a switch in the control room to overcome its failure. The staff reviewer will consider the availability of compensating actions and the likelihood of successful injection of the sodium pentaborate where non-redundant active components fail to perform their intended functions.
Each Reliability Requirement, as it impacts and is supported by the SSES SBLC System, is addressed in detail in Section 4.2 of this evaluation.
IF System, is addressed in detail in Section 4.2 of this evaluation.
PP&L CALCULATION SHEET Dept PROJECT Calc. No.
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Date Assessment of SBLC Rev. No.
Designed By nG Kowal System for Suppression Checked By Pool pH Control Sh. No.
98-of 138-
2.0 CONCLUSION
S & RECOMMENDATIONS The results of this calculation show that the use of the SBLC System for preventing re-evolution of iodine from the suppression pool in the event of a Design Basis Accident (DBA-LOCA) meets all of the NRC Guidelines for that application.
3.0 ASSUMPTIONSIDESIGN INPUTS The following general input data was used in this evaluation:
3.1 SBLC System component data was obtained from References 6.2 through 6.16.
3.2 Performance history of critical components was obtained from References 6.16 through 6.18.
3.3 Other input data as referenced in the respective section(s), or when used.
4.0 METHODOLOGY By means of the approach presented in Section 1.2, the details of substantiation of using the SBLC System for this application follow.
4.1 Quality Guidance of the SBLC System in Support of 10 CFR 50.67:
As suggested by the "Guidance on the Assessment of a BWR SLC System for pH Contror, guideline items (a) through (e) present details of demonstrating reasonable assurance regarding the quality of the SSES SBLC System. These are presented in the same order as listed in Section 1.4 above.
a)
The SLC system should be orovided with standby AC power supplemented by the emeraencv diesel generators.
The SBLC pumps, storage tank heaters and instrumentation and controls are powered from or connectable to the standby AC power supply. The pump, W
powered from or connectable to the standby AC power supply. The pump,
PP&L CALCULATION SHEET Dept PROJET Calc. No.
EC-053-1012
- _D_
Assessment of SBLC Rev. No.
Designed By-GJ KoWmI System for Suppression Checked ByBPool pH Control Sh. No.
S-N of 138.-
explosive actuated valve, and instrumentation and controls for loop 'A" are powered from load group 1C and those components in loop "B" are powered from load group 1A. All components in the SBLC System are connected to Division I power, but the use of two load groups per electrical division provides for electrical separation for the SBLC System.
Reference 6.24 (Drawing E-166, Sheets 1, 2, 5, and 6) show that each SBLC pump and associated equipment is powered from an independent 4.16 kV bus through the preferred AC electrical power to all Class 1 E loads. This is shown on Single Line Diagram for the station, Reference 6.8 (E-1, Sheet 1). It shows that the normal power supply for Division I, Channel A and Division I, Channel C is from Engineered Safeguard Transformer 101 (OX201). However, Division I can also be fed by Engineered Safeguard Transformer 103 (OX203). In the event of total loss of offsite power sources, onsite Independent diesel generators provide the standby safety features loads.
The A pump, 1 (2)P208A, (along with power to open squib valve 1 (2)48-FO04A, and control power for the A instrumentation and controls) is from Division l, Channel C, MCC 1(2)B236, which can be supplied from the C Diesel, if offsite power is unavailable.
The B pump, 1 (2)P208B (along with power to open squib valve 248-FO04B and control power for the B instrumentation and controls) is from Division I, Channel A, MCC 1 (2)B217, which can be supplied from the A Diesel if offsite power is unavailable. The power to open the squib valve 148-FO04B, is from 1 B216.
Valves HV-1 (2)48-F006 are powered from 1 E 480V, MCC 1 (2)B236 Both of the SLC storage tank heaters (heater A - 1(2)E219, and heater B -
1(2)E220) are powered from 1 E 480V, MCC 1 (2)B236.
b)
The SLC system should be seismically auallf led in accordance with Regulatory Guide 1.29 and A~pendix A to 10 CFR Part 100.
Mechanical Components:
The SBLC System is designed to meet the intent of Regulatory Guide 1.29,
'Seismic Design Classificationu, Revision 2, 2/76 General Design Criterion 2, Design Basis for Protection Against Natural Phenomena" (GDC 2), requires that structures, systems, and components W
Phenomena" (GDC 2), requires that structures, systems, and components
PP&L CALCULATION SHEET Dept.
PROJECT Calc. No.
E -053-1012 DatA Assessment of SBLC Rev. No.
Designed By G Kowal System for Suppression Checked By Pool pH Control Sh. No.
10-of 138-important to safety be designed to withstand the effects of natural phenomena such as earthquakes without loss of capability to perform their safety functions.
The guidance in Regulatory Guide 1.29 provides an acceptable method of determining seismic classification and applicability. Because the SBLC System forms part of the RCPB, and can be used for reactor shutdown, it is classified by Regulatory Guide 1.29 as Seismic Category I. The NRC Safety Evaluation Report, NUREG-0776 Section 9.3.2, lists compliance with Regulatory Guide 1.29 as one of the reasons that the SBLC design is acceptable.
SBLC System Seismic Category I structures and components are analyzed under the loading conditions of the SSE and OBE. Since the two earthquakes vary in intensity, the design of Seismic Category I structures, components, and equipment to resist each earthquake and other loads are based on levels of material stress or load factors, whichever is applicable. Piping and equipment, including support structures, are designed to Seismic Class I earthquake requirements. FSAR Table 3.2-1 contains a detailed breakdown of the SBLC System and the seismic classification.
Electrical Equipment and Instrumentation:
The SBLC Seismic Category 1 electrical and instrumentation and control equipment is designed to meet the intent of IEEE Standard 344-1971, "IEEE Recommended Practices for Seismic Qualification of Class 1 E Equipment for Nuclear Power Generating Stations". (FSAR Section 3.1Oa.2).
All SBLC electrical and instrumentation and control equipment designated as Seismic Category 1 are designed to resist and withstand the effects of the postulated earthquakes. Seismic Category 1 instrumentation and electrical equipment is designed to withstand the effects of the safe shutdown earthquake (SSE) defined in FSAR Subsection 3.7.1, and to withstand the effects of hydrodynamic loads without functional impairment. The Class 1 E equipment is capable of performing all safety-related functions during; (1) normal plant operation, (2) anticipated transients, (3) design basis accidents, and (4) post-accident operation, while being subjected to, and after the cessation of, the accelerations resulting from the SSE at the point of attachment of the equipment to the building or supporting structure.
c)
The SLC system should be incorporated into the plant's ASME Code ISI and IST Programs based upon the plant's code of record (10 CFR 50.55a).
W
PP&L CALCULATION SHEET Dept.
PROJECT Calc. No.
E -053-1012 Date Assessment of SBLC Rev. No.
Designed By G; Kowal System for Suppression Checked By Pool pH Control Sh. No.
14-of 138-The SBLC is designed to meet the design intent of the requirements of the ASME Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components'.
1 OCFR50.55a, "Codes and Standards, requires that an inservice inspection program be developed in accordance with ASME Section Xl. NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Plants", requires a test program to ensure that all ASME Code Class 1, 2, and 3 pumps and valves will be in a state of operational readiness to perform necessary safety functions throughout the life of the plant. The ASME Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components," describes an acceptable method of complying with the requirements of IOCFR5O.55a and NUREG-0800 for a test program to test ASME Code Class 1, 2, and 3 pumps and valves.
Where practical, all ASME Section III Class 1, 2, and 3 pumps are in-service tested in accordance with Subsection IWP of ASME Section Xl in order to establish and detect changes in the hydraulic and mechanical reference parameters. The pump test program meets, lo the extent practical, the requirements for establishing reference values of IWP-3000 of ASME Section Xl.
The allowable ranges of in-service test quantities, corrective actions, and bearing temperature tests are in accordance with IWP-3200 and IWP-4300 of ASME Section Xl.
SSES Procedure NDAP-QA-0423, commits the plant to ASME IST pump and valve testing as required by Technical Specification 5.5.6, "Inservice Testing Program". This Specification provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program includes testing frequencies specified in Section Xl of the ASME Boiler and Pressure Vessel Code and applicable Addenda.
Functional Testing:
Functional testing of the SBLC System is performed by (1) circulating demineralized water with the explosive valves closed and (2) pumping demineralized water from the test tank through the explosive valves into the reactor.
System testing enhances the reliability of the system and demonstrates system It I
d_;
i
PP&L CALCULATION SHEET Dept PROJECT Caic. No.
E-053-1012 Date Assessment of SBLC Rev. No.
Designed By G Kowalu System for Suppression Checked By Pool pH Control Sh. No.
12-of 138-also provides the capability to verity system pumping capability to the reactor when the plant is shut down.
d)
The SLC system should be incorporated into the nlant's Maintenance Rule proaram consistent with 10 CFR 50.65.
The SBLC System is designed to meet the intent of the requirements of 10CFR5O.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants". The SBLC Ssystem has been incorporated into the plant's Maintenance Rule Program.
The Commission's determination as stated in Regulatory Guide 1.160, Rev. 1, was that the decision that a maintenance rule was needed arose from the conclusion that proper maintenance is essential to plant safety. PPL has not committed to a particular revision of this regulatory guide.
However, the SBLC System is designed such that periodic surveillance testing and maintenance can be performed on system components.
PPL Procedure NDAP-QA 0413, "SSES Maintenance Rule Program," implements the SSES program for compliance with 10CFR50.65.
The following table summarizes PP&L's commitment to the SBLC System Maintenance Rule functions. The data for SBLC System is maintained (or viewed) at the following SSES Information System sites:
S:\\EPIXDATA\\READONLY\\FILES\\MAINTENANCE RULE DATA or S:\\EPIXDATA\\MSAccess\\Mntrule.mdb /wrkgrp F
FUNCTION MAINTENANCE RULE FAILURE FUNCTION (MRFF)
NUMBER l
GUIDANCE i STANDBY LIQUID CONTROL SYSTEM # 53 i
01A Pump A injects sodium Component failures resulting in the loss of pentaborate solution into capability to inject sodium pentaborate into the the reactor as an altemate reactor vessel.
means of shutting down the reactor independent of the CRD system W
PP&L CALCULATION SHEET Dept.
PROJECT CaIc. No.
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Designed By G. Kowal System for Suppression Checked By Pool pH Control Sh. No.
13-of 138-FUNCTION NUMBER FUNCTION MAINTENANCE RULE FAILURE FUNCTION (MRFF)
I GUIDANCE 0
01 B Pump B injects sodium Component failures resulting in the loss of pentaborate solution into capability to inject sodium pentaborate into the the reactor as an alternate reactor vessel.
means of shutting down the reactor independent of the CRD system 02 Provide containment Failure of 1 (2)48F007 and HV1 (2)48F006 to close isolation on demand. LLRT is monitored with the overall containment integrity function in system 59.
03 Components of this system Leakage through a visible indication (i.e. through are required to maintain wall leakage) resulting in loss of reactor coolant integrity of the reactor fluid from the reactor coolant system boundary.
coolant pressure boundary 04 Maintain SLC piping and Component failures resulting in loss of capability tank at sufficiently high to maintain SLC fluid within the required limits for temperature to keep fluid temperature. Failure of the heat tracing, sodium pentaborate above including failure of the associated breaker saturation temperature 1(2)B236063 (A heater) or 1(2)B236111 (B heater), may cause a MRFF. Reference TS Table 3.1.7-2.
05 Provide SBLC flow and Failures that result in the inability to determine storage tank level SBLC flow or storage tank level indication indication to the control (indication is available from 1 (2)C601 and the room plant computer). Blockage of a bubbler tube may be a MRFF.
06 Provide input to RWCU SBLC logic system component failures resulting in Isolation logic on SBLC the inability to isolate the RWCU outboard actuation isolation valve, HV1 (2)44F004.
07 Provide Containment Failure that results in the inability to determine the Isolation valve position position of HV1 (2)48F006 from the control room.
indication signal for control Light bulb failures are not considered a MRFF room display IAW NDAP-OA-0413.
08 Provide an alternate Component failures resulting in loss of capability means of reactor vessel to makeup to the reactor vessel via the SBLC.
makeup via the SLC Boron Tank or demin water cross-l tie V
PP&L CALCULATION SHEET Dept.
PROJECT Caic. No.
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14-of 138-e)
The SLC system should meet 10 CFR 50.49 and Appendix A (GDC
- 4) to 10 CFR 50.
The SBLC System is designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation (not accident), maintenance, and testing. (GDC 4)
Table A-1 of licensing topical report NEDE-31096-P, "Anticipated Transients Without Scram; Response to NRC ATWS Rule, 10CFR50.62" notes that NRC guidance for EQ for a new SLC System would be to design for anticipated operational occurrences only, not for accidents. A review of the reactor building post-LOCA temperature response calculation (EC-LOCA-0500) determined that the area in which the SBLC system is located only increases a few degrees during the first few hours post-LOCA. Additionally, the SBLC equipment will not experience significant radiation damage given the short duty time of the SBLC system and the early initiation time for the design basis scenario. The relative humidity and area pressures should remain relatively unchanged. Given that SBLC initiation will occur within the first few hours post-LOCA and the demand time is low, the environment that the SBLC system electrical equipment will experience post-LOCA is not significantly different than the environment that it experiences during normal operation and will be able to successfully fulfill its design basis function.
The SBLC is appropriately protected against dynamic effects, including the effects of missiles that may result from equipment failures and from events and conditions inside the plant. Runs of system piping in the secondary containment which are subject to damage due to possible failure of nearby piping or components of other systems are protected by structural steel or reinforced concrete, or spatial separation (FSAR Sect. 9.3.5, 7.4.1.2).
FSAR Section 3.11 discusses the normal and accident environmental conditions relative to temperature, pressure, humidity, and integrated radiation exposure under which systems and components required for safe shutdown are required to remain functional. Reference 6.2 lists harsh environments of various plant areas, including those where the SBLC is located, and the normal and anticipated accident environmental conditions in these areas. Safety-related equipment is installed in accordance with mechanical and electrical separation requirements.
It is also designed and qualified to function properly in the environments listed.
W
PP&L CALCULATION SHEET Dept.
PROJECT Calc. No.
EC-053-1012 Date Assessment of SBLC Rev. No.
Designed By (l Kotwal System for Suppression Checked By Pool pH Control Sh. No.
15-of 138-Tornado-generated missiles are the only natural phenomena missiles considered. Protection consists of tornado-resistant buildings with structures and barriers designed to protect against the postulated missiles listed in FSAR Table 3.5-4.
The SBLC is designed to meet the intent of Regulatory Guide 1.46, "Protection Against Pipe Whip Inside Containment", 5/73. (FSAR Section 3.6.2.1.4.5)
General Design Criterion 4, "Environmental and Missile Design Basis" (GDC 4),
requires that structures, systems, and components important to safety be appropriately protected against dynamic effects that may result from equipment failures, including the effects of pipe break. Regulatory Guide 1.46 describes an acceptable basis for selecting the design locations and orientations of postulated pipe breaks in designing the SBLC System piping within the reactor containment and for determining the measures that should be taken for restraint against pipe whipping that may result from such breaks.
Pipe whip is an unrestrained pipe movement of either end of the ruptured pipe in any direction about a plastic hinge formed at the nearest pipe whip restraint.
Pressurized components in the SBLC System where service temperature exceeds 2000F or service pressure exceeds 275 psig were evaluated as to the potential for pipe whip. Pipe whip restraints are provided for the SBLC injection line inside the primary containment. The plant has been designed in accordance with the criteria of Branch Technical Position ASB 3-1, "Protection Against Postulated Piping Failures in Fluid Systems Outside ContainmentV and is documented in Section 3.6 of NUREG-0776, "Safety Evaluation Report Related to the Operation of SSES Units I and 2".
4.2 Reliability Requirements in Support of AST (a) The licensee should identify the non-redundant active components in the SLC system and provide their make, manufacturer and model number.
Through a thorough review of the SBLC System components (Attachment 1) and the system P&lDs (Reference 6.6) single components with no backup or redundant component with a singe power source (SBLC tank heaters) were Identified and documented as the single failure candidates (Table 4.4.2).
Characteristics of each non-redundant active component are presented in detail in the respective section where the component is individually discussed.
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PP&L CALCULATION SHEET Dept.
PROJECT Calc. No.
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Designed By-GJo K al System for Suppression Checked By-Pool pH Control Sh. No.
19-of 138-However, Table 4.2.1 below identifies the non-redundant components and their design characteristics.
Table 4.2.1 - Component Characteristics Component Component Component Component Model Component Name Function System Number Manufacturer Number (Unit)
SBLC Initiate HS14804 CR 2940 General Manual system (U)
Electric initiation boron HS24804 switch injection.
(U2)
(Reference 6.24, (Reference Closes Sh. 1) 6.24, Sh. 1) contacts that energize the A and B Pumps SBLC Normally HV148F006 1 'A " Yarway Yarway Corp.
Outboard CLOSED.
(U1)
Welbond Valve Blue Bell, PA motor Acts as an HV248FQ06 with Limitorque operated isolation (U2)
Electric Motor stop check check valve Actuator.
valve in the Globe stop-check (Reference injection line valve.
6.21, Sh. 1) when in the OPEN (Reference 6.21, position.
Sh. 1)
SBLC Check valve 148F007 1 tk ' Y-Type Borg Warner inside for the SBLC (U1)
Check Valve Nuclear drywelr injection line. 248F007 Part No. 74730 Valve check (U2)
Division valve.
(Reference 6.10, Van Nuys, Sh.1)
CA (Reference 6.10, Sh. 1)
Locked Stays open 148F008 1 '/2 " Gate Valve, Borg Warner open to allow (Ul)
Cres.
Nuclear manual boron 248F008 Valve injection injection.
(U2)Part No. 74680 Division I injection I injection.
I (U2)
I Part No. 74680 I Division 0
V
PP&L CALCULATION SHEET Dept.
PROJECT Calc. No.
EC 053 1012 Date Assessment of SBLC Rev. No.
Designed By G; Kowal System for Suppression Checked By Pool pH Control Sh. No.
17-of 138-valve Down stream of the above check valve.
(Reference 6.20, Sh. 1)
Van Nuys, CA (Reference 6.20. Sh. 1)
SBLC Operates to 1E219 (Ul)
Part No.
General Storage automatically 2D433G0022 Electric tank heater maintain 2E219 (U2)
Part No.
General UA" solution 2D433GO022 Electric temperature (10 kW) above the (Reference precipitation 6.31) point (Reference 6.31)
SBLC Used to I E220 (Ul)
Part No.
General Storage elevate the 166B7320P001 Electric tank heater mixture "B"
temperature 2E220 (U2)
Part No.:
Wellman Co.
during 2D507G140 (40 kW) chemical addition (Reference 6.31)
(Reference
____6i3-.
Additional information on SBLC operation and redundancy is provided below.
Operation of the SBLC pumps and the explosive actuated valves that inject the solution into the reactor are controlled from the control room panel by a single manual control switch on panel 1 C601 keylocked in the 'STOP' position. This is shown on drawing J-802 Sheet 2 (Reference 6.25). The key is removable in the left "STOP" position. The SBLC is initiated by turning the keylock switch to the "START" position. Placing the key switch in the "START" position initiates both "A" and "B" trains of the SBLC. When the SBLC is initiated, both explosive-actuated valves fire. Simultaneously, both SBLC pumps are started and parallel solution injection begins. This is shown on elementary diagram M1 -C41-36 Sheets 1, 2, and 3 (Reference 6.26) and M1-C41-31 (Reference 6.27).
Concurrently with initiation of the SBLC, a signal is sent to the Reactor Water Cleanup (RWCU) System to isolate the RWCU System from the reactor to prevent the removal and dilution of the neutron absorbing solution. The SBLC pumps may be operated locally for system testing, but actuation of the explosive actuated valves may only be accomplished from the control room.
W
PP&L CALCULATION SHEET Dept.
PROJECT Catc. No.
EC-053-10t2 Date Assessment of SBLC Rev. No.
Designed By G Kowal System for Suppression Checked By Pool pH Control Sh. No.
18-of 13.-
Redundancy has been designed into the electric power system supporting SBLC System components, controls and instrumentation. Justification in support of this statement follows.
Redundancy of SBLC System Comnonents:
The on-site electric power system includes four load groups. The load groups are redundant in that three load groups are capable of ensuring vital functions are maintained in the event of postulated accident. Sufficient independence Is provided between redundant load groups to ensure that postulated single failures affect only a single load group and are limited to the extent of total loss of that load group. The remaining redundant load groups remain intact to provide for the containment integrity.
The SBLC pumps, storage tank heaters and instrumentation and controls are powered from or connectable to the standby AC power supply. The pump, explosive actuated valve, and instrumentation and controls for loop NA" are powered from load group 1 C and those components in loop uB" are powered from load group 1 A. All components in the SBLC are connected to Division I power, but the use of two load groups per electrical division provides for electrical separation for the SBLC System. The only exception is the storage tank heaters which are powered from a common bus for each respective unit.
The SBLC pump circuit is protected or separated from the explosive valve ignition circuit. Protection or separation between these two circuits is required so that a short in the ignition circuit will not affect operation of the pumps.
The ignition circuit for each explosive actuated valve squib is fused to prevent disabling any pump with a short In any squib valve. The fuses are shown on MI -
C41-36 (Reference 6.27). Each firing circuit (two per valve) contains a single fuse (C41 -F2, F3, F5, F6) which are sized at 2 amps. An electrical short in the ignition circuitry will cause the fuse to fail, isolating the shorted circuit from the balance of the control system.
SBLC System Control:
Controls are provided, in the control room, from which actions can be taken to operate the SBLC System safely under normal conditions. (GDC 19)
Controls for normal operation, monitoring, and testing the SBLC are placed in the main control room. Information is furnished to the operator through meters, W
main control room. Information is furnished to the operator through meters,
PP&L CALCULATION SHEET Dept.
PROJECT CaIc. No.
E -053-1012 Date Assessment of SBLC Rev. No.
Designed By G KowaL System for Suppression Checked By Pool pH Control Sh. No.
10-of 139-annunciators, gauges, and indicating lights as to the standby and operational status of the SBLC. Operation of the SBLC from the control room is entirely a manual operation to prevent inadvertent initiation of the system.
Instrumentation and Control:
Criterion XIV of Appendix B to 1 OCFR50 'Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants", requires that measures be established for indicating the operating status of structures, systems and components of the nuclear power plant, such as by tagging valves and switches, to prevent Inadvertent operation. Section 50.55a of 10CFR50, "Codes and Standards", requires in Paragraph (h) that protection systems meet the requirements set forth in IEEE 279-1971, "IEEE Standard Criteria for Protection Systems for Nuclear Power Generating Stations"'.
The continuity of the explosive valve circuit is continuously monitored and is annunciated in the control room if the continuity is broken (current flow is interrupted). The level and temperature of the storage tank solution are continuously monitored with the high and low levels and high and low temperature conditions annunciated in the control room. The removal of all other equipment for servicing is manually annunciated and is administratively controlled.
The SBLC System is designed to meet the intent of Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants To Assess Plant and Environs Conditions During and Following an Accident", Revision 2, 12180.
General Design Criterion 13, 'Instrumentation and Control" (GDC 13), requires that instrumentation be provided to monitor variables and systems over their anticipated ranges for accident conditions as appropriate to ensure adequate safety. General Design Criterion 19, "Control Room" (GDC 19), requires that equipment, including the necessary instrumentation, at appropriate locations outside the control room be provided with the design capability for prompt hot shutdown of the reactor. Regulatory Guide 1.97 provides an acceptable method for designing the SBLC instrumentation to conform to the requirements of General Design Criteria 13 and 19.
AAdI A_
a__4 n-7 M
A i nn I
- AA -d_-I -
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1_ ^ _-
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PP&L CALCULATION SHEET Dept-PROJECT Calc. No.
E E053-1012 Data Assessment of SBLC Rev. No.
Designed By G Kowal System for Suppression Checked By Pool pH Control Sh. No.
20- of 138-level instrumentation LI/FI-1(2)4806 (including LE-1(2)4812 and LT-C41-1 (2)N001) has a detection range of 0 to 126 inches and 0 to 5000 gallons. The tank size is 5711 gallons (Reference 6.38). Per Reference 6.4 the setpoint volume for High Alarm is at 4897 gallons and Low Alarm at 4587 gallons (which is also the Technical Specification 3.1.7 limit). LE-1 (2)4812 and LT-C41-1 (2)NO01 are not 1 E qualified but are fed from a vital UPS bus, 1 (2)D666, which meets the requirement that instrumentation be powered from a reliable source.
The instrument readouts are real time and continuous. The instrumentation is required to be of Regulatory Guide 1.97 Type D. Category 2, design and qualification criteria. Additionally, the instrumentation should be energized from a high reliability power source, but not necessarily standby power, and should be backed up by batteries where momentary interruption is not tolerable. PLA-2222 (Reference 6.28), "Susquehanna Steam Electric Station Conformance to Regulatory Guide 1.97, Rev. 2", describes in Section 4.0 that the SBLC flow and level indication exceeds the range and meets the environmental qualification and power supply requirements for Type D, Category 2 instrumentation. The instrumentation is not required to be seismically qualified, per Regulatory Guide 1.97 Position 1.4.
(b) The licensee should provide the design-basis conditions for the component and the environmental and seismic conditions under which the component may be required to operate during a design basis accident. Environmental conditions include design-basis pressure, temperature, relative humidity and radiation fields.
The staff reviewer will compare the environmental and seismic conditions associated with the design-basis accident to the conditions for which the component was designed to determine whether the component is capable of performing its intended function.
Environmental conditions, including design basis pressure, temperature, relative humidity and radiation fields are presented in Table 4.2.2 below. To provide a clear distinction of environmental conditions, the Normal Operation and DBA Columns have been split into a) conditions internal to the system and b) 1i conditions external to the system. The seismic qualification for each component is discussed in Section 4.5.
0 W
nw I
31gr Dck PP&L CALCULATION SHEET Dept.
PROJECT Calc. No.
EC 5
SV3-1012 Date Assessment of SBLC Rev. No.
Designed By-G.Kowal System for Suppression Checked B)
Pool pH Control
$h. No.
2-of 138-Table 4.2.2 - Component Design/Environmental Operating Conditions Component Location where Design Basis of Normal Operating DBA Conditions of Component Component Mode of Component Operation Resides Component (Conditions of Component as Part of (Conditions of the System)
Component during System Operation)
HS14804- (U)
Control Room P =14.7psia P
14.7psia P = 14.7psia HS24804 (U2)
T=75F T75 F T =75 F (Not a harsh RH = 50%
RH= 50%
RH= 50%
(Manual environment Rad = s.5 mR/hr Rad = 5.5 mR/hr Rad = s.5 mR/hr initiation switch) designation)
Reference (6.29, Reference (6.29, Reference (6.29, Reference (6.29, 6.30, 6.30) 6.30) 6.30)
FSAR Sect. 6.4.4.1)
HV148F006 Reactor Building P = 1203 psi Injection time frame Injection time frame (Ul)
EL 752' T = 570 F HV148F006 Rooms 1-506,11-RH = N/A (water)
INSIDE SYSTEM INSIDE SYSTEM (U2) 506 Rad = 2 100 mR/hr P = Reactor static P s56 psia head to1203 psi (Firstisolat Reference
-(6.31, T = 70/570 F T 5340 F
I 5igr
~ck PP&L CALCULATION SHEET Cac No.
Deptp Date Designed By G Kowal!-
Checked By PROJECT Assessment of SBLC System for Suppression Pool pH Control Calc. No.
Rev. No.
Sh. No.
E C--0 53-10 _
22-of 1 38 I -
l r
I l
I Component Location where Component Resides Design Basis of Component (Conditions of Component as Part of the System)
Normal Operating Mode of Component (Conditions of Component during System Operation)
DBA Conditions of Component Operation IJI L
v
^
v A
cnecK valve) 6.32) 6.32, Sht. 9)
RH = N/A (water)
Rad a 100 mR/hr EXTERNAL ENV.
P - 14.7 psia T = 60/110 F RH = 20/80%
Rad = 10 R/hr Reference (6.31, 6.32, FSAR Table 9.3-11)
RH = N/A (water)
Rad ! 100 mR/hr EXTERNAL ENV.
P - 14.7 psla T = to 133 F RH = 100%
Rad = 6.2 x 10 4 F/hr Reference (6.31, 6.32, FSAR Table 9.3-11) 148F007 (Ul)
Drywell P = 1203 psi Injection time frame Injection time frame 248F007 (U2)
EL 739' T = 570 F Rooms 1-400,11-RH = N/A (water)
INSIDE SYSTEM INSIDE SYSTEM 400 Rad = > 100 mR/hr P = Reactor static P s 56 psia (Check valve)
Refrce6.33, head tol 203 psi T = 340 F
I te.-.
3igr ack 0
PP&L CALCULATION SHEET Dept.
Date Designed By G Kowal Checked By PROJECT Assessment of SBLC System for Suppression Pool pH Control CaIc. No.
Rev. No.
EC 053 1012 Sh. No.
2-of 138-I
p
-
I Component Location where Component Resides Design Basis of Component (Conditions of Component as Part of the System)
Normal Operating Mode of Component (Conditions of Component during System Operation)
DBA Conditions of Component Operation a
F 7
1 34)
Reference (6.31, 6.32, Sht. 9)
T = 70/570 F RH = N/A (water)
Rad = 100 mR/hr EXTERNAL ENV.
P = 0.1-1.5 psig T = 90/150 F RH = 20/90 %
Rad = 26.25 R/hr Reference (6.31, 6.33, FSAR Table 9.3-11, 6.40)
T RH = N/A (water)
Rad = a 100 mR/h EXTERNAL ENV, P s 56 psia Tsto34OF RH = 100%
Rad = 7.1 x 106" /hr Reference (6. 33, FSAR Table 9.3-11) 148F008 (Ul)
Drywell P = 1203 psi Injection time frame Injection time frame 248F008 (U2)
EL 738' T = 570 F Rooms 1-400,11-RH = N/A (water)
INSIDE SYSTEM INSIDE SYSTEM 400 Rad = z 100 mR/hr P = Reactor static P _ to 56 psia
I Vt_
3igr
?ck' PP&L CALCULATION SHEET
- Dept, Date Designed By GJKowaL Checked By PROJECT Assessment of SBLC System for Suppression Pool pH Control Calc. No.
Rev. No.
EC.0534042-Sh. No.
24-of 138-r l
n I
l
___1.
l l
'..omponent Location where Component Resides Design Basis of Component (Conditions of Component as Part of the System)
Normal Operating Mode of Component (Conditions of Component during System Operation)
DBA Conditions of Component Operation I_
_ I J.I I
1
_ J kiockea open gate valve)
HeTerence (b. ~33, 34)
Reference (6.31, 6.32, Sht. 9) head tol203 psi T = 70/570 F RH = NIA (water)
Rad = > 100 mR/hr EXTERNAL ENV.
P = 0.1-1.5 psig T = 90/150 F RH = 20/90 %
Rad = 26.25 R/hr Reference (6.31, 6.33, FSAR Table 9.3-11, 6.40)
T = 85/95 F RH = N/A (water)
Rad=> 100 mR/h EXTERNAL ENV.
P 5 56 psia TS to 340 F RH = 100%
Rad=7.1 x106R/hr Reference (6. 33, FSAR Table 9.3-11) 1 E219 (U1)
Reactor building Tank Conditions Tank Conditions Tank Conditions 2E219 (U2)
EL 749' 1-513,11-513 INSIDETANK INSIDE TANK INSIDE TANK
XI
,3igr ack.
PP&L CALCULATION SHEET Dept.'
Date Designed By..G.Kowal
[Checked By-PROJECT Assessment of SBLC System for Suppression Pool pH Control Calc. No.
Rev. No.
Sh. No.
E -053-4012 -
25-of 138-U P
pml Component Location where Component Resides Design Basis of Component (Conditions of Component as Part of the System)
Normal Operating Mode of Component (Conditions of Component during System Operation)
DBA Conditions of Component Operation J
I (10 kW heater inside SBLC tank)
Reference (6.32)
P = approx 10' water T = 85/95 F RH = N/A (water)
Rad = 0.1 mR/hr OUTSIDE TANK P =-.25 inwg T = 60/100 F RH = 20/80%
Rad=0.1 mR/hr Reference (6.4, 6.32)
P = approx 10' water T = 85/95 F RH = N/A (water)
Rad = 0.1 mR/hr P = approx 10' water T = 85/95 F RH = N/A (water)
Rad=0.1 mR/hr OUTSIDE TANK P - 14.7 psia T= 113 F RH = 100%
Rad = 100 R/hr Reference (6.4, 6.32)
OUTSIDE TANK P - 14.7 psia T = 60/100 F.
RH = 20/80%
Rad = 0.1 mR/hr Reference (6. 4, 6.32) 1 E220(U1)
Reactor building Tank Conditions Tank:onditions Tank Conditions 2E220(U12)
EL 749'1I 1-513,11-513 INSIDE TANK INSIDE TANK INSIDE TANK P =apx 10' water P
Wp l
=approxl0'water
E ty-
- igr
- ack, PP&L CALCULATION SHEET Dept.
Date Designed By G LKowa!
Checked By PROJECT Assessment of SBLC System for Suppression Pool pH Control Calc. No.
Rev. No.
EC-053-101 2 Sh. No.
26-of 138-S S
S Component Location where Component Resides Design Basis of Component (Conditions of Component as Part of the-System)
Normal Operating Mode of Component (Conditions of Component during System Operation)
DBA Conditions of Component Operation A
I I.
I (40 kW heater
- -inside SBLC tank)
Reference (6.32)
T = 85/95 F RH = N/A (water)
Rad = 0.1 mR/hr OUTSIDE TANK P = -.25 inwg T = 60/100 F RH = 20/80%
Rad = 0.1 mR/hr Reference (6. 4,6.32) water T = 85/95 F RH = N/A (water)
Rad = 0.1 mR/hr OUTSIDE TANK P - 14.7 psia T = 60/100 F RH = 20/80%
Rad=0.1 mR/hr Reference (6. 4, 6.32)
T = 85/95 F RH N/A (water)
Rad = 0.1 mR/hr OUTSIDE TANK P - 14.7 psia T=113F RH= 100%
Rad = 100 R/hr Reference (6. 4, 6.32)
PP&L CALCULATION SHEET Dept.
PROJECT Calc. No.
EC-053-1012 DatP Assessment of SBLC Rev. No.
Designed By G KJwal-System for Suppression Checked By Pool pH Control Sh. No.
27-of 138-0 (c) The licensee should indicate whether the component was purchased in accordance with Appendix B to 10 CFR Part 50. If the component was not purchased in accordance with Appendix B, the licensee should provide information on the quality standards under which it was purchased. For the latter situation, information on the component would be reviewed by appropriate technical review branch responsible for the compoOnent, as requested by the lead SPSB reviewer.
Table 4.2.3 affirms the purchase requirement of the components under 1 OCFR50, Appendix B criteria and points to the reference where this is confirmed.
Table 4.2.3 - 1 OCFR50, Appendix B Requirement Component Classification Purchased in Where accordance referenced with 10CFR 50, App. B HS14804 Q
Yes Reference (Ul)
(6.15, 6.34)
HS24804 (U 2)_
HV148FO06 Q
Yes Purchase (U)
Spec. P-14A HV248F006 (U2) and Reference (6.15,6.35) 148F007 Q
Yes Purchase (Ul)
Spec. P-14BC 248F007 (U2) and Reference (6.15, 6.36)
V
PP&L CALCULATION SHEET Dept.
PROJECT Calc. No.
E 053 -1012 Date Assessment of SBLC Rev. No.
Designed By G Kowal System for Suppression Checked By Pool pH Control Sh. No.
24-of 138-
,Y t
148F008 Q
Yes Purchase (Ul)
Spec. P-14BC 248F008 (U2)and Reference (6.15, 6.37) 1E219 (U1) 0 Yes Reference 2E21_9 (U2)
(6.15,6.34) 1 E220 (Ul) 0 Yes Reference 2E220 (U2)
(6.15, 6.34)
(d) The licensee should provide the performance history of the component both at the licensee's facility and in industry databases such as EPIX and NPRDS.
The staff reviewer will use this information to evaluate the reliability of the component relative to other components used in safety-related applications.
Information has been included in Attachments 2 and 3 of this calculation. The data In Attachment 2 is an extensive search of the EPIX and NPRDS data bases. contains confirmation of Susquehanna's component operating history.
Other than routine maintenance on the Susquehanna specific components no failures have occurred. Similar results were obtained from the extensive search of EPIX and NPRDS data bases. Therefore, the equipment is reliable.
(e) The licensee should provide a description if its inspection and testing program including standards, frequency and acceptance criteria. The staff reviewer will use this information to evaluate the licensee's activities to monitor the component's performance at the facility. The information on the component would be reviewed by appropriate technical review branch responsible for the component, as requested by the lead SPSB reviewer.
In response to the above, Table 4.2.4 below summarizes the inspection and testing program for the SBLC System and components W
4 Pt,.
te-sigr ack 0
PP&L CALCULATION SHEET Dept.
PROJECT Calc. No.
EC-053-1012 Date Assessment of SBLC Rev. No.
Designed By GKowaL System for Suppression Checked By Pool pH Control Sh. No.
29-of 138-Tab;e 4.2.4 - Component Testing and Inspection Program
-esl
'roe 40.
00.
.!00.
Test/lnspection Title Purpose Acceptance Criteria Unit Procedure NO, SUS-ISTPLN-Pump and Valve Unit 1 &2 IST Pump and Valve As noted In Test
- 1 100.0 Inservice Inspection Program establishes testing Requirements Testing Program requirements to assess the
- 2 SUS-ISTPLN-operational readiness of 200.0 certain ASME Safety Class 1, 2, and 3 pumps and valves that are required to:
- a.
Shut down the reactor to the safe shutdown condition,
- b.
Maintain the reactor in the safe shutdown condition, or
- c.
Mitigate the consequences of an accident.
.Tests Re.uired for SBL
l l-
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Migr ack' wesi
'ro0 JO.
PP&L CALCULATION SHEET Dept.
PROJECT Date Assessment of SBLC Designed By G.JowaLt~
System for Suppression Checked By Pool pH Control Calc. No.
Rev. No.
Sh. No.
Cf%_nr0_-1 n1 q 3Q-of 138-Testllnspection I
I -
lTest/Inspection Procedure NO.
Title Purpose Acceptance Criteria Unit
& -
A I
1.
. Valves:
HV1(2)48FO06:
Full Stroke Open - Once Every 92 d Stroke rime Open - Once Every 92 d Full Stroke Closed - Once Every 92 d Stroke Time Closed - Once Every 92 d Seat leakage test required by 10 CFR 50 Appendix J -In accordance with owners program.
Remote Position Indication -
Once every two years I __________
I 3t,
'e_
3igr ack I
PP&L CALCULATION SHEET Dept.
PROJECT Date Assessment of SBLC Designed By G KowaL! System for Suppression Checked By Pool pH Control Cabc. No.
Rev. No.
=nfl2_1 An1 0
=
Sh. No.
3-of 138-esl
'roc 40.
.r Test/inspection Procedure NO.
Title Purpose Acceptance Criteria Unit 1(2)48F007:
Full Stroke Open - Once Every 92 d Full Stroke Closed - Once Every 92 d Seat leakage test required by 10 CFR 50 Appendix J -In accordance with owners program 1(2)48F008 Remote Position Indication -
Once every two years SO-153-003 24 - Monthly SBLC
- 1) demonstrate all heat traced All heat traced piping
- 1 Operability piping is unblocked by demonstrated unblocked by SO-253-003 pumping from storage tank to pumping from storage tank to
- 2 test tank test tank
_2) demonstrate the capability
I
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- e 3igr Dck 0
0 PP&L CALCULATION SHEET Dept.
Date Designed By G Kowa!-
Checked By PROJECT Assessment of SBLC System for Suppression Pool pH Control Calc. No.
Rev. No.
Sh. No.
crl non0
-4 n1 2 r_-
32-of 138-esl
'rot 40.
Test/Inspection Test/lnspection Procedure NO.
Title Purpose Acceptance Criteria Unit
-
d
I I
of SBLCI Systems pumps to individually provide required flow at a specific discharge pressure and fulfilling requirements of Station In-Service Test (IST) Program Plan quarterly testing
- 2) demonstrate proper opening and closing of SBLC Injection HV-148F006
- 3) demonstrate proper opening of Injection Check 1 48F007 Pump A/B Minimum Flow is >
41.2 gpm with a Discharge Pressure of 2 1395 psig SBLC Pump A/B Flow within 41.2 and 44.3 gpm with Discharge Pressure within 1395 and 1405 psig
- 0-SO-1 53-004 Quarterly SBLC Flow Demonstrate capability of Pump AIB Minimum Flow is 2
- 1 Verification Standby Liquid Control 41,2 gpm with a Discharge SO-253-004 System pumps to individually Pressure of 2 1395 psig
- 2 provide required flow at a specified discharge pressure, SBLC Pump N/B Flow within fulfilling requirements of 41.2 and 45gpm with
=
Station Inservice Test (IST)
Discharge Pressure within
I pt, toe sigi eck PP&L CALCULATION SHEET Dept.
PROJECT Date---
Assessment of SBLC Designed By G KowaL-System for Suppression Checked By-Pool pH Control CaIc. No.
Rev. No.
FrC.n5inia-Sh. No.
33-of 138-res
'rc0 40O.
Test/Inspection Testtinspection Procedure NO.
Title Purpose Acceptance Criteria Unit h
- d.
d
-
SO-153-015 SO-253-015 Two Year SBLC RPI Checks Demonstrate proper operation of Remote Position Indicators (RPI's) used In valve exercising testing as required once per two years by Station Inservice Testing (IST)
Program Plan HV-148-F006 RPI CLOSED indication acceptable Yes/No HV-148-F006 RPI INTERMEDIATE indication acceptable Yes/No HV-148-F006 RPI OPEN indication acceptable Yes/No HV-148-F008 RPI CLOSED indication acceptable Yes/No HV-148-F008 RPI INTERMEDIATE indication acceptable Yes/No HV-148-F008 RPI OPEN indication acceptable
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40, 0
PP&L CALCULATION SHEET Dept.
PROJECT Date Assessment of SBLC Designed By G KowaL' System for Suppression Checked By-Pool pH Control r
Calc. No.
Rev. No.
Sh. No.
cFo-r
- 2.
n n
j u
o 34-of 138-E-,:
Testlinspection Title Purpose Acceptance Criteria Unit Procedure NO.
Yes/No SE-159-047 LLRT OF STANDBY This procedure describes how A Combined leak rate of less
- 1 LIQUID CONTROL to perform the LLRT for the than or equal to 3.3 gpm SE-259-047 PENETRATION Standby Liquid Control (12,492 ccm) for all
- 2 NUMBER X-42 AND Penetration Number X-42.
containment isolation valves CHECK VALVE NDAP-QA-0412 outlines the in hydrostatically tested lines OPERABILITY TESTS frequency. Additionally, this which penetrate the Primary procedure covers 24 month Containment, when tested at check valve operability testing 1.10 P8, 49.5 psig.
required by the ASME code per TS 5.5.6.
Confirm that check valve HV148F006 closes by observing essentially restricted flow through HV148F006 to vent 148005.
PP&L CALCULATION SHEET
- Dept.
PROJECT Calc. No.
EC-053-1 012 Date Assessment of SBLC Rev. No.
Designed By CG Kowal System for Suppression Checked By Pool pH Control Sh. No.
of 138-(f) The licensee should also indicate the potential compensating actions that could be taken within an acceptable time period to address the failure of the component. An example of a compensating action might be the ability to jumper a switch in the control room to overcome this failure. The staff reviewer will consider the availability of compensating actions and the likelihood of successful injection of the sodium pentaborate where non-redundant active components fail to perform their intended functions.
Compensating actions are discussed in the specific sections for the Hand Switch (HS 1(2)4804), Section 4.5.2, and replacement of the heating element in the Borated Water Storage Tank, Section 4.5.4.
4.3 All Active and Passive Components of the SBLC System To obtain a complete listing of the SBLC System equipment and components, the SSES's Nuclear Information Management System (NIMS) (Reference 6.16) was queried. Out of a database of 381.572 pieces of equipment and components the search was narrowed to 373 components for the SBLC System. A copy of this data listing is included as Attachment No. 1. This data set was then reviewed in conjunction with the System P&ID (Reference 6.6) for components critical to the SBLC System function, These results are discussed in the subsequent Section 4.4.
4.4 Critical Components Subject to Single Failure Criteria From the data listed in Attachment No. 1 and the System P&ID nineteen components in each unit's SBLC System were identified as being contributing to (or resulting) in potential single failure. These components are summarized in the following Table 4.4.1.
A further assessment V
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EG 3-0 1012 Assessment of SBLC Rev. No.
Designed Bym KnalJa>l System for Suppression Checked By Pool pH Control Sh. No.
36-of 138-TABLE 4.4.1 SBLC SYSTEM COMPONENTS LIST CONTRIBUTING TO, OR RESULTING IN SINGLE FAILURE N
rSINGLE FAILURE O
COMP. ID.
SYST.
COMPONENT NAME I FUNCTION CRITERIA NO.
COMPONENT UNIT I 1
148011 153A SBLC INJECTION PUMP A STORAGE TANK SUPPLY VLV NO 2
148F001 163A SELC INJECTION PUMP B STORAGE TANK SUPPLY VLV NO 3
148F002A 153A SBLC INJECTION PUMP A SUCTION VLV NO 4
148F002B 153A SBLC INJECTION PUMP B SUCTION VLV NO 5
148F003A 1S3A SBLC INJECTION PUMP A DISCHARGE VLV NO 6
148F003B 153A SBLC INJECTION PUMP B DISCHARGE VLV NO 7
148F004A 153A SQUIB VLV A NO 8
148F004B 153A SQUIB VALVE 8 NO 9
148Ft07 153A CHECK VALVE YES 10 148FC08 153A STANDBY LIOUID CONTROL INJ ISO VALVE YES 11 148F033A 1S3A CHECK VALVE NO 12 148F033B 153A CHECK VALVE NO 13 1E219 153A SBLC STORAGE TANK ELECTRIC HEATER A YES 14 1E220 153A SBLC STORAGE TANK ELECTRIC HEATER B YES 15 IP208A 153A STANDBY UQ CONTROL PUMP 'A NO 16 1 P208B 153A STANDBY UQ CONTROL PUMP 'B NO 17 1T204 153A STANDBY LIQUID CONTROL STORAGE TANK NO (PASSIVE) 18 HS14804 t53A SBLC MANUAL INITIATION SWITCH YES 19 HV148FOO6 153A SBLC OB INJECTION VALVE YES UjNIT 2 1
248011 253A SBLC INJECTION PUMP A STORAGE TANK SUPPLY VLV NO 2
248F001 2S3A SBLC INJECTION PUMP B STORAGE TANK SUPPLY VLV NO 3
248F002A 253A SBLC INJECTION PUMP A SUCTION VLV NO 4
248F00ZB 253A
_BLC INJECTION PUMP B SUCTION VLV NO 5
248F003A 253A SBLC INJECTION PUMP A DISCHARGE VLV NO 6
248F003B 253A SBLC INJECTION PUMP B DISCHARGE VLV NO 7
248FO04A 253A EXPLOSIVE ACTUATED NO 8
248F004B 253A EXPLOSIVE ACTUATED NO 9
248F007 263A CHECK VALVE YES 10 248F008 253A STANDBY LIQUID CONTROL NJ ISO VALVE YES I 1 248F033A 253A CHECK VALVE NO 12 248F033B 253A SBLC PUMP 2P208B DISCHARGE CKV NO 13 2E219 253A SSLC STORAGE TANK ELECTRIC HEATER A YES 14 2E220 253A SBLC STORAGE TANK ELECTRIC HEATER B YES 15 2P208A 253A STANDBY LIO CONTROL PUMP A' NO 16 2P208B 253A STANDBY L10 CONTROL PUMP 'B' NO 2T204 253A STANDBY LQUID CONTROL STORAGE TA NO (PASSIVE) 18 HS24804 253A SBLC MANUAL INITIATION SWITCH YES 19 HV248F006 253A S8LC 01 INJECTION VALVE YES lU
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Designed Byg G Kowal System for Suppression Checked B y Pool pH Control Sh.No.
3 of 139-of components in this table with respect to design attributes such as redundancy, single pow source, interlocks and hand operation results in a further reduction to six potential single failure components for each unit. A summary Table 4.4.2 of these components is shown below, with the corresponding identification number from Table 4.1 above.
TABLE 4.4.2 Single Failure Criteria Components N
SINGLE FAILURE 0
COUP. ID.
SYST.
COMPONENT NAME I FUNCTION CRITERIA NO.
COMPONENT/
ACTIVE (PASSIVE)
UJNIT I_
9 148FOO7 153A CHECK VALVE YESIACVE 10 148F008 153A STANDBY LQUID CONTROL INJ ISO VALVE YES PASSIVE 13 1 E219 153A SBLC STORAGE TANK ELECTRIC HEATER A YES ACTIVE 14 IE220 153A S8LC STORAGE TANK ELECTRIC HEATER B YES I ACTIVE 18 HS14804 153A SBLC MANUAL INITIATION SWITCH YESIACTIVE 19 HVI48FOOB 153A SBLC OB INJECTION VALVE YESI
_A_
_E UNIT 2 S
248F007 253A CHECK VALVE YES I ACTIVE 10 248F008 253A STANDBY LIQUID CONTROL IW ISO VALVE YES I PASSIVE 13 2E219 253A SBLC STORAGE TANK ELECTRIC HEATER A YES / ACMIVEE 14 2E220 253A SBLC STORAGE TANK ELECTRIC HEATER B YESI ACTIVE 18HS248D4 253A SBLC MANUAL INITIATION SWITCH YES I ACTIVE 19 HV248F006 253A SBLC OB INJECTION VALVE YES ACTIVE The components shown in Table 4.4.2 fall under the definition of single failure criteria i.e., aa occurrence that results in the loss of capability of a component to perform its intended safety function." In order to take credit for the application of the SBLC System to the suppression pool pH function these components must be evaluated for their low risk failure probability an judged acceptable. This is done for each component including the guidelines (a)-(e) discuss in Section 4.1 above as well as, the following evaluation criteria:
a) component's design (seismic, ASME, etc.), inspection and procurement program b) testing and maintenance program c) industry historical performance of these components d)
SSES plant experience with these components e) power source The argument and justification for the low risk of failure of each component is presented in detail in the following Section 4.5.
V Thkm arneimftn+ onti igmc~tifio-atien forw hm tl'%%aa rioL. ~4 faila.ri Mckf
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PP&L CALCULATION SHEET Det.
PROJECT Caic. No.
EC-053-1012 Assessment of SBLC Rev. No.
Designed By G Kouail System for Suppression Checked By Pool pH Control Sh. No.
38-of 138-4.5 Justification for Low Risk Failure Probability The argument and justification for the low risk of failure of each component identified in Tabl 4.4.2 follows.
4.5.1 CHECK VALVE -1 (2)48FO07(1)
The possibility of SBLC System Isolation Check Valve 1(2)48-F007 having a single failure (falls closed-preventing flow) when called to service of system injection into the Reactor Ves el is evaluated consequently. The valve is a high reliability component whose potential failure i very low and this premise is justified below.
The objective argument against a single failure (fails closed) probability of the SBLC Injectio check valve is based on the in-place safeguards and the quality applied to the valve's operation. First, the valve has been procured as ASME,Section III, Class 1 safety-related component, is periodically tested and inspected, and has demonstrated historical performan e with no failures. Second, an extensive search of INPO (EPIX, NPRDS - Attachment No. 2) and Susquehanna (NIMS) databases revealed no failures (to open or close) of this and simil r valves. The INPO, EPIX and NPRDS databases were searched on all BWR (including Susquehanna) plants on key words such as: Standby Liquid Control (SBLC), Maintenance Rule applicability and for the particular valve (by function, type and manufacturer).
All records reviewed show only requirement for routine maintenance and minor correction to lea rate. The Susquehanna site system engineer likewise confirmed this result through in-plant performance history (Attachment No. 3).
The results of this evaluation show the potential for failure of the valve is very low based on 1e quality as established by the component's procurement as an ASME, Section ll, Class 1 safety-related valve, its periodic testing and inspection (References 6.1 and 6.14), and historical performance of the component (NIMS Data Base Maintenancl Record, INPO EPI, NPRDS).
Table 4.5.1 further summarizes the important attributes, which serve as additional testimony of the valve's reliability against a potential single failure occurrence.
j) Terminology is used throughout to designate Unit #1 and #2 valves and components.
V.
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PROJECT Calc. No.
EC 1012 Assessment of SBLC Rev. No.
Designed By, GKowal System for Suppression Checked By Pool pH Control Sh. No.
39-of 138-TABLE 4.51 Valve Component Data Sheet VALVE NO 1 (2)48-F007 REFERENCES AlTRIBUTE E
TYPE
}Lit Check - I Y Inch Y Type 6.10 MANUFACTURER Borg - Warner 6.10 NORMAL Valve In closed position. Ultrasonic flow 6.2, 6.3,6.6,6.13,6.14 OPERATION unit FE-1 (2)4806 would Indicate If valve fails closed on system start.
QUALITY YES 6.15,6.16 ASSURANCE 10CFR50, APPENDIX B REQUIREMENT o CLASS YES 6.15,6.16 Quality Group A, per RG 1.26 SAFETY 1 - Per ANSI, N212 6.15,6.16 CLASSIFICATION ASME ASME Section III, Class 1 6.15, 6.16
- ASECIll, NB 6.15, 6.16 MAINTENANCE YES 6.15, 6.16 RULE SEISMIC CATEGORY I, SSE 6.15, 6.16 CATEGORY Although, acknowledging that a single failure possibility exists to open the Infection check valve, the above arguments accentuate that the potential for failure is very low. This is bas on the quality as established by the valve's procurement as a safety-related valve, its testing and inspection and historical performance.
4.5.2 SBLC MANUAL INITIATION SWITCH. HS1(2)4804 As mentioned above, one of the two components identified,Athe main control room selector switch HS1 (2)4804 is also considered for the single failure criteria. Similar to the check valve the hand switch is likewise a high reliability component whose potential for failure is very low In the event that system operation is required, the operator must place Keylock Hand Switch HS-14804, SBLC MANUAL INITIATION on Panel 1C601 to the START position. This switch of the maintained contact type, and in the START position, acts to close contacts that energi, is
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PP&L CALCULATION SHEET PROJECT Caic. No.
EC 053-1012
. Assessment of SBLC Rev. No.
Designed By a Kowal System for Suppression Checked By Pool pH Control Sh. No.
40- of 138-both the 'A' and ABE SBLC Pump start relays and the K2 and K6 relays. The pumps will continue to run until stopped by the Control Room operator.
The Hand Switch is a high reliability component at a very accessible location and whose fail is very unlikely. This switch is of the maintained cortact type (passive) and is turned on manually. In case of remote possibility of failure of this switch, an available option allows access to the back panel where it could be easily replaced (or bypassed) in enough time to start system initiation.
Table 4.5.2 lists some important attributes, which serve as additional testimony of the switch' reliability against a potential single failure occurrence.
TABLE 4.5.2 Key Locked Hand Switch Component Data Sheet re s
VALVE NO HS1(2)4804 REFERENCES ATTRIBUTE TYPE Key Locked Hand Switch 6.6, 6.16 MANUFACTURER General Electric 6.7 NORMAL Maintained contact type switch. Operator 6.2, 63,6.16 OPERATION must place switch on Panel 1 (2)C601 to the START position to energize relays to start pumps.
EO NO 6.15,6.16 QUALITY YES 6.15,6.16 ASSURANCE 10CFR50, APPENDIX B REQUIREMENT 0 CLASS YES 6.15, 6.16 Ouallty Group A, per RG 1.26 SAFETY 1 - Per ANSI, N212 6.15, 6.16 CLASSIFICATION ASME No 6.15,6.16 ASEC No 6.15,6.16 MAINTENANCE YES 6.15,6.16 RULE SEISMIC CATEGORY I, SSE 6.15,6.16 CATEGORY The results show the Hand Switch HS 1(2)4804 is a high reliability component, at a very accessible location and whose failure is very improbable and would not prevent the SBLC System from performing its intended function.
The results show the Hand Switch HS 1(2)4804 is a high reliability component, at a very
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EC-053-1012 Assessment of SBLC Rev. No.
Designed By G Kowal System for Suppression CheckedE Pool pH Control Sh. No.
441 of 138-4.5.3 STANDBY LIQUID CONTROL INJ ISO VALVE - 1(2)48F008: SBLC OB INJECTION VALVE HV1 (2)F006 The possibility of SBLC System Isolation Valves HV 1 (2)48-F006 and 1 (2)48-F008 experiencing a single failure (fail closed) when called to service is evaluated consequently.
Even though the single failure criteria applies to the containment isolation valves, the valves are very high reliability components whose potential failure is very small.
The objective argument against a single failure (fails closed) probability of the SBLC Injectio valves is based on the in-place safeguards and the quality applied to the valves' operation.
First, the valves have been procured as ASME, Section l1l, Class I safety-related, are periodically tested and inspected, and have demonstrated historical performance of their reliability. Second, from safety consideration, valve HV-1 (2)48F006 has a keylock switch an will annunciate on Control Panel C601 if the switch is in CLOSE position or if the valve is NC T FULLY OPEN. Similarly, valve 1 (2)48-F0O8 is LOCKED OPEN and its' position indication is shown on Control Panel C601.
A detailed search of the NIMS Data Base shows only routine maintenance requirement of th valves and minor corrections to instrumentation. There has not been an incident where eithr valve closed spuriously or had a false indication of being open or closed.
The results of this evaluation show the potential for failure of the valve is very low based on 1 We quality as established by the component's procurement as an ASME,Section III, Class 1 safety-related valve, its periodic testing and inspection (References 6.13, 6.14), and histori I performance of the component (NIMS Data Base Maintenance Record and INPO - EPIX, NPRDS).
Table 4.5 further summarizes the important attributes, which are additional proof of the valve3' reliability and safety against a single failure occurrence.
0 w
PP&L CALCULATION SHEET PROJECT Calc. No.
EF-053-1012 Assessment of SBLC Rev. No.
Designed By.G KowaL System for Suppression Checked By Pool pH Control Sh. No.
42-of 139-TABLE 4.5.3 VALVE NO HV 1 (2)48-FOO6 1 (2)48-FOO8 REFERENCES ATTRIBUE TYPE YARWAY-1 1/2 MOV Bor -Warner - 1 1/2' GT 6.7,620, 6.21 NORMAL Position Switch ZS-12.
Locked open manual 6.4,6.6.6.7,6.11, OPERATION Alarm if valve not fully open injection. Position indication 6.12 (AR-107.D03). Displayed displayed on 1(2)C601.
on 1(2)C601 Powered by 1(2)Y216.
Powered by I1(2)B236.
QUALITY YES YES 6.15,6.16 ASSURANCE 10CFR50, APPENDIX B 10CFR50, APPENDIX B REQUIREMENT 0 CLASS YES YES 6.15.6.16 Quality Group A, per RG Quality Group A, per RG 1.26 1.26 SAFETY 1 - Per ANSI, N212 1 -Per ANSI, N212 6.15, 6.16 CLASSiFICATION ASME ASME Section III, Class 1 ASME Section III, Class 1 6.15, 6.16 ASEC III, NB III, NB 6.15 6.16 MAINTENANCE YES YES 6.15,6.16 RULE SEISMIC CATEGORY I, SSE CATEGORY I, SSE 6.15,6.16 CATEGORY Acknowledging the possibility of a single failure to close one of the two SBLC injection valve-the above argument accentuates that the pote'ntial for failure is very low. This is based on the quality as established by the valves' procurement as safety-related valves, their testing a inspection, and their historical performance.
4.5.4 SBLC STORAGE TANK ELECTRIC HEATERS A. B - 1(2)E219. 1(2)E220 Table 4.4.2 also lists SBLC Storage Tank Heater A (1 (2)E219) and Heater B (1 (2)E220) as potential compo ients for single failure. Their function is maintaining a minimum storage tani temperature to I Prevent the sodium pentaborate solution from precipitating out of solution; thereby, rendering the system incapable of performing its design functions. The heaters are active components and are somewhat redundant which is best explained by their respective function. Storage tank heater A" is a 10 kW heater powered from 480 VAC MCC 1 (2)B236.
This heater operates to automatically maintain solution temperature above the precipitation point, and can be removed for maintenance/replacement without draining the storage tank.
active components and are somewhat redundant which is best explained by their respective
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PROJECT Catc. No.
EC 053-1012 Assessment of SBLC Rev. No.
Designed By G Koaal System for Suppression Checked By Pool pH Control Sh. No.
43 of 13&-
Storage Tank Heater "B" is used to elevate the temperature during chemical addition to increase the solubility of the sodium pentaborate in water. This is necessary because the mixing of sodium pentaborate and water is an endothermic reaction, which draws heat from the system. This heater is a 40 kW heater powered from 480 VAC MCC 1 (2)B236.
As is evident above, the single failure criteria impacts the heaters since they are powered frc the same power source i.e., 480 VAC MCC 1 (2)B236.
Since regulatory criteria dictate that SBLC System initiation post LOCA is completed by 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, an option is available for supplying power to the heaters from Diesel Generator A or C (References 6.8 and 6.9) on loss of the AC Bus. However, should backup power not be available for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the need for maintaining the minimum storage tank temperat re is still necessary to prevent sodium pentaborate from precipitating out of solution; thereby rendering the system not applicable of performing the AST function. Therefore, a calculatio was performed to determine the transient cool-down rate of the tank's inventory over a 24 hc ur period with the heaters off. The solution temperature at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> confirmed it is still within V
design limits.
The stepped approach of the Calculation is presented as follows:
AssumptlonsAnput:
Input data for the Storage Tank's normal operating temperature limits were obtained from References 6.2 through 6.5. These were used in setting the initial conditions.
- With the heater control switch in AUTO, the 'A' heater is controlled by a temperature indicating controller to maintain tank temperature between 850F and 950F.
- The high temperature alarm activates at a tank temperature of 1 100F, increasing and the low temperature alarm activates at 800F, decreasing. The low temperature alarm set at 800F ensures action can be taken prior to tank temperature decreasing below the saturation temperature of the solution.
- Technical Specification 3.1.7 requires a minimum sodium pentaborate concentration of 1B.
6 weight percent limit. From Figure 3.1.7.2 of the Technical Specification at that concentration an acceptable operating range temperature of 660F is required.
The SBLC Storage Tank geometry and dimensions were obtained from Reference 6.22.
It was determined a standard electrical analogy method for transient conduction is applicabl for this situation. Equations and parameters used were obtained from Reference 6.23, Sections 34 and 35.
The tank's sodium pentaborate solution was assumed to have properties of ordinary water.
V Ace ---
I b-.
Sections 34 and 35.
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PROJECT Caic. No.
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Designed By G KowaL System for Suppression Checked By Pool pH Control Sh. No.
44 of 138-MethodologY:
Using the above input and assumptions, conservative evaluations were performed to determine temperature decay (cool-down) in the Standby Liquid Control System Storage Tai in the event of loss of both heaters.
First, the geometry and dimensions of the tank used in the analysis is illustrated in the sketcl below: Data is obtained from References 6.22 and 6.41.
Tank ID = 9 ft Tank OD = 9.03 ft Wall thickness = 3/16" Water level = 4587 gal
. 11 5.6 = 9.63 ft (low)
.-120
-Water level = 4897 gal
..123.5" = 10.3 ft (high)
.i...j >.I Tank insulation = 1" Calcium silicate
,....SBLC STORAGE ANK' Second, the approach referenced for transient conduction is obtained from Reference 6.23 is included below. The method used to determine the time dependent fluid temperature in t tank is the Lumped Parameter Electrical Analogy Method which Is described below.
LUMPED PARAMETER ELECTRICAL ANALOGY METHOD Tt= T. + (To - T.) exp (-4Ce Re)
(1)
Where:
Ce = cppV Re= I /hA, Tt= medium temperature at time -t, OF To= initial medium temperature, OF T= bulk outside ambient temperature, 'F W
Tt = medium temperature at time -t, OF
PP&L CALCULATION SHEET D~pt PROJECT Caic. No.
EC 053-1012 Assessment of SBLC Rev. No.
Designed By G. Kanwal System for Suppression Checked By Pool pH Control Sh. No.
4-of 13&-
T.'= surface temperature, OF k = thermal conductivity, BtuI(hr-ft- 0F) t =time, hr p = mass density, lb/ft3 = 62.3 Cp= specific heat, Btullbm- 'F = 0.999 Lc = characteristic length, ft
(= VIAs)
V = volume, ft3 As = surface area, ft2 h = film coefficient, Btu/(hr-ft2-IF)
= 0.29{(Ts - T.)/L4i 025 (for a vertical cylinder geometry), (applicable for GrPr = 10 4 to 109)
First, the confirmation of the Rayleigh Number (GrPr product) has to be made in order to permit the use of the cylinder film coefficient.
The Prandtl Number is defined as follows:
Pr = cpl/k Where ji = viscosity, lb/hr-ft And the Grashof Number is, Gr = (L 3gpp2 (Tr T-))/p2 Where g = gravitational acceleration, ftVhr2 i = volumetric coefficient of expansion, 11 0R Assuming conservative conditions for T$,= 950F and T. = 60OF, the Grashof Number is conservatively determined using T. (601F), (Reference 6.23, Appendix 35.C)
Pr =0.72 g9Pm 2/l 2 2.58 x 106 (interpolated) 1=
(V/A&)3 = (rr2h/2Trrh)
= (r/2)3 = ((9.03 fV2)/2)3 = 11.5 feet3 Note that the surface area of the top and bottom of the tank are neglected. The bottom of th tank is connected to concrete and will insulate the tank from heat loss. Additionally, the wat does not go to the top of the tank therefore the inside lid of the tank will be exposed to air. T heat transfer through the lid will be very small and is neglected.
Therefore, the Rayleigh Number (GrPr product) is, GrPr = 1 1.5x(2.58 x 106)x(95 - 60)x 0.72 = 7.48 E+08 Therefore, the Rayleigh Number (GrPr product) is,
PP&L CALCULATION SHEET D t PROJECT Catc. No.
EC -053-1012 Assessment of SBLC Rev. No.
Designed By G Kowa!
System for Suppression Checked B
y-Pool pH Control Sh. No.
46 of 138-in addition to confirming the Rayleigh number, Reference 6.23 states that d/L > 35/(Gr)0.25.
This confirmation is performed below.
9.03/2.26 ? 35/(1.04 x 109)° 25 OR 4.0 x 0.2 Which satisfies the criteria of using the above film coefficient: 0.29[(T. - T)/b}° 25 Utilizing Equation 1 above i.e., Tt = T + (T. - T.) exp (-t/ReCe), with the following input, a parametric study of the tank temperature with time was estimated.
From above.
Co = CPPV (Equivalent thermal resistance)
Re = 1 /hAs (Equivalent thermal resistance)
The following range of values were used in the analysis, To = initial medium (sodium pentaborate) temperature, OF
= range of 950F to 800F (950F taken conservatively as the upper normal operating temperature)
T. = bulk outside ambient temperature, 'F
= range of 80OF to 600F (assumed)
V = minimum volume, ft3 = 4587 gal x 0.13368 ft3/gal (see above calculation and sketch)
=613 ft3 Note the minimum tank volume was conservatively used since it lowers the amount of ma to be cooled.
As = surface area, ft2 = 6.28x4.515'x9.633' (see above calculation and sketch above)
= 273 ft2 h = 0.29{(Ts - T.)/IL)P0 25 (Variable h) (Reference 6.23, page 35-5)
(the medium temperature is assumed to be the surface temperature).
Also, a constant heat transfer coefficient of 2.0 Btu/hr-ft-OF was also used for some ca Therefore, substituting values C. = cppV = (0.999) (62.3) (613) = 38,151 I nererure, wuumitnumiy Vlwuti
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47-of 138-.
Re = 1 /hAs = 1 / (0.29{(Ts - T.)/L0)}0 25 ) (273) = 1 I 79.2 {(Ts - T.4) Lc10 25
= 1179.2 ((Ts - T.)/2.26)25 = 1/64.6(Te - T.) 0 25 = 0.01 55(Te - T-)4° Or C. X Re = (38,151)(0.01 55(T. - T.)4 25) = 591.3(Ts - T.)@ 25 Substituting the above parameters into Equation 1, Tt = T. + (T. - TV) exp (-tIC, Re)
= T.. + (To - T.) exp (-t / (591.3/ (T, - T.0)0 25)
= T. + (To - T.) exp (-t(.00169({(T. - T.))025)))
(2)
Equation (2) above was used to produce the transient results of temperature in the tank usin the transient film coefficient.
Note that for all cases the tank insulation was conservatively neglected since the insulation v ill limit the temperature decrease.
4.5.4.1 Constant Heat Transfer Coefficient Analysis:
Given the uncertainty of the air flow patterns around the tank a case was run with a constant heat transfer coefficient. A value of 6.0 Btu/hr ft2 OF was chosen since it is representative of heat transfer coefficient for a 15 mph wind speed. This value will obviously bound any conditions that would exist in the reactor building.
The calculation was performed in a manner similar to the methodology described above exc pt the value of Re simply became 1IhAs = 1/(6)(273) = 6.105 x 104 A number of parametric runs were performed for the variable input values discussed in Secti n 4.5.4 above. The results were generated using an EXCEL spreadsheet and are presented below in Table 4.5.4. The spreadsheet results are included as Attachment 5. Table 4.5.4 results use the variable (h) and a constant (h) = 6.0 Btu/hr-ft2. Only the two most challengin cases are presented.
- r
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48-of 138-TABLE 4.5.4 -Cool-down Temperatures Using a Variable and Constant(h)
Variable (h)
Constant (h)
TIME (h = 6.0)
(hr) 80 Inside,
80 Inside, 60 Outside 60 Outside 0
8° 80 0.5 79.96429 79.57518 1
79.92868 79.15938 1.5 79.89316 78.75241 2
79.85774 78.35409 2.S 79.82242 77.96422 3
79.78718 77.58264 3.5 79.75204 77.20917 4
79.717 76.84363 4.5 79.68205 76.48585 5
79.64719 76.13567 5.5 79.61242 75.79293 6
79.57774 75.45747 6.5 79.54316 75.12913 7
79.50867 74.80777 7.5 79.47427 74.49324 8
79.43996 74.18539 8.5 79.40574 73.88407 9
79.37161 73.58916 9.5 79.33757 73.30051 10 79.30362 73.01799 11 7923566 72A7083 12 79.16836 71.94667 13 79.10141 71.44453 14 79.03481 70.96351 15 78.96855 70.5027 16 78.90264 70.06126 17 78.83707 69.63837 18 78.77184 69.23326 19 78.70695 68.84518 20 78.6424 68.4734 21 78.57817 68.11726 22 78.51428 67.77608 23 78.45072 67.44924 24 78.38748 67.13614 la
PP&L CALCULATION SHEET Q
L PROJECT Calc. No.
Er-053 1012 Assessment of SBLC Rev. No.
Designed By G KJowaL-System for Suppression Checked By Pool pH Control Sh. No.
4-of 138-It is evident above that the initial and outside temperature conditions are very impacting. The most rapid cool down occurs with the assumption of a constant film coefficient (h = 6.0). However, the Technical Specification limit (66 OF) Is not exceeded over the entire 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with either coefficient.
5.0 RESULTS Acknowledging that a single failure of one of the components listed in Table 4.4.2 is remotel possible, the above arguments accentuate that the potential for failure is very low. This is based on the quality as established by the components' procurement as safety-related valve their testing and inspection, their historical performance and as in the case of the heaters, availability of redundant power sources.
0 W
PP&L CALCULATION SHEET PROJECT Caic. No.
E C- 0 5 3-301-2 Assessment of SBLC Rev. No.
Designed By-G KowaL System for Suppression Checked By Pool pH Control Sh. No.
50- of 138
6.0 REFERENCES
6.1 RG 1.183, uAlternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", Regulatory Guide, U.S. N.R.C.
6.2 TM-OP-053-ST, "Standby Liquid Control", Systems Training Student Text, Rev. 03, 4/25/02.
6.3 DBD-042, "Standby Liquid Control System", Rev. 2.
6.4 AR-107-001, 'CRD, SLC, DRYWELL SUMPS 1C601," Annunciator Procedure.
6.5 OP-153-001, "Standby Liquid Control System", Rev. 21.
6.6 Drawing M-(2)148, "Unit 1 P&ID, Standby Liquid Control," Rev. 34.
6.7 Drawing D107315, Sht.3, 4, 7, 8, Schematic Diagram-"Standby Liquid Control System", Rev.
17 6.8 Drawing Dl 07150, Sht. 1, Susquehanna S.E.S. Unit 1 & 2, "Single Line Diagram Station", R v.
30.
6.9 Drawing Dl107159, Sht. 1, "Single Line Meter & Relay Diagram, 125VDC, 25OVDC & 120VA Systems", Unit 1 & 2,Rev. 23.
6.10 Drawing FF110470, Sh. 1001, "Valve Assembly lift Check - 1 1/2 inch Y Type." Borg - Warn r Corp.
'11 Proc. No. CL-1 53-0011, "Standby Liquid Control System", Electrical, Rev. 7.
6.12 Proc. No. CL-153-0013, "Standby Liquid Control System", Mechanical -Containment, Rev.
6.13 SO-153-003, "24 Month SBLC Operability", Rev. 20.
6.14 SO-153-004, "Quarterly SBLC Flow Verification", Rev 30.
6.15 Susquehanna Station FSAR Table 3.2-1.
6.16 Susquehanna Station Nuclear Information Management System (NIMS).
6.17 Susquehanna Station Site Performance & Maintenance History - System Engineer Ian C.
Missien).
6.18 INPO computer available databases, EPIX and NPRDS.
6.19 Deleted.
6.20 Drawing 74680 (FF110470), "Valve Assembly - 1 'Iz inch Gate. Cres." Borg - Wamer Corp.
6.21 Drawing FF110140, Sht. 1001,"1 1/2" Yarway Welbond Valve With Limitorque Electric Motor Actuator-Stop Check Design." Rev. 8.
6.22 Drawing FF121010, Sh. 2801, 2802, Standby Liquid Control Storage Tank, General Electric Co.
6.23 Undeburg, Michael R., "Mechanical Engineering Reference Manual for the PE Exam",
Eleventh Edition. Professional Publications. Inc., Belmont, CA.
6.24 Drawing D107315, Sht. 1, 2, 5, 6 Schematic Diagram-"Standby Liquid Control System".
6.25 Drawing D107315, Sht. 2, "Emerg. Core CIg. Benchboard, 1C601", Unit 1.
6.26 Drawing Ml -C41-36, "Elem. Diag.-Standby Liquid Control", Sht. 1, 2, 3.
6.27 Drawing M1 -C41-31, 'FCO.-Standby Liquid Control", Sht. 1.
'28 PLA 2222, "Conformance to Regulatory Guide 1.97, Rev. 2", (93309710001).
(29 Calculation EC-030-1007, " Transient Temperature Response of CS with HVAC - Normal an 1 Accident Conditions".
6.30 Drawing A-512, "Shielding and Radiation Zoning Drawing, Control Building, EL 729'-1".
6.31 NIMS Data Base I 29 Calculation EC-030-1007, " Transient Temperature Response of CS with HVAC - Normal an
PP&L CALCULATION SHEET PROJECT Calc. No.
EC-053-1 012 Assessment of SBLC Rev. No.
Designed By G Kowal System for Suppression Checked By Pool pH Control Sh. No.
54-of 138 6.32 Drawing C-1815, Sheet 9, "SSES Unit I& 2 Reactor Building Equipment Qualification Harsh Environment Zones.
6.33 Drawing C-1 815, Sheet 1, "SSES Unit 1& 2 Primary Containment Equipment Qualification Harsh Environment Zones 6.34 General Electric's "Nuclear Products Quality Assurance Manual".
6.35 Yarway's "Nuclear Products Quality Assurance Manual" 6.37 Borg-Warner's "Nuclear Products Quality Assurance Manualr 6.38 Drawing J-653, Sheet 53, Rev. 7, "SBLC Storage Tank".
6.39 Email from Ian Missien (site engineer) based on a walkdown and measurement of the insulation thickness.
6.40 Calculation EC-RADN-1 004, " Equipment Qualification Radiation Doses for Selected Zones Due to Hydrogen Injection", Appendix G. (Values in this calculation estimated based on TID 6.41 Drawing J-653 Sheet 53 (PPL Drawing #A-103785, Sheet 53) "SBLC Storage Tank".
V
EC-53-1012 Revision 0 Pave 52 of 138 PP&L CALCULATION SHEET C
PROJECT Calc. No.
EC 053-1012 Assessment of SBLC Rev. No.
0 Designed By GAKowal-System for Suppression Checked By Pool pH Control Sh. No.
4-of 68-ATTACHMENT NO. 1 SBLC UNIT 1 AND UNIT2 COMPONENT LUST w
EC-053-1012 Revision 0 Paoe 53 01138 SLC STANDBY LIQUID CONTROL COMPONENT LIST NXL0l-U1 153 SLC STANDBY LIQUID CONTROL F014813 153 SLC STANDBY LIQUID CONTROL 1
F014814 153 SLC STANDBY LIQUID CONTROL 1
FV14814 153 SLC STANDBY LIQUID CONTROL 1
NXF01-U1 153 SLC STANDBY LIQUID CONTROL 1
148013 153 ISLC STANDBY LIQUID CONTROL 1
SPDCB1O1H23 153A ISLC STANDBY LIQUID CONTROL 1
148F002A 153A iSLC STANDBY LIQUID CONTROL 1
148F014 153A
!sLC STANDBY LIQUID CONTROL F114814 153A ISLC STANDBY LIQUID CONTROL HSS14802 153A ISLC STANDBY LIQUID CONTROL 1
JBD-178 153A SLC STANDBY LIQUID CONTROL 1
LIC41 IR601 153A SLC STANDBY LIQUID CONTROL 1
PIC41 1R003 153A SLC STANDBY LIQUID CONTROL 1'
SPJCD107H9 153A SLC STANDBY LIQUID CONTROL 1,
SPDCBIOIH2015 153A SLC STANDBY LIQUID CONTROL SPHCB1O5H2001 153A SLC STANDBY LIQUID CONTROL 11 JT207A 153A SLC STANDBY LIQUID CONTROL SPDCA106H19 153A SLC STANDBY LIQUID CONTROL 1
P1148R003-R2 153A SLC STANDBY LIQUID CONTROL 1__
1T207B 153A SLC STANDBY LIQUID CONTROL 1
SPDCB101Hi7 153A SLC STANDBY LIQUID CONTROL 1
SPDCB1 01 H201 0 153A ISLC STANDBY LIQUID CONTROL 148F002B 153A ISLC STANDBY LIQUID CONTROL 1
148F003B 153A
SPDCB10OH2 153A
'SLC STANDBY LIQUID CONTROL HCB105H9 153A SLC STANDBY LIQUID CONTROL 1
148015 153A iSLC STANDBY LIQUID CONTROL SPDCB101H31 153A ISLC STANDBY LIQUID CONTROL 1.
SPHCDl3lH3 153A SLC STANDBY LIQUID CONTROL 1
SPJBD1O45H2000 153A SLC STANDBY LIQUID CONTROL 1
SPJCD107H1O 153A SLC STANDBY LIQUID CONTROL IC-PI148207B-153A SLC STANDBY LIQUID CONTROL 1_
E 148005 153A SLC STANDBY LIQUID CONTROL 11 HCB105H2 153A SLC STANDBY LIQUID CONTROL 1
DCA-106 153A SLC STANDBY LIQUID CONTROL 1
SPDCB1O1H29 153A SLC STANDBY LIQUID CONTROL 1
LG14803 153A SLC STANDBY LIQUID CONTROL SPDCB1O1H14 153A SLC STANDBY LIQUID CONTROL 1
ZS14806 153A ISLC STANDBY LIQUID CONTROL TAHL14810 153A
!SLC STANDBY LIQUID CONTROL SPHBD1 01 H2008 1 53A
!SLC STANDBY LIQUID CONTROL 1:
SPDCB1O1H6 153A -SLC STANDBY LIQUID CONTROL 1,
SPDCB1O1H3S 153A iSIC STANDBY LIQUID CONTROL 1_
SPDCB01H2050 153A TSLC STANDBY LIQUID CONTROL 1E SPDCB1OI H2O 153A E
_1 SPDCB10iH20 153A ISLC STANDBY LIQUID CONTROL 1
SPDCBIOIH61 153A SLC STANDBY LIQUID CONTROL 1
LISH 14812 153A SLC STANDBY LIQUID CONTROL 1
DCB-101 153A SLC STANDBY LIQUID CONTROL 1
SPDCBl 01H44 1 53A SLC STANDBY LIQUID CONTROL 1
HCB105H8 153A SLC STANDBY LIQUID CONTROL HS14808B 153A SLC STANDBY LIQUID CONTROL HV148F006/ACT 153A ISLC STANDBY LIQUID CONTROL 1
IHS148088 1153A ISLG S IANUBY LIUUID NIUL 11 I HVI 4BFOOBIACT 1153A ISLC STANDBY LIQUID CONTROL I
V lHV148F00G/ACT 1153A I SLC STANDBY LIOUID CONTROL I
EC-053-io12 ReVisbon 0 Pace 54 et 138 P1148R003-R1 153A SLC STANDBY LIQUID CONTROL 1
SPDCB101 Hi 153A SLC STANDBY LIQUID CONTROL 1
HCB105H1 153A SLC STANDBY LIQUID CONTROL 1
1 SPDCB101 H34 153A SLC STANDBY LIQUID CONTROL 1
F114806 153A SLC STANDBY LIQUID CONTROL 1
SPJBDIO45H2001 153A SLC STANDBY LIQUID CONTROL XY14806 153A SLC STANDBY LIQUID CONTROL 1
148010 153A SLC STANDBY LIQUID CONTROL 148F031 153A SLC STANDBY LIQUID CONTROL 1
1E219 153A SLC STANDBY LIQUID CONTROL 1
DCA-206 153A SLC STANDBY LIQUID CONTROL 1
SPDCB10lH32 153A SLC STANDBY LIQUID CONTROL 1
SPDCB1l1H24 153A SLC STANDBY LIQUID CONTROL 1
1P2088 153A SLC STANDBY LIQUID CONTROL 1
!148F017 1153A SLC STANDBY LIQUID CONTROL 1
148F015
!153A SC STANDBY LIQUID CONTROL TSHLC411N003 153A SLC STANDBY LIQUID CONTROL 1
TEC41IN006 153A SLC STANDBY LIQUID CONTROL__
1 SPHCD13IH1 153A SLC STANDBY LIQUID CONTROL SPDCB101H4 153A SLC STANDBY LIQUID CONTROL 1
SPDCB101H33 153A SLC STANDBY LIQUID CONTROL SPDCBIOIHI1 153A SLC STANDBY LIQUID CONTROL 1
SPDCA106H8 153A SLC STANDBY LIQUID CONTROL 1
SPDCA106HI7 153A SLC STANDBY LIQUID CONTROL 1
,148016 153A SLC STANDBY LIQUID CONTROL 1
TSHL14810 153A SLC STANDBY LIQUID CONTROL 1
ISPDCB010H7 153A SLC STANDBY LIQUID CONTROL 1
jHS14806 153A SLC STANDBY LIQUID CONTROL 1
SPDCB101H21 153A SLC STANDBY LIQUID CONTROL 1
SPDCB1O1H2016 153A SLC STANDBY LIQUID CONTROL I
SPDCB101HI2 1153A SLC STANDBY LIQUID CONTROL I
Pl148207A 153A SLC STANDBY LIQUID CONTROL 1
JBD181HI 153A SLC STANDBY LIQUID CONTROL 1
i.JBD-1045 153A SLC STANDBY LIQUID CONTROL 1
,HS14804 153A SLC STANDBY LIQUID CONTROL i
1 IHCB105H4 153A SLC STANDBY LIQUID CONTROL 1
'FT14806 153A SLC STANDBY LIQUID CONTROL 1
JDCB-201 153A SLC STANDBY LIQUID CONTROL 1
,1T203 153A SLC STANDBY LIQUID CONTROL 1
'1E220 153A SLC STANDBY LIQUID CONTROL 1
I148F033A 1153A SLC STANDBY LIQUID CONTROL 1
XYC41 I M600A 1 53A SLC STANDBY LIQUID CONTROL 148012
'153A SLC STANDBY LIQUID CONTROL 1
WV148F006 1153A SLC STANDBY LIQUID CONTROL FICC41I R004 j 153A SLC STANDBY LIQUID CONTROL 1
148F003A i153A SLC STANDBY LIQUID CONTROL 1
148F001 153A SLC STANDBY LIQUID CONTROL
,1 1148009 153A SLC STANDBY LIQUID CONTROL 1__
'148008 153A SLC STANDBY LIQUID CONTROL 1
!148002 153A SLC STANDBY LIQUID CONTROL 1
ITICC41 I R002 153A SLC STANDBY LIQUID CONTROL 1
iTE14810 153A SLC STANDBY LIQUID CONTROL 1
SPHCD131H2 153A SLC STANDBY LIQUID CONTROL
{_
1__
SPHCB105H4
! 153A SLC STANDBY LIQUID CONTROL -
_I _1 SPDCB1O0H30 1153A SLC STANDBY LIQUID CONTROL i_
t SPDCB1O1H2008 153A SLC STANDBY LIQUID CONTROL I
1 HS14808A 1153A SLC STANDBY LIQUID CONTROL 1
HS14808A 1153A SC STANDBY LIQUID CONTROL 1
V
EC-053-1Of 2 Revrsfon a Paoe 55 of 138 P1148207B 153A SLC STANDBY LIQUID CONTROL 1
SPDCA106H2005 153A SLC STANDBY LIQUID CONTROL i
SPHCB105H3 153A SLC STANDBY LIQUID CONTROL 1
PSV148FO29A 153A SLC STANDBY LIQUID CONTROL 1
ZS14808L 153A SLC STANDBY LIQUID CONTROL 1
148003 n
153A SLC STANDBY LIQUID CONTROL 1
SPDCA106HI4=
153A SLC STANDBY LIQUID CONTROL 1
148FO04B 153A SLC STANDBY LIQUID CONTROL 1
148F024 153A SLC STANDBY LIQUID CONTROL 1
SPDCA106H35 153A SLC STANDBY LIQUID CONTROL 1
SPDCBf1OH1O 153A SLC STANDBY LIQUID CONTROL 1
SPDCBI 01 H22 153A SLC STANDBY LIQUID CONTROL 1
ISPDCBI10H5 153A SLC STANDBY LIQUID CONTROL 1
IC-PI148207A-153A SLC STANDBY LIQUID CONTROL 1
.SPDCB011H2013 153A SLC STANDBY IUQUID CONTROL 1
1148018
_153A SLC STANDBY LIQUID CONTROL 1
tSPDCB1O1H15
- 153A SLC STANDBY LIQUID CONTROL 1
148F012 153A SLC STANDBY LIQUID CONTROL 1
FE14806 153A SLC STANDBY LIQUID CONTROL I
148F033B 153A SLC STANDBY LIQUID CONTROL 1
1148F021 153A SLC STANDBY LIQUID CONTROL 1148FO18 153A SLC STANDBY LIQUID CONTROL 1
1480174 153A SLC STANDBY LIQUID CONTROL 1
IXA14804 153A SLC STANDBY LIQUID CONTROL 1
PCY1 481 1B 153A SLC STANDBY LIQUID CONTROL SPCCB181H1Bj 153A SLC STANDBY LIQUID CONTROL 153A SLC STANDBY LIQUID CONTROL t
SPDCA106H2006 1153A SLC STANDBY LIQUID CONTROL 1
IPT148N0O4-R2 1153A SLC STANDBY LIQUID CONTROL 1
iPT148NO04-RI
.153A SLC STANDBY LIQUID CONTROL 1
LAHL14801 153A SIC STANDBY LIQUID CONTROL 1
lP208A 153A SLC STANDBY LIQUID CONTROL 1
- ,148F026 153A SLC STANDBY LIQUID CONTROL 1
!148FC25 153A SLC STANDBY LIQUID CONTROL 1
ISPDCB1lOH8 1153A SLC STANDBY LIQUID CONTROL 1
.LIC411RO01 153A SLC STANDBY LIQUID CONTROL 1
!PSV148FD29B 153A SLC STANDBY LIQUID CONTROL 1
1148004 153A SLC STANDBY LIQUID CONTROL 1
IPCV14811C 153A SLC STANDBY LIQUID CONTROL 1
!TAHL14803 153A SLC STANDBY LIQUID CONTROL 1
SPHCB105H2 153A SLC STANDBY LIQUID CONTROL 1
SPHCB105H1I_
153A SLC STANDBY LIQUID CONTROL I
SPDCB1l1H28 153A SLC STANDBY LIQUID CONTROL =
1 PCV1481A 153A SLC STANDBY LIQUID CONTROL 1
SPDCA106HIO 153A SLC STANDBY LIQUID CONTROL 1
IT204 153A SLC STANDBY LIQUID CONTROL 1
LE14812 153A SLC STANDBY LIQUID CONTROL 1
1JBD-181 153A SLC STANDBY LIQUID CONTROL 1
'HCB105H11 153A SLC STANDBY LIQUID CONTROL 1
1148F016 153A SLC STANDBY LIQUID CONTROL 1
148F011 I
153A SLC STANDBY LIQUID CONTROL 1
148F008 153A SLC STANDBY LIQUID CONTROL
__1
- SPDCBi0lHI9 153A SLC STANDBY LIQUID CONTROL 1
1 SPDCB10IH2011 153A SLC STANDBY LIQUID CONTROL 1
1 SPHCB105H2002 1153A SIC STANDBY LIQUID CONTROL 1
LSHLC41I N600 1 53A SLC STANDBY LIQUID CONTROL
__1 1
3 5A I
TNBYLQI ONRL Li tHCD-131 153A SLC STANDBY LIQUID CONTROL !
tHC 131 153A 1SCTADYLQ, CN R8L I
-711 V
EC-053-10T2 Revision Paae 58 of I1S8 0
HCB105H7 153A SLC STANDBY LIQUID CONTROL 1
SPDCB101H9 153A SLC STANDBY LIQUID CONTROL 1
HCB-105 153A SLC STANDBY LIQUID CONTROL 1
LUIF114806 1153A SLC STANDBY LIQUID CONTROL 1
148019 153A SLC STANDBY LIQUID CONTROL 1
SPDCA106H16 153A SLC STANDBY LIQUID CONTROL 1
XYC41IM600B 153A SIC STANDBY LIQUID CONTROL HCB105H3 153A SLC STANDBY LIQUID CONTROL 1
SPHCB105H2000 153A SLC STANDBY LIQUID CONTROL l
1 SPDCB101H40 153A SLC STANDBY LIQUID CONTROL I
1 SPDCB1 01 H3 153A SLC STANDBY LIQUID CONTROL 1
_PPCB101 H2014_ 153A SLC STANDBY LIQUID CONTROL 1
SPDCB10IH2002.153A SIC STANDBY LIQUID CONTROL I
SPDCBIOIH1000 53A SLC STANDBY LIQUID CONTROL I
1 iPTC41N004 1153A SLC STANDBY LIQUID CONTROL I
1 148011 1153A SLC STANDBY LIQUID CONTROL I
1 JBD178H1 153A SSLC STANDBY LIQUID CONTROL i
SPDCB101H43 153A SLC STANDBY LIQUID CONTROL I
SPDCB101lH37 153A SLC STANDBY LIQUID CONTROL 1
148F027 153A SLC STANDBY LIQUID CONTROL I
LTC411NO01 153A SLC STANDBY LIQUID CONTROL I
SPDCA106H42 153A SLC STANDBY LIQUID CONTROL j
ESC411 K600 153A SLC STANDBY LIQUID CONTROL 1
ICOI I 153A SLC STANDBY LIQUID CONTROL I
148F007 153A SLC STANDBY LIQUID CONTROL 1
148007 153A SLC STANDBY LiQUID CONTROL 1
148006 153A SLC STANDBY LIQUID CONTROL
- I1 148001 153A SLC STANDBY LIQUID CONTROL I
I IZS14808U 153A SLC STANDBY LIQUID CONTROL 1
SPDCB101 H45 1 53A SLC STANDBY LIQUID CONTROL
_1I SPDCB101H39 1153A SLC STANDBY tlQUID CONTROL i_
1 l148FO04A 1153A SLC STANDBY LIQUID CONTROL I
!SPDCB1O1H2009 i153A SLC STANDBY LIQUID CONTROL 1
NXF01-U2 1253 SLC STANDBY LIQUID CONTROL 2
248013 1253 SLC STANDBY LIQUID CONTROL 2
FV24814 i253 SLC STANDBY LIQUID CONTROL 2
12CB253 1253 SC STANDBY LIQUID CONTROL 2
12CB254 253 SLC STANDBY LIQUID CONTROL 2
!F024814 253 SLC STANDBY LIQUID CONTROL 2
F024813 253 SLC DBY LIQUID CONTROL 2
NXL01-U2 253 SLC STANDBY LIQUID CONTROL 2
248F025 1253A SLC STANDBY LIQUID CONTROL 1
2 2T203 1253A SLC STANDBY LIOUID CONTROL 2
SPDCB201 H5026 1253A SLC STANDBY LIQUID CONTROL I
2 248004 253A SLC STANDBY LIQUID CONTROL 1
2 SPJCD207HI1 253A SLC STANDBY LIQUID CONTROL 2
LSHLC412NS00 253A SLC STANDBY LIQUID CONTROL 2
SPDCB201 H5022 253A SLC STANDBY LIQUID CONTROL 2
HCB205H52 253A SLC STANDBY LIQUID CONTROL 2
SPHCB205H56 253A SLC STANDBY LIQUID CONTROL 2
SPHCD231 H4 253A SLC STANDBY LIQUID CONTROL 2
ISPJCD207H2 253A SLC STANDBY LIQUID CONTROL 2
1248F33A 1253A SLC STANDBY LIQUID CONTROL 2
2T207A 1253A SLC STANDBY LIQUID CONTROL 2
ISPHCB205H54 1253A SLC STANDBY LIQUID CONTROL 2
2 SLC STANDBY LIQUID CONTROL 1
2 2'T207B 1253A SLC STANDBY LIQUID CONTROL i
2
.I ILsu IY U)Li,
f
.ISW L
vIu W
Iv L
LI L2T207B 1253A SLC STANDBY LIOUID CONTROL 2
V
EC4053.t0t2 Revision 0 Pace 57 of 138 HCB205H54 253A SLC STANDBY LIQUID CONTROL 1
2 ZS24806 253A SLC STANDBY LIQUID CONTROL I
2 SPDCB201 H5 253A SLC STANDBY LIQUID CONTROL I
2 2T204 253A SLC STANDBY LIQUID CONTROL 2
LE24812 253A SLC STANDBY LIQUID CONTROL 2
248003 253A SLC STANDBY LIQUID CONTROL 2
248017 253A SLC STANDBY LIQUID CONTROL 2
248F017 253A SLC STANDBY LIQUID CONTROL 2
2E219 253A SLC STANDBY LIQUID CONTROL 2
HSS24802 253A SLC STANDBY LIQUID CONTROL 2
TSHLC412N003 253A SLC STANDBY LIQUID CONTROL 2
LIFI24806 253A SLC STANDBY LIQUID CONTROL 2
P1248207A 253A SLC STANDBY LIQUID CONTROL 2
SPHBD601OH90Q0 253A SLC STANDBY LIQUID CONTROL 2
SPHBD601OH9001 253A SLC STANDBY LIQUID CONTROL, 2
SPHCD231 H2 253A SLC STANDBY LIQUID CONTROL 2
2P208B 253A SLC STANDBY LIQUID CONTROL 2
248001 253A SLC STANDBY LIQUID CONTROL 2
248F021 253A SLC STANDBY LIQUID CONTROL 2
248F024 253A SLC STANDBY LIQUID CONTROL 2
SPDCA206H2604 253A SLC STANDBY LIQUID CONTROL 2
SPDCB201 H61 253A SLC STANDBY LIQUID CONTROL 2
LISHL24812 253A SLC STANDBY LIQUID CONTROL 2
IPTC412N004 253A SLC STANDBY LIQUID CONTROL 2
248005 253A SLC STANDBY LIQUID CONTROL 2
SPHCD231H 253A SLC STANDBY lIQUID CONTROL 2
ITEC4I2NO06 253A SLC STANDBY LIQUID CONTROL I
2 ZS24808U 1253A SLC STANDBY LIQUID CONTROL 2
TAHL24803
-1253A SLC STANDBY LIQUID CONTROL 2
248006 253A SLC STANDBY LIQUID CONTROL 2
248FQ07 253A SLC STANDBY LIQUID CONTROL 2
ESC412K600 253A SLC STANDBY LIQUID CONTROL _
2 SPDCA206H2611 1253A SLC STANDBY LIQUID CONTROL 2
HS24808A 253A SLC STANDBY LIQUID CONTROL 2
PlC412R600 253A SLC STANDBY LIQUID CONTROL 2
SPDCA206H2618 253A SLC STANDBY LIQUID CONTROL 2
ISPDCA206H2620 253A SLC STANDBY LIQUID CONTROL 2
SPDCB20IH58 253A SLC STANDBY LIQUID CONTROL 2
SPDCB201H9001 253A SLC STANDBY LIQUID CONTROL 2
I PHB 6001019003 1253A SLC STANDBY LIQUID CONTROL 2
SPJCD207H9004 53A SIC STANDBY LIQUID CONTROL 2
SPJCD207H9006 1253A SLC STANDBY LIQUID CONTROL 2
248019 253A SLC STANDBY LIQUID CONTROL 2
HBD-6010 253A SLC STANDBY LIQUID CONTROL 2
FT24806 253A SLC STANDBY LIQUID CONTROL 2
SPDCB201H5001 1253A SLC STANDBY LIQUID CONTROL 2
SPDCB201OH5002 253A SLC STANDBY LIQUID CONTROL 2
SPDCB201H60 253A SLC STANDBY LIQUID CONTROL 2
TICC412R002 253A SIC STANDBY LIQUID CONTROL 2
TSHL24810 253A SLC STANDBY LIQUID CONTROL 2
XA24804
- 253A SLC STANDBY IIQUF D CONTROL 2
XYC412M600B 253A SLC STANDBY LIQUID CONTROL 2
248009 253A SLC STANDBY LIQUID CONTROL 2
SPDCB20IH521 1
253A SIC STANDBY LIQUID CONTROL 2
FE24806 253A SIC STANDBY LIQUID CONTROL 2
PCV2411A A 253A SIC STANDBY LIQID CONTROL 2
IHCB205H53 1253A SIC STANDBY LIQUID CONTROL 1
2 CB205H53 1253hIC253A S TANDBY LIQUID CONTROL 2
V
EC.053-1012 RevislOn 0 Paae 58 of 138 oHS24808B 1253A SLC STANDBY LIQUID CONTROL 2
PIC412R03 253A SLC STANDBY LIQUID CONTROL 2
248F012 253A SLC STANDBY L(QUID CONTROL 2
248F027 253A SLC STANDBY LIQUID CONTROL 2
HCB2O5H51 253A SLC STANDBY LIQUID CONTROL 2
JBD281 HI 253A SLC STANDBY LIQUID CONTROL 2
LG24803 253A SLC STANDBY LIQUID CONTROL 2
248FO01 253A SLC STANDBY LIQUID CONTROL 2
12E220 253A SLC STANDBY LIQUID CONTROL 2
1248F004B 253A SLC STANDBY LIQUID CONTROL 2
JBD-278 253A SLC STANDBY LIQUID CONTROL 2
PSV248F029B 253A SLC STANDBY LIQUID CONTROL 2
PT248N004-Rl 253A SLC STANDBY LIQUID CONTROL 2
SPDCA206H2602 1253A SLC STANDBY LIQUID CONTROL 2
SPHCD231 H3 253A SLC STANDBY LIQUID CONTROL 2
248002 253A SLC STANDBY LIQUID CONTROL 2
248008 253A SLC STANDBY LIQUID CONTROL l
2 248F002A 253A SLC STANDBY LIQUID CONTROL I
2 SPHBD601OH9002 253A SLC STANDBY LIQUID CONTROL I
2 HCB-205 253A SLC STANDBY LIQUID CONTROL 2
HV248F006 253A SLC STANDBY LIQUID CONTROL 2
HV248F006/ACT 253A SLC STANDBY LIQUID CONTROL 2
JBD-2045 253A SLC STANDBY LIQUID CONTROL 2
SPDCA206H2608 253A SLC STANDBY LIQUID CONTROL 2
SPDCB201H19 253A SLC STANDBY LIQUID CONTROL 2
SPHCB205H58 263A SLC STANDBY LIQUID CONTROL 2
HCB205H4 253A SLC STANDBY LIQUID CONTROL 2
248016 253A SLC STANDBY LIQUID CONTROL 2
248F004A 253A SLC STANDBY LIqUID CONTROL 2
SPDC201IH5020 253A SLC STANDBY LIQUID CONTROL 2
248007 253A SLC STANDBY LIQUID CONTROL I
2 i248F026 253A SLC STANDBY LIQUID CONTROL 2
HS24804 253A SLC STANDBY LIQUID CONTROL 2
HS24806 253A SLC STANDBY LIQUID CONTROL 2
SV248F029A-253A SLC STANDBY LIQUID CONTROL 2
!SPDCA206H2601 253A SLC STANDBY LIQUID CONTROL 2
SPJBD2045H9001 1253A SLC STANDBY LIQUID CONTROL 2
PCV2481iC 1253A SLC STANDBY UIQUID CONTROL 2
2P208A 253A SLC STANDBY LIQUID CONTROL 2
TE24810 I253A SLC STANDBY LIQUID CONTROL 2
248F031 253A SLC STANDBY LIQUID CONTROL 2
2C011 253A SLC STANDBY LIQUID CONTROL 2
FICC412RO04 253A SLC STANDBY LIQUID CONTROL 2
HCD-231 253A SLC STANDBY LIQUID CONTROL 2
JBD278HI 253A SIC STANDBY LIQUID CONTROL 2
LIC412RO01 253A SLC STANDBY LIQUID CONTROL I
2 SPDCB21 H5003 253A SLC STANDBY LIQUID CONTROL I
2 1248010 253A SLC STANDBY LIQUID CONTROL I
2 iTAHL24810 253A SLC STANDBY LIQUID CONTROL l
2
!gPDCA206H2619 253A SLC STANDBY LIQUID CONTROL 1
2
'SPJCD207H9Q03 253A SLC STANDBY LIQUID CONTROL 2
1248012 253A SLC STANDBY LIQUID CONTROL 2
'248F011 253A SIC STANDBY LIQUlD CONROL 2
I 1ZZZ~h~ZZZjSIC STANDBY LIQUID CONTROL 2
L248F018 1253A
_ SLC STANDBY LIQUID CONTROL 2
HCB205H3 23A ISLC STANDBY LIQUID CONTROL 2
iLAHL24801 253A SLC STANDBY LIQUID CONTROL I
2 IP1248207B 253A SLC STANDBY LIQUID CONTROL I
2 4LL~OUI VIM lOL.
IPUD T LIVUII
%VFfV I L
I 1
IPI248207B 253A ISLC STANDBY LIQUID CONTROL I
21 U
ECs053-1012 Revision O Pace 59 of 138 I
'SPMBD2045149000 253A SLC STANDBY LIQUID CONTROL 2
PT248N0S4-R2 253A SLC STANDBY LIQUID CONTROL 2
248011 253A SLC STANDBY LIQUID CONTROL 2
SPDCB201H5023 253A SLC STANDBY LIQUID CONTROL 2
ISPDCB201H5024 1253A SLC STANDBY LIQUID CONTROL 2
248018 1253A SLC STANDBY LIQUID CONTROL 2
248F002B 253A SLC STANDBY LIQUID CONTROL 2
248FQMB 253A SLC STANDBY LIQUID CONTROL 2
248F033B 253A SLC STANDBY LIQUID CONTROL 2
JBD-281 253A SLC STANDBY LIQUID CONTROL 2
iLTC412NOO1 253A SLC STANDBY LIQUID CONTROL 2
'PI248R003-R2 253A SLC STANDBY LIQUID CONTROL 2
IIC-PI248207A-253A SLC STANDBY LIQUID CONTROL 2
248015 253A SLC STANDBY LIQUID CONTROL 2
248F003A 253A SLC STANDBY LIQUID CONTROL 1
2 248F015 253A SLC STANDBY LIQUID CONTROL 2 2 245F016 253A SLC STANDBY LIQUID CONTROL 2
.DCD-220 253A SLC STANDBY LIQUID CONTROL 2
HCB205Hl 253A SLC STANDBY LIQUID CONTROL 2
IPCV24811I B 253A SLC STANDBY LIQUID CONTROL 2
ISPDCB201H2600 253A SLC STANDBY LIQUID CONTROL 2
SPDCB201IH56 253A SLC STANDBY lIQUID CONTROL 2
XYC412M600A 1253A SLC STANDBY LIQUID CONTROL 2
SPDCA206H2606
?253A SLC STANDBY LIQUID CONTROL 2
IC-PI248207B-I253A SLC STANDBY LIQUID CONTROL 2
248F008 253A SLC STANDBY LIQUID CONTROL I
2 P1248R003-R1 1253A SLC STANDBY LIQUID CONTROL, 2
!SPDCA206H2607 253A SLC STANDBY LIQUID CONTROL 1
2 ISPDCB2O1H5025 253A SLC STANDBY LIQUID CONTROL 2
!XY24806 253A SLC STANDBY LIQUID CONTROL 2
LZS24808L 253A SLC STANDBY LIQUID CONTROL 2
SPDCB201 H57 253A SLC STANDBY LIQUID CONTROL 2
,SPHCB205H60 r253A SLC STANDBY LIQUID CONTROL 2
ISPDCD220H1 253A SLC STANDBY LIQUID CONTROL I
2 V
EC-Q53-1012 RevislonO Paoe 60 of 138 PP&L CALCULATION SHEET D
PROJECT Calc. No.
En 053 1012 Assessment of SBLC Rev. No.
0 Designed By-G Kowal System for Suppression Checked By Pool pH Control Sh. No.
1-of 44-ATTACHMENT NO. 2 EPIX, NPRDS VALVE DATA 0
0 V
Failure Summary Report Page I of 18 EC.053-1C12 RevIsfonO Pame 61 at 138 Equipment Performance and Information Exchange 4.0 Failure Summary Report Generation Date 3/17/2005 V
Failure Summary Report Page 2 of 18 EC-5-1012 Revision 0 Pae 62 of 138 EPIX 4.0 Failure Summary Report 0
Specific Model: 3243-26-i Direct Cause or Contributor General Cause: mechanical process MNext Susquehanna 2 Failure Number: 306 Bookmarks:
Abstract Abstract Contact Equipment Details Susquehanna 2-Failure Number :306 02/09/1997 2:35:00 AM No plant effect, from power operation. No generation capability was lost. A Rosemount Controls Systems model 1151 DP4E22TO0O2PB (1151 DP4E22TOO02PB), failure caused the event. SLO STANDBY LIQUID CONTROL accumulators, tanks, air receivers, 2T204-unaffected by failure; transmitters, detectors, elements, LTC412N001-high output, but available; indicators, recorders, gauges, LI1F124806-high output/indication.
Contact DORN'JERRY G System Engineer 570-542-3443 3443 jgdom~pplweb.com Equipment Details Components Affected:
SLC STANDBY LIQUID CONTROL System Key:
Accumulators, tanks, air receivers 2T204 unaffected by failure After4701 days in service Site Common Name: STANDBY LIQUID CONTROL STORAGE TA Manufacturer Alpha Tank & Metals Mfg.
Model: 3243-26-1 Generic Model: 3243-26-1 Application :Boron Injection Tank Type (Parts List) :Liquid, Unpressurized SLC STANDBY LIQUID CONTROL System Supporting:
Indicators, recorders, gauges LUF124806 high output/indication After 187 days in service Site Common Name: SBLC TANK LEVEL AND FLOW Manufacturer: International Instruments Div/ Sigma Model: 9270-Dl N-0-2-VB Generic Model: 9270-D1 N-0-2-VB Parameter Measured/input Signal :Flow Type (Primary Function) (Parts List) :Indicator Component Causlng Failure:
Supporting:
SLC STANDBY LIQUID CONTROL Transmitters, detectors, elements LTC412N001 high output, but available After4701 days in service W
high output, but available
Failure Summary Report Causes of Component Failure:
Associated Maintenance:
Page 3 of 18 ECO03-1012 Revision O Pace 63 of 138 Site Common Name: SBLC STORAGE TANK LEVEL TRANSMITTER Manufacturer Rosemount Controls Systems Model: 1151DP4E22TOO02PB Generic Model: 1151 DP4E22TOO02PB Parameter Measured/linput Signal Level Principle of Operation (Parts List): Positive Displacement Type (Primary Function): Transmitter LTC412N001 tube sbIc storage tank level transmitter - bubbler tube -
clogged/blocked - inservice since 3/28/84 Due to:
mechanical process, clogged / blocked Function restored by:
operator actions taken restored normal lineup Recurrence Prevented by:
preventive maintenance interval changed preventive maintenance program revised None
[oDI IPreQ INextI Susquehanna 2 Failure Number: 307 Bookmarks:
Abstract Abstract Contact Eguipment Details Susquehanna 2-Failure Number :307 02(22/1997 12:00:00 PM - No plant effect, from power operation. No generation capability was lost. A Rosemount Controls Systems model 1151 DP4E22T0002PB (1151 DP4E22T0002PB), failure caused the event. SLC STANDBY LIQUID CONTROL accumulators, tanks, air receivers, 2T204-unaffected by failure; transmitters, detectors, elements, LTC412NO01-high output, but available; indicators, recorders, gauges, LI/FI24806-high output/indication.
Contact DORN'JERRY G System Engineer 570-542-3443 3443 jgdorn~pplweb.com Equipment Details Components Affected:
SLC STANDBY LIQUID CONTROL System Key:
Accumulators, tanks, air receivers 2T204 unaffected by failure After4714 days in service Site Common Name: STANDBY LIQUID CONTROL STORAGE TA Manufacturer: Alpha Tank & Metals Mfg.
Model: 3243-26-1 Generic Model: 3243-26-1 Application :Boron Injection Tank Type (Parts List) :Liquid, Unpressurized SLC STANDBY LIQUID CONTROL System Supporting:
Indicators, recorders, gauges L1F124806 W
SLC STANDBY LIQUID CONTROL System
Failure Summary Report Pagce_47o 18 EC-053-1012 Aeviskn 0 Pace 64 of 138 Component Causing Failure:
Supporting:
Causes of Component Failure:
Associated Maintenance:
high output/indication After 200 days in service Site Common Name: SBLC TANK LEVEL AND FLOW Manufacturer: International Instruments Div/ Sigma Model: 9270-Dl N-0-2-VB Generic Modet: 9270-Di N-0-2-VB Parameter Measured/input Signal Flow Type (Primary Function) (Parts List) ;Indicator SLC STANDBY LIQUID CONTROL Transmitters, detectors, elements LTC412N001 high output, but available After 4714 days in service Site Common Name: SBLC STORAGE TANK LEVEL TRANSMITTER Manufacturer Rosemount Controls Systems Model: 1 151DP4E22T0002PB Generic Model: 1151 DP4E22TOO02PB Parameter Measured/input Signal: Level Principle of Operation (Parts List): Positive Displacement Type (Primary Function): Transmitter LTC412NO01 tube sbIc storage tank level transmitter - bubbler tube -
clogged/blocked - inservice since 3/28/84 Due to:
mechanical process, clogged / blocked Function restored by:
operator actions taken restored normal lineup Recurrence Prevented by:
preventive maintenance interval changed preventive maintenance program revised None ITopl lPrevj INext Susquehanna 2 Failure Number: 308 Bookmarks:
Abstract Abstract Contact Equipment Details Susquehanna 2-Failure Number :308 03/08/1997 1:30:00 AM - No plant effect, from power operation. No generation capability was lost. A Rosemount Controls Systems model 1151DP4E22TO0O2PB(1151DP4E22TOO02PB), failurecausedthe event. SLC STANDBY LIQUID CONTROL accumulators,tanks,airreceivers,2T204-unaffectedby failure; transmitters, detectors, elements, LTC412NO01-high output, but available; indicators, recorders, gauges, LI/FI24806-high output/indication.
Contact 0
DORN*JERRY G System Engineer 570-542-3443 3443 jgdornmpplweb.com A_...,
v_...............
Failure Summary Report Equipment Details Components Affected:
SLC STANDBY LIQUID CONTROL System U
Key:
Accumulators, tanks, air receivers 2T204 unaffected by failure After 4728 days in service Site Common Name: STANDBY LIQUID CONTROL STORAGE TA Manufacturer: Alpha Tank & Metals Mfg.
Model: 3243-26-1 Generic Model: 3243-26-1 Application :Boron Injection Tank Type (Parts List) :Liquid, Unpressurized SLC STANDBY LIQUID CONTROL System Supporting:
Indicators, recorders, gauges L/Fi24806 high output/indication After 214 days in service Site Common Name: SBLC TANK LEVEL AND FLOW Manufacturer: International Instruments Div/ Sigma Model: 9270-DI N-0-2-VB Generic Model: 9270-DI N-O-2-VB Parameter Measured/Input Signal :Flow Type (Primary Function) (Parts List) :Indicator Component Causing SLC STANDBY LIQUID CONTROL Supporting:
Transmitters, detectors, elements LTC412NO01 high output, but available After4728 days in service Site Common Name: SBLC STORAGE TANK LEVEL TRANSMITTER Manufacturer: Rosemount Controls Systems Model: 1151 DP4E22TOO02PB Generic Model: 1151 DP4E22TOO02PB Parameter Measured/Input Signal: Level Principle of Operation (Parts List): Positive Displacement Type (Primary Function): Transmitter Causes of Component LTC412N001 tube sbic storage tank level transmitter - bubbler tube -
Failure:
clogged/blocked - inservice since 3/28/84 Due to:
mechanical process, clogged / blocked Function restored by:
operator actions taken restored normal lineup Recurrence Prevented by:
preventive maintenance Interval changed preventive maintenance program revised Associated Maintenance:
None Page 5 of I 8 EC45os31012 Revision 0 Pace 65 of 138 t
JPrevINextJ Susquehanna 2 Bookmarks:
Abstract Abstract Failure Number: 309 Contact Equipment Details b
Bookmarks:
Abstrac Contact Eauipment Details
Failure Summary Report Page 6 of IS Failre ummry Rpor Paec~of 18 EC-.053.1012 Revision 0 Paoe 68 0? 138 Susquehanna 2-Failure Number :309 0210911997 2:00:00 PM - No plant effect, from power operation. No generation capability was lost. A Rosemount Controls Systems model 1151 DP4E22TOO02PB (1151 DP4E22TOO02PB), failure caused the event. SLC STANDBY LIQUID CONTROL accumulators, tanks, air receivers, 2T204-unaffected by failure; transmitters, detectors, elements, LTC412N001-high output, but available; indicators, recorders, gauges, Ll/FI24806-high output/indication.
Contact DORN*JERRY G System Engineer 570-542-3443 3443 Jgdornmpplweb.com Equipment Details Components Affected:
SLC STANDBY LIQUID CONTROL System Key:
Accumulators, tanks, air receivers 2T204 unaffected by failure After 4701 days in service Site Common Name: STANDBY LIQUID CONTROL STORAGE TA Manufacturer Alpha Tank & Metals Mfg.
Model: 3243-26-1 Genetic Model: 3243-26-1 Application :Boron Injection Tank Type (Parts List) :Liquid, Unpressurized SLC STANDBY LIQUID CONTROL System Supporting:
Indicators, recorders, gauges LI/F124806 high outputlindication After 187 days in service Site Common Name: SBLC TANK LEVEL AND FLOW Manufacturer International Instruments Div/ Sigma Model: 9270-D1 N-0-2-VB Generic Model: 9270-01 N-0-2-VB Parameter Measured/lInput Signal :Flow Type (Primary Function) (Parts List) :Indicator Component Causing SLC STANDBY LIQUID CONTROL Failure.-
Supporting:
Transmitters, detectors, elements LTC412NDO1 high output, but available After4701 days In service Site Common Name: SBLC STORAGE TANK LEVEL TRANSMITTER Manufacturer: Rosemount Controls Systems Model: 1151 DP4E22T0002PB Generic Model: 1151 DP4E22T0002PB Parameter Measured/linput Signal: Level Principle of Operation (Parts List) : Positive Displacement Type (Primary Function) : Transmitter Causes of Component LTC412N001 tube sbIc storage tank level transmitter - bubbler tube -
Fallure:
clogged/blocked - inservice since 3/28/84 Due to:
mechanical process, clogged / blocked Function restored by:
operator actions taken Ije
Failure Summary Report EC.053-1012
?ac~e all0f1138 restored normal lineup Recurrence Prevented by:
preventive maintenance interval changed preventive maintenance program revised None Associated Maintenance:
fopl IPrev ILNexti Susquehanna 2 Failure Number: 310 Bookmarks:
Abstract Abstract Contact Equipment Details Susquehanna 2-Failure Number :310 04/12/1997 12:00:00 PM - No plant effect, from power operation. No generation capability was lost. A Rosemount Controls Systems model 1151 DP4E22TOO02PB (1151 DP4E22TOO02PB), failure caused the event. SLC STANDBY LIQUID CONTROL accumulators, tanks, air receivers, 2T204-unaffected by failure; transmitters, detectors, elements, LTC412N001 - high output, but available; indicators, recorders, gauges, LI/FI24806-high output/indication.
Contact DORN JERRY G System Engineer 570-542-3443 3443 jgdom~pplweb.com Equipment Details Components Affected:
SLC STANDBY LIQUID CONTROL System Key:
Accumulators, tanks, air receivers 2T204 unaffected by failure After4763 days in service Site Common Name: STANDBY LIQUID CONTROL STORAGE TA Manufacturer: Alpha Tank & Metals Mfg.
Model: 3243-26-1 Generic Model: 3243-26-1 Application :Boron Injection Tank Type (Parts List) :Liquid, Unpressurized SLC STANDBY LIQUID CONTROL System Supporting:
Indicators, recorders, gauges LVF[24806 high output/indication After249 days in service Site Common Name: SBLC TANK LEVEL AND FLOW Manufacturer: International Instruments Div/ Sigma Model: 9270-Dl N-0-2-VB Generic Model: 927D-Dl N-0-2-VB Parameter Measured/input Signal :Flow Type (Primary Function) (Parts List) Indicator Component Causing SLC STANDBY LIQUID CONTROL Failure:
Supporting:
Transmitters, detectors, elements LTC41 2N001 high output, but available After 4763 days In service W
high output, but available
Failure Summary Report Page 8 of 18 EC-053.1012 RevIsion 0 Paae 68 of 138 Causes of Component Failure:
Associated Maintenance:
Site Common Name: SBLC STORAGE TANK LEVEL TRANSMITTER Manufacturer: Rosemount Controls Systems Model: 1151 DP4E22T0002PB Generic Model: 1151 DP4E22TOOO2PB Parameter Measuredlinput Signal: Level Principle of Operation (Parts List): Positive Displacement Type (Primary Function): Transmitter LTC412NO01 tube sbic storage tank level transmitter - bubbler tube -
clogged/blocked - inservice since 3/28/84 Due to:
mechanical process, clogged / blocked Function restored by:
operator actions taken restored normal lineup Recurrence Prevented by:
preventive maintenance interval changed preventive maintenance program revised None ITOpI IPrevj JNextl Susquehanna 2 Failure Number : 311 Bookmarks:
Abstract Abstract Contact Eauipment Details Susquehanna 2-Failure Number :311 05/01/1997 4:54:00 PM - No plant effect, from power operation. No generation capability was lost. A Rosemount Controls Systems model 1151 DP4E22T0002PB (1151 DP4E22TOO02PB ), failure caused the event. SLC STANDBY LIQUID CONTROL accumulators, tanks, air receivers, 2T204-unaffected by failure; transmitters, detectors, elements, LTC412N001-high output, but available; indicators, recorders, gauges, LI/F124806-high output/indication.
Contact DORN*JERRY G System Engineer 570-542-3443 3443 jgdomrpplweb.com Equipment Details Components Affected:
SLC STANDBY LIQUID CONTROL System Key:
Accumulators, tanks, air receivers 2T204 unaffected by failure After 4782 days in service Site Common Name: STANDBY LIQUID CONTROL STORAGE TA Manufacturer: Alpha Tank & Metals Mfg.
Model: 3243-26-1 Generic Model: 3243-26-1 Application :Boron Injection Tank Type (Parts List) :Liquid, Unpressurized SLC STANDBY LIQUID CONTROL System Supporting:
Indicators, recorders, gauges Ll/F124806 W
I ype Jrarns LISt) :LUquio, unpressunzea USLO STANDBY 1 t1 ID nCONTROL Svqtpm
Failure Summary Report Component Causing Failure:
Supporting:
Causes of Component Failure:
Page 9 of 18 EC-053-1012 Revision 0 Pace 69 of 138 high output/indication After 268 days In service Site Common Name: SBLC TANK LEVEL AND FLOW Manufacturer International Instruments Div/ Sigma Model: 9270.D1 N-0-2-VB Generic Model: 9270-D1 N-0-2-VB Parameter Measured/input Signal :Flow Type (Primary Function) (Parts List) :Indicator SLC STANDBY LIQUID CONTROL Transmitters, detectors, elements LTC412N001 high output, but available After 4782 days in service Site Common Name: SBLC STORAGE TANK LEVEL TRANSMITTER Manufacturer: Rosemount Controls Systems Model: 1151 DP4E22TOO02PB Generic Model: 1151 DP4E22TOO02PB Parameter MeasuredlInput Signal : Level Principle of Operation (Parts List): Positive Displacement Type (Primary Function) : Transmitter LTC41 2N001 tube sbic storage tank level transmitter - bubbler tube -
clogged/blocked - inservice since 3/28/84 Due to:
mechanical process, clogged / blocked Function restored by:
operator actions taken restored normal lineup Recurrence Prevented by:
preventive maintenance interval changed preventive maintenance program revised None Associated Maintenance:
{TopI IPrevi INext]
Susquehanna 2 Failure Number: 312 Bookmarks:
Abstract Abstract Contact Equipment Details Susquehanna 2-Failure Number :312 05/17/1997 3:30:00 PM - No plant effect, from power operation. No generation capability was lost. A Rosemount Controls Systems model 1151DP4E22TOO02PB (1151DP4E22T0002P8), failure caused the event SLC STANDBY LIQUID CONTROL accumulators, tanks, air receivers, 2T204-unaffected by failure; transmitters, detectors, elements, LTC412N001-high output, but available; indicators, recorders.
gauges, LIFI24806-high output/indication.
Contact DORN*JERRY G System Engineer 570-542-3443 3443 jgdorntpplweb.com V
Failure Summary Report Page 10 of IS eC4c 53 1072 NM.
'&Of 13 Equipment Details Components Affected:
SLC STANDBY LIQUID CONTROL System Key:
Accumulators, tanks, air receivers 2T204 unaffected by failure After 4798 days in service Site Common Name: STANDBY LIQUID CONTROL STORAGE TA Manufacturer Alpha Tank & Metals Mfg.
Model: 3243-26-1 Generic Model: 3243-26.1 Application :Boron Injection Tank Type (Parts List) :Liquid, Unpressurized SLC STANDBY LIQUID CONTROL System Supporting:
Indicators, recorders, gauges Ll/F124806 high outputfindication After284 days in service Site Common Name: SBLC TANK LEVEL AND FLOW Manufacturer International Instruments Div/ Sigma Model: 9270-Dl N-0-2-VB Generic Model: 9270-Dl N-0-2-VB Parameter Measured/lInput Signal :Flow Type (Primary Function) (Parts List) :Indicator Component Causing Failure:
Supporting:
SLC STANDBY LIQUID CONTROL Transmitters, detectors, elements LTC412NO01 high output, but available After4798 days in service Site Common Name: SBLC STORAGE TANK LEVEL TRANSMITTER Manufacturer: Rosemount Controls Systems Model: 1151 DP4E22TOO02PB Generic Model: 1151 DP4E22T0002PB Parameter Measured/input Signal Level Principle of Operation (Parts List): Positive Displacement Type (Primary Function): Transmitter LTC41 2N001 tube sblc storage tank level transmitter - bubbler tube -
clogged/blocked - inservice since 3/28/84 Due to:
mechanical process, clogged / blocked Causes of Component Failure:
Function restored by:
operator actions taken restored normal lineup Recurrence Prevented by:
preventive maintenance interval changed preventive maintenance program revised None Associated Maintenance:
mopULPrevINAxt Susquehanna 2 Bookmarks:
Abstract Abstract Failure Number: 313 Contact Equipment Details W
Bookmarks:
Abstract Contact Eguipment Details
.. Failure Summ'ary Report Page I I of 18 EC-053-1012 Revison O Pae 71 of 138 Susquehanna 2-Failure Number :313 06/03/1997 9:00:00 PM - No plant effect, from power operation. No generation capability was lost. A Rosemount Controls Systems model 1151 DP4E22TOO02PB (1151 DP4E22TOO02PB ), failure caused the event. SLC STANDBY LIQUID CONTROL accumulators, tanks, air receivers, 2T204-unaffected by failure; transmitters, detectors, elements, LTC412N001-high output, but available; indicators, recorders, gauges, L11F124806-high output/indication.
Contact DORN'JERRY G System Engineer 570-542-3443 3443 jgdom~pplweb.com Equipment Details Components Affected:
SLC STANDBY LIQUID CONTROL System Key:
Accumulators, tanks, air receivers 2T204 unaffected by failure After4815 days in service Site Common Name: STANDBY LIQUID CONTROL STORAGE TA Manufacturer: Alpha Tank & Metals Mfg.
Model: 3243-26-1 Generic Model: 3243-26-1 Application :Boron Injection Tank Type (Parts List) :Liquid, Unpressurized SLC STANDBY LIQUID CONTROL System Supporting:
Indicators, recorders, gauges L1/F124806 high output/indication After301 days in service Site Common Name: SBLC TANK LEVEL AND FLOW Manufacturer: International Instruments Div/ Sigma Model: 9270-Dl N-0-2-VB Generic Model: 9270-DI N-0-2-VB Parameter Measured/linput Signal :Flow Type (Primary Function) (Parts List) Indicator Component Causing SLC STANDBY LIQUID CONTROL Failure:
Supporting:
Transmitters, detectors, elements LTC412N001 high output, but available After4815 days in service Site Common Name: SBLC STORAGE TANK LEVEL TRANSMITTER Manufacturer: Rosemount Controls Systems Model: 1151 DP4E22T0002PB Generic Model: 1151 DP4E22TOO02PB Parameter MeasuredlInput Signal: Level Principle of Operation (Parts List): Positive Displacement Type (Primary Function) : Transmitter Causes of Component LTC41 2N001 tube sbIc storage tank level transmitter - bubbler tube -
Failure:
clogged/blocked - inservice since 3/28/84 Due to:
mechanical process, clogged / blocked Function restored by:
operator actions taken V
E*
s...In. een.ag In,.
Failure Summary Report Piage 12 of 18 ECC53-1o02 Revision 0 Paoe 72 of 138 restored normal lineup Recurrence Prevented by:
preventive maintenance interval changed preventive maintenance program revised None Associated Maintenance:
lTopl jPrevl INexti Susquehanna 2 Failure Number: 314 Bookmarks:
Abstract Abstract Contact
.Egioment Details Susquehanna 2-Failure Number :314 06/30/1997 12:00:00 PM -No plant effect, from power operation. No generation capability was lost. A Rosemount Controls Systems model 1151 DP4E22TOO02PB (1151 DP4E22TOO02PB), failure caused the event. SLC STANDBY LIQUID CONTROL accumulators, tanks, air receivers, 2T204-unaffected by failure; transmitters, detectors, elements, LTC412NO01-high output, but available; indicators, recorders, gauges, LVF124806-high outputlindication.
Contact DORN'JERRY G System Engineer 57G-542-3443 3443 jgdom~pplweb.com Equipment Details Components Affected:
SLC STANDBY LIQUID CONTROL System Key:
Accumulators, tanks, air receivers 2T204 unaffected by failure After4842 days in service Site Common Name: STANDBY LIQUID CONTROL STORAGE TA Manufacturer: Alpha Tank & Metals Mfg.
Model: 3243-26-1 Generic Model: 3243-26-1 Application :Boron Injection Tank Type (Parts List) :Liquid, Unpressurized SLC STANDBY LIQUID CONTROL System Supporting:
Indicators, recorders, gauges LI/FI24806 high output/indication After 328 days in service Site Common Name: SBLC TANK LEVEL AND FLOW Manufacturer: International Instruments Div/ Sigma Model: 9270-Dl N-0-2-VB Generic Model: 9270-Dl N-0-2-VB Parameter Measured'lnput Signal :Flow Type (Primary Function) (Parts List) Indicator Component Causing SLC STANDBY LIQUID CONTROL Fallure:
Supporting:
Transmitters, detectors, elements LTC412N001 high output, but available Alter4842 days in service W
high output, but available A D...; ADAn A-.
Failure Suirnary Report Causes of Component Failure:
Associated Maintenance:
Page 13 of 18 EC.053-t 0i2 RevisicOO Pace 73 01 38 Site Common Name: SBLC STORAGE TANK LEVEL TRANSMITTER Manufacturer Rosemount Controls Systems Model: 1151 DP4E22T0002PB Generic Model: 1151 DP4E22T0002PB Parameter Measured/Input Signal: Level Principle of Operation (Parts List): Positive Displacement Type (Primary Function): Transmitter LTC412NO01 tube sbIc storage tank level transmitter - bubbler tube -
clogged/blocked - inservice since 3/28/84 Due to:
mechanical process, clogged I blocked Function restored by:
operator actions taken restored normal lineup Recurrence Prevented by:
preventive maintenance Interval changed preventive maintenance program revised None
[op] jPrevj jNextl Susquehanna 2 Failure Number: 315 Bookmarks:
Abstract Abstract Contact Equipment Details Susquehanna 2-Failure Number :315 07/31/1997 11:29:00 PM -No plant effect, from power operation. No generation capability was lost. A Rosemount Controls Systems model 1151 DP4E22TOO02PB (1151 DP4E22TOO02PB), failure caused the event. SLC STANDBY LIQUID CONTROL accumulators, tanks, air receivers, 2T204-unaffected by failure; transmitters, detectors, elements LTC412NO01-high output, but available; indicators, recorders, gauges, LI/FI24806-high output/indication.
Contact DORN*JERRY G System Engineer 570-542-3443 3443 jgdom~pplweb.com Equipment Details Components Affected:
SLC STANDBY LIQUID CONTROL System Key:
Accumulators, tanks, air receivers 2T204 unaffected by failure After4873 days in service Site Common Name: STANDBY LIQUID CONTROL STORAGE TA Manufacturer: Alpha Tank & Metals Mfg.
Model: 3243-26-1 Generic Model: 3243-26-1 Application :Boron Injection Tank Type (Parts List) :Liquid, Unpressurized SLC STANDBY LIQUID CONTROL System Supporting:
Indicators, recorders, gauges L11FI24806 Type (Parts List) :Lquia, unpressunzeu Ci r. QTAMfnRV l ifar fn r.nNTROL Svstem
Failure Summary Report 0
Component Causing Failure:
Supporting:
Causes of Component Failure:
Associated Maintenance:
Page 14 of 18 EC-03-1O0 2 Revw san a PaWe 74 of 1i8 high output/indication After359 days in service Site Common Name: SBLC TANK LEVEL AND FLOW Manufacturer: International Instruments Div/ Sigma Model: 9270-DI N--2-VB Generic Model: 9270-DI N-0-2-VB Parameter Measuredlinput Signal :Flow Type (Primary Function) (Parts List) :Indicator SLC STANDBY LIQUID CONTROL Transmitters, detectors, elements LTC412NO01 high output, but available After4873 days In service Site Common Name: SBLC STORAGE TANK LEVEL TRANSMITTER Manufacturer Rosemount Controls Systems Model: 1151 DP4E22TO002PB Genefic Model: 1151 DP4E22T0002PB Parameter Measured/Input Signal: Level Principle of Operation (Parts List): Positive Displacement Type (Primary Function): Transmitter LTC412NO01 tube sbIc storage tank level transmitter -bubbler tube -
clogged/blocked - inservice since 3/28/84 Due to:
mechanical process, clogged I blocked Function restored by:
operator actions taken restored normal lineup Recurrence Prevented by:
preventive maintenance interval changed preventive maintenance program revised None fTOpI 1Previ INext-Susquehanna 2 Failure Number: 316 Bookmarks:
Abstract Abstract Contact Eauipment Details Susquehanna 2-Failure Number :316 09/02/1997 12:00:00 PM - No plant effect, from power operation. No generation capability was lost. A Rosemount Controls Systems model 1151 DP4E22TOO02PB (1151 DP4E22TOO02PB), failure caused the event. SLC STANDBY LIQUID CONTROL accumulators, tanks, air receivers, 2T204-unaffected by failure; transmitters, detectors, elements, LTC412N001 - high output, but available; indicators, recorders, gauges, LI/FI24806-high outputtindication.
Contact DORN'JERRY G System Engineer 570-542-3443 3443 jgdom~pplweb.com V
Failure Summary Report Equipment Detai Components Affected:
V Key:
Supporting:
Component Causing Failure:
Supporting:
Causes of Component Failure:
Associated Maintenance:
FIS Pag j
5 Rev4-10 0 Paw 75 01138 SLC STANDBY LIQUID CONTROL System Accumulators, tanks, air receivers 2T204 unaffected by falrure After 4906 days in service Site Common Name: STANDBY LIQUID CONTROL STORAGE TA Manufacturer Alpha Tank & Metals Mfg.
Model: 3243-26-1 Generic Model: 3243-26-1 Application :Boron Injection Tank Type (Parts List) :Liquid, Unpressurized SLC STANDBY LIQUID CONTROL System Indicators, recorders, gauges LI/FI24806 high outputfindication After 392 days In service Site Common Name: SBLC TANK LEVEL AND FLOW Manufacturer: International Instruments Div/ Sigma Model: 9270-DIN-0-2-VB Generic Model: 9270-Dl N-0-2-VB Parameter Measured/Input Signal :Flow Type (Primary Function) (Parts List) :Jndicator SLC STANDBY LIQUID CONTROL Transmitters, detectors, elements LTC412NO01 high output, but available After4906 days in service Site Common Name: SBLC STORAGE TANK LEVEL TRANSMITTER Manufacturer Rosemount Controls Systems Model: 1151 DP4E22T0002PB Generic Model: 1151 DP4E22T0002PB Parameter Measured/input Signal: Level Principle of Operation (Parts List): Positive DIsplacement Type (Primary Function): Transmitter LTC41 2NO01 tube sbkc storage tank level transmitter - bubbler tube - blocked tube
- inservice since 3/28/84 Due to:
mechanical process, clogged / blocked Function restored by:
operator actions taken restored normal lineup Recurrence Prevented by:
preventive maintenance interval changed preventive maintenance program revised None DOplPrev[Nextl Susquehanna 2 Bookmarks:
Abstract Abstract Failure Number: 317 Contact Equipment Details 4P Bookmarks:.
Abstract Contact Eguipment Details
Failure Summary Report Page 16 of'-F8--'
ECQJ5310?2 Re~vIsion o Pa 78 of 1s3 8 Susquehanna 2-Failure Number :317 11/24/1997 10:00:00 AM - No plant effect, from power operation. No generation capability was lost. A Rosemount Controls Systems model 1151 DP4E22TOO02PB (1151 DP4E22TOO02PB ), failure caused the event. SLC STANDBY LIQUID CONTROL accumulators, tanks, air receivers, 2T204-unaffected by failure; transmitters, detectors, elements, LTC412NOO1-high output, but available; indicators, recorders, gauges, LI/F124806-high outpuVindication.
Contact I
DORN*JERRY G System Engineer 570-542-3443 3443 1gdomrpplweb.con Equipment Details Components Affected:
SIC STANDBY LIQUID CONTROL System Key:
Accumulators, tanks, air receivers 2T204 unaffected by failure After4989 days in service Site Common Name: STANDBY LIQUID CONTROL STORAGE TA Manufacturer: Alpha Tank & Metals Mfg.
Model: 3243-26-1 Generic Model: 3243-26-1 Application :Boron Injection Tank Type (Parts List) :Liquid, Unpressurized SLC STANDBY LIQUID CONTROL System Supporting:
Indicators, recorders, gauges LI/F124806 high output/indication After 475 days in service Site Common Name: SBLC TANK LEVEL AND FLOW Manufacturer International Instruments Div/ Sigma Model: 9270-Dl N-0-2-VB Generic Model: 9270-Dl N-0-2-VB Parameter Measured/Input Signal :Flow Type (Primary Function) (Parts List) :Indicator Component Causing Failure:
Supporting:
Causes of Component Failure:
SLC STANDBY LIQUID CONTROL Transmitters, detectors, elements LTC412NO01 high output, but available After4989 days in service Site Common Name: SBLC STORAGE TANK LEVEL TRANSMITTER Manufacturer: Rosemount Controls Systems Model: 1151 DP4E22TOO02PB Generic Model: 1151 DP4E22T0002PB Parameter Measured/Input Signal: Level Principle of Operation (Parts List): Positive Displacement Type (Primary Function): Transmitter LTC412N001 tube sbic storage tank level transmitter - bubbler tube - blocked tube
- inservice since 3/28/84 Due to:
mechanical process, clogged I blocked Function restored by:
operator actions taken W
Poine-flem rpptenrd hby
EC.o53.tOz Failure Summary Report Page 17 of 18 Revision o Pa 80 0 7 7 o1 138 restored normal lineup Recurrence Prevented by:
preventive maintenance Interval changed preventive maintenance program revised Associated None Maintenance:
Nn fCopi JPrevJ Susquehanna 2 Failure Number: 820 Bookmarks:
Abstract Contact Equipment Details Abstract Susquehanna 2-Failure Number :820 05/2011999 - No plant effect, from power operation. No generation capability was lost. A Rosemount Controls Systems model 1151 DP4E22TOO02PB (1151 DP4E22TOO02PB), failure caused the event. SLC STANDBY LIQUID CONTROL accumulators, tanks, air receivers, 2T204-unaffected by failure; transmitters, detectors, elements, LTC412NO01-high output, but available; indicators, recorders, gauges, LUF124806-high output/indication.
Contact MISSIEN*IAN C System Engineer 570-542-3396 3396 icmissien~ppIweb.com Equipment Details Components Affected:
SLC STANDBY LIQUID CONTROL System Key:
Accumulators, tanks, air receivers 2T204 unaffected by failure After5531 days in service Site Common Name: STANDBY LIQUID CONTROL STORAGE TA Manufacturer Alpha Tank & Metals Mfg.
Model: 3243-26-1 Generic Model: 3243-26-1 Application :Boron Injection Tank Type (Parts List) :Uquid, Unpressunzed SLC STANDBY LIQUID CONTROL System Supporting:
Indicators, recorders, gauges L1/FI24806 high outputlindication After 1017 days in service Site Common Name: SBLC TANK LEVEL AND FLOW Manufacturer International Instruments Div/ Sigma Model: 9270-Dl N-0-2-VB Generic Model: 9270-Dl N-0-2-VB Parameter Measured/Input Signal :Flow Type (Primary Function) (Parts List) Indicator Component Causing SLC STANDBY LIQUID CONTROL Failure:
Supporting Transmitters, detectors, elements LTC412NO01 high output, but available After5531 days in service W
high output, but available an. -
n
.J.
Failure Summary Report 0
Page 18 of 18 EC4053tC12 Revson O Pace 78 of 138 Site Common Name: SBLC STORAGE TANK LEVEL TRANSMITTER Manufacturer Rosemount Controls Systems Model: 1 151 DP4E22T0002PB Generic Model: 1151 DP4E22T0002PB Parameter Measured/Input Signal: Level Principle of Operation (Parts List) : Positive Displacement Type (Primary Function) : Transmitter LTC412N001 tube sbIc storage tank level transmitter - bubbler tube - blocked tube
- inservice since 3/28/84 Due to:
mechanical process, clogged / blocked Function restored by:
operator actions taken restored normal lineup Recurrence Prevented by:
preventive maintenance interval changed preventive maintenance program revised None Causes of Component Failure:
Associated Maintenance:
INPO Equipment Performance and Information Exchange 4.0 Production Read Only w
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EPIX/NPRDS General Text Search Look for "SBLC"AND "ISOLATION CHECK VALVE" I n rNPRDS S rF Search Tips Documents 1 to 2 of 2 matching the query ""SBLC" AND "ISOLATION CHECK VALVE"".
- 1. 92.uQUAD CITIES I-Valves, dampers Abstract. *SBLCS Cntmnt Isol Check Va~veI-11O1-I6 01 nternal Leakage-Standby Liquid Control-GE"System Function/Operation Unaffected-Resulted in No Significant Effect-Crane Co-3888-XU http:/www.inpo.ora/databases/nprdsl185/cwe adll85708.htm - size 6333 bytes -
11/13/1992 5:00:00 PM GMT
- 2. 92'HOPE CREEK 1-Valaves. dampers Abstract: *SBLCS Cntmnt Isol Check Valve-lBHV-029-Internal Leakage-Standby Liquid Control-GE-System Function/Operation Unaffected-Resulted In No Significant Effect-Rockwell Int/ Flow Control Div-1.5-36274T1 http://www. inpo. oro/databases nnrds/1 64Aj ghcs1 164209. htm - size 5909 bytes -
10/7/1992 5:00:00 PM GMT Page 1 of I 0
_0
Failure Summary Report Page I of 2 EC-083-101p 2
Rle9!S!O 0 paae oe8?t138 Equipment Performance and Information Exchange 4.0 Failure Summary Report Generation Date 3/17/2005
Failure Summary Report Page 2 of 2 EC-053-1012 RevfsioriO PaPe l8 of 138 EPIX 4.0 0
Failure Summary Report Key Direct Cause or Contributor Component Type: Valves, dampers Component Type: Valves, dampers Nine Mile Point 2 Failure Number: 351 Boomataks:
Abstract Abstract Contact Eguipment Details Nine Mile Point 2-Fallure Number :351 03107/2000 3:20:00 PM -Outage impacted, from refueling. No generation capability was lost. A Velan Inc model B303-6W14MS (B303-6W14MS), failure caused the event. Standby Liquid Control System valves, dampers, 2SLS*1 0- internal leakage when fully seated.
Contact Tanguay, Thomas System Engineer 31 5-349-4428 TanguayT@nimo.com Equipment Details Component Causing Failure:
Key:
Causes of Component Failure:
Associated Maintenance:
Standby Liquid Control System Valves, dampers 2SLS*V1 0 internal leakage when fully seated After4906 days in service Industry Common Name: 'SBLCS Cntmnt Isol Check Valve Manufacturer Velan Inc Model: B303-6W14MS Generic Model: B303-6W1 4MS Body Material: Austenitic Stainless STL-31 6 Function/Application: One-Way Flow Nominal Inlet Size (Range) :2 to 3.99 IN Operator: None Type (Parts List): Check 2SLSV1 0 none Identified by investigation Due to:
mechanical process, foreign material Function restored by:
operator actions taken repaired device (beyond recalibration)
Recurrence Prevented by:
actions to prevent recurrence not needed None Ii I
IiII INPO Equipment Performance and Information Exchange 4.0 Production Read Only W
INPO Equipment Performance and Information Go dA n
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Failure Summary Report Page I of 12 EC"053-1012 Revision 0 Pace 82 ct US Equipment Performance and Information Exchange 4.0 Failure Summary Report Generation Date3/17/2005 V
Failure Summary Report
-Pa-ge 2 of 12 ECosxfO 12 Revision Pacz 83 et 138 EPIX 4.0 0
Failure Summary Report Manufacturer: Crane Co Generic Model Number: 3888 Unit: Dresden 2 MR System: Standby Liquid Control MNextM Dresden 2 Failure Number: 245 Bookmarks:
Abstract Abstract Contact Equipment Details Dresden 2-Failure Number :245 03/09/1998 10:30:00 AM - No plant effect, from refueling. No generation capability was lost. A Crane Co model 3888XU (3888 ), failure caused the event. Standby Liquid Control valves, dampers, 2-1101 internal leakage when fully seated.
Contact Daniel Oakley LLRT System Engineer 815 942-2920 3708 daniel.oakley@ ucm.com Equipment Details Component Causing Standby Liquid Control Failure:
Key:
Valves, dampers 2-1101-15 internal leakage when fully seated After 10288 days in service Industry Common Name: *SBLCS Cntmnt Isol Check Vatve Manufacturer: Crane Co Model: 3888XU Generic Model: 3888 Body Material: Austenitic Stainless STL-Other Function/Application: One-Way Flow Nominal Inlet Size (Range): 1/2 to 1.99 IN Operator: None Type (Parts List): Check Causes of Component 2-1101-15 none identified by investigation Failure.
Due to:
equipment age - invalid cause after 09/01/2001, normal, expected aging -
invalid cause after 09/01/2001 Function restored by:
replaced device Recurrence Prevented by:
actions to prevent recurrence not needed Associated Maintenance: Unplanned Manufacturer: Rockwell Int/ Flow Control Div Unit: Hatch 1 Generic Model Number: 36274 MR System: SBLC W
Mauatrr Rokw
_ _nlFo oto i
eei oe ubr 67 Manufacturer: Rockwell Int/ Flow Control Div Generic Model Number: 36274
Failure Summary Report Page 3 of 12 EC-053-1O12 Revision 0 Paae 84 of 138 ITopl IPrevi INexti Hatch 1 Failure Number:60 Bookmarlks:
Abstract Abstract Contact Equipment Details Hatch 1-Failure Number :60 03/1311999 12:00:00 PM - No plant effect, from cold shutdown. No generation capability was lost. A Rockwell Int/ Flow Control Div model 36274 (36274), failure caused the event SBLC valves, dampers, 1041 -F006-internal leakage when fully seated.
Contact TROUNG, THI SYS ENG 912 5371395 2468 Equipment Details Component Causing SBLC Failure:
Key:
Valves, dampers 1 C41 -F006 internal leakage when fully seated After4781 days In service Industry Common Name: CSBLCS Cntmnt Isol Check Valve Manufacturer: Rockwell Int/ Flow Control Div Model: 36274 Generic Mode!: 36274 Body Material: Austenitic Stainless STL-316 Function/Application: One-Way Flow Nominal Inlet Size (Range): 1/2 to 1.99 IN Operator: None Type (Parts List) : Check Causes of Component 1C41-F006 spring(s) loss of compression - inservice since 2/8/86 Failure.
Due to:
equipment age - invalid cause after 0910112001, normal, expected aging -
invalid cause after 09/01/2001 Function restored by:
repaired device (beyond recalibration) replaced piece part Recurrence Prevented by:
actions to prevent recurrence not needed Associated Maintenance: None Manufacturer: Velan Inc Unit: Nine Mile Point 2 Generic Model Number: B303-6W14MS MR System: Standby Liquid Control System 1 1p IreviN"xtl Nine Mile Point 2
" Nine Mile Point 2 Failure Number: 351 Failure Number : 351
Failure Summary Report Page 4 of 12 EC45 owt02 Revision o Pace 85 ci 13a Bookmarks:
Abstract Abstract Contact ument Details 0
Nine Mile Point 2-Failure Number :351 03/07/2000 3:20:00 PM - Outage impacted, from refueling. No generation capability was lost. A Velan Inc model B30346W14MS (B303-6W14MS), failure caused the event. Standby Liquid Control System valves, dampers, 2SLS'V1 0- internal leakage when fully seated.
Contact Tanguay, Thomas System Engineer 315-349-4428 TanguayT nimo.com Equipment Details Component Causing Failure:
Key:
Causes of Component Failure:
Associated Maintenance:
Standby Liquid Control System Valves, dampers 2SLS*V1 0 internal leakage when fully seated After 4906 days in service Industqy Common Name: *SBLCS Cntmnt Isol Check Valve Manufacturer: Velan Inc Model: B303-6W14MS Generic Modet: B303-6W14MS Body Material : Austenitic Stainless STL-316 Function/Application : One-Way Flow Nominal Inlet Size (Range): 2 to 3.99 IN Operator: None Type (Parts List): Check 2SLSV1 0 none identified by investigation Due to:
mechanical process, foreign material Function restored by:
operator actions taken repaired device (beyond recalibration)
Recurrence Prevented by; actions to prevent recurrence not needed None Manufacturer: Velan Inc Unit: Browns Ferry 3 Generic Model Number: W7234B13MS MR System: Standby Liquid Control-GE ITopl lPrevl INextl Browns Ferry 3 Failure Number: 200 Bookmarks:
Abstract Abstract Contact EauiDment Details Browns Ferry 3-Failure Number :200 03/26/2002 - No plant effect, from refueling. No generation capability was lost. A Hancock Mfg Co Inc model 0
5580 (5580 ), Velan Inc model W7234B1 3MS (W7234B1 3MS ), Atwood & Morrill Co. IncJXomox model 11462 (11462 ), Velan Valve Corp model B107144B02AA (B107144B02AA ), Anchor/Darling Valve Co. model 900/w9223821 a (900/W9223821A ), Anchor / Darling Co. model 900/W9223821 A (900/W9223821A ), failure W
5580 (5580 ), Veian Inc model W7234B1 3MS (W7234B1 3MS ), Atwood & Morrill Co. IncJXomox model 11462 i44 A00 1r Ih
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Failure Summary Report Page 5 of 12 EC-CI-012 Revlon 0 Paoe 86 Of 138 caused the event. High Pressure Coolant Injection-GE valves, dampers, 3-CKV-073-0609-internal leakage when fully seated; Standby Liquid Control-GE valves, dampers, 3-CKV-063-0526-internal leakage when fully seated; Feedwater-GE valves, dampers, 3-CKV-003-0554-internal leakage when fully seated; Main Steam-GE valves, dampers, 3-FCV-001 -0056-internal leakage when fully seated; Reactor Water Cleanup-GE valves, dampers, 3-CKV-069-0629-internal leakage when fully seated; valves, dampers, 3-CKV-069-0628-internal leakage when fully seated.
Contact Fredrick Nilsen LLRT Component Engineer 256-729-2958 2958 fjnilsen@tva.gov Equipment Details Component Causing Failure:
Key:
Causes of Component Failure:
Component Causing Failure:
Key:
Causes of Component Failure:
Feedwater-GE Valves, dampers 3-CKV-003-0554 internal leakage when fully seated After 9156 days in service Industry Common Name: Fdwtr Cntmnt Check Valve Manufacturer: Atwood & Morrill Co. IncJXomox Model: 11462 Generic Model: I 462 Body Material: Carbon Steel Function/Application: Flow Control (ind temp control)
Nominal Inlet Size (Range) :20 to 39.99 IN Operator: None Type (Parts List) : Check 3-CKV-003-0554 none Identified by investigation Due to:
mechanical process, leakage Function restored by:
repaired device (beyond recalibration)
Recurrence Prevented by:
supplemental testing performed High Pressure Coolant Injection-GE Valves, dampers 3-CKV-073-0609 internal leakage when fully seated After9156 days in service Industry Common Name: Primary Cntmnt Isol Valve Manufacturer; Hancock Mfg Co Inc Model: 5580 Generic Model: 5580 Body Material: Carbon Steel Function/Application: One-Way Flow Nominal Inlet Size (Range): 2 to 3.99 IN Operator: None Type (Parts List): Check 3-CKV-073-0609 none identified by investigation Due to:
mechanical process, leakage Function restored by:
repaired device (beyond recalibration)
Recurrence Prevented by:
supplemental testing performed W
repaired device (beyond recalibration)
Ad n-.--*_-a....
Failure Summary Report Page 6 of 12 EC.O53-1012 Revtsion 0 Pace 87 of 138 Component Causing Failure:
Key:
Causes of Component Failure:
Component Causing Failure:
Key:
Causes of Component Failure:
Component Causing Failure:
Key:
Main Steam-GE Vatves, dampers 3-FCV-001 -0056 internal leakage when fully seated After2375 days in service Industry Common Name: Primary Cntmnt Isol Valve Manufacturer Velan Valve Corp Model: B107144B02AA Generic Model: B1307144B02M Body Material: Carbon Steel Function/Application : Shutoff/lIsolation/Stop Nominal Inlet Size (Range): 2 to 3.99 IN Operator: Electric Motor/Servo (MOV)
Type (Parts List): Gate 3-FCV-001 -0056 none identified by investigation 3-FCV-00 -0056 seat Due to:
mechanical process, leakage Function restored by:
tested and restored to service Recurrence Prevented by:
engineering analysis performed Reactor Water Cleanup-GE Valves, dampers 3-CKV-069-0628 internal leakage when fully seated After 840 days in service Site Common Name: Primary Cntmnt Isol Valve Manufacturer Anchor / Darling Co.
Model: 9001W9223821 A Generic Model: 900DW9223821 A Function/Application : One-Way Flow Nominal Inlet Size (Range) : 4 to 11.99 IN Operator: None Program: Appendix J LLRT program SubType: Check-Swing Type (Parts List) : Check 3-CKV-069-0628 seat Due to:
mechanical process, leakage Function restored by:
replaced piece part Recurrence Prevented by; supplemental testing performed Reactor Water Cleanup-GE Valves, dampers 3-CKV-069-0629 internal leakage when fully seated After 840 days in service Site Common Name: Primary Cntmnt Isol Valve Manufacturer Anchor/Darling Valve Co.
Model: 900/w9223821 a Generic Model: 9001W9223821A Function/Apptication : One-Way Flow Nominal Inlet Size (Range): 4 to 11.99 IN Operator: None rijominai iniet bize tmange) 4 tO I I.U INJ OnArator: NonA
Failure Summary Reporit Page 7 of 12 Causes of Component Failure:
Component Causing Failure:
Key:
Causes of Component Failure:
Associated Maintenance:
T.MlI IPrev( INexti Browns Ferry 3 EC.053-1C12 Revision C Pawe 88 of 13 Program: Appendix J LLRT program Service: Clean water SubType: Check-Swing Type (Parts List) : Check Use: System, line, or component isolation check 3-CKV-069-0629 seat Due to:
mechanical process, leakage Function restored by:
replaced piece part Recurrence Prevented by:
supplemental testing performed Standby Liquid Control-GE Valves, dampers 3-CKV-063-0526 internal leakage when fully seated After 9156 days in service Industry Common Name: SBLCS Cntmnt Isol Check Valve Manufacturer: Velan Inc Model. W7234B13MS Generic Model: W7234B1 3MS Body Material: Carbon Steel Function/Application: One-Way Flow Nominal Inlet Size (Range):1/2 to 1.99 IN Operator: None Type (Parts List): Check 3-CKV-063-0526 none identified by investigation Due to:
mechanical process, leakage Function restored by:
recalibrated/adjusted device Recurrence Prevented by:
supplemental testing performed Unplanned Failure Number: 272 I
Bookmarks:
Abstract Abstract Contact Equipment Details Browns Ferry 3-Failure Number :272 03/01/2004 - No plant effect, from refueling. No generation capability was lost. A Crane Valve Prod/Crane Co Fr Chapman model CD-06005-8-06 (CD-06005-8-06 ), Velan Inc model W7234B1 3MS (W7234B1 3MS ), Velan Valve Corp model B1307144B02AA (B13071144B02AA), Anchor/Darling Valve Co. model 900/w9223821a (900/W9223821 A ), Anchor / Darling Co. model 900/W9223821 A (900/W9223821 A ), Pittsburgh - Des Moines Steel Co ( PDM ) model A (A ), General Electric Company model F01 (FO ), failure caused the event. High Pressure Coolant Injection-GE valves, dampers, 3-FCV-073-0026-internal leakage when fully seated; Standby Liquid Control-GE valves, dampers, 3-CKV-063-0526-internal leakage when fully seated; Radwaste-GE valves, dampers, 3-FCV-077-0002A-internal leakage when fully seated; Main Steam-GE valves, dampers, 3-FCV-001 -0056-Internal leakage when fully seated; Reactor Water Cleanup-GE valves, dampers, 3-CKV-069-0629-internal leakage when fully seated; valves, dampers, 3-CKV-069-0628-internal leakage when fully seated; Primary Containment-GE containment penetrations, air locks, hatches, 3-STRU-303-DW/HEAD-loss of pressure boundary function; containment penetrations, air locks, hatches, 3-EPEN-100-0101 C-loss of pressure boundary function.
W leakage when fully seated; Primary Containment-GE containment penetrations, air locks, hatches, 3-STRU-On'3 r%%eA11 n
A r%
^^n.,
h-.-4ftr& "e~not.^n- ^^ntainmanf ncnnatratinne air Inmlka Nzit-hce q_FDP9;K_
Failure Summary Report Page 8 of 12 EC0534012 Revwson 0 Pae 8S of 138 Contact Frederick Nilsen Containment Leak Rate Program Engineer 2958 fjnilsen @tva.gov 256-729-Equipment Details Component Causing Failure:
Key:
Causes of Component Failure:
Component Causing Failure:
Key:
Causes of Component Failure:
High Pressure Coolant Injection-GE Valves, dampers 3-FCV-073-0026 internal leakage when fully seated After9862 days in service Industry Common Name: 'IHPCI Suct From Supp Pool Isol Valve Manufacturer Crane Valve Prod/Crane Co Fr Chapman Model: CD-06005-8-06 Generic Model: CD-06005-8-06 Body Material: Carbon Steel Function/Application : Shutoff/lsolationlStop Nominal Inlet Size (Range) :12 to 19.99 IN Operator: Electric Motor/Servo (MOV)
Type (Parts List): Gate 3-FCV-073-0026 wedge Due to:
management, delayed implementation of corrective actions resource management, resources not available or insufficient Function restored by:
repaired device (beyond recalibration)
Recurrence Prevented by:
overhauled or refurbished equipment Main Steam-GE Valves, dampers 3-FCV-001 -0056 Internal leakage when fully seated After3081 days in service Industry Common Name: Primary Cntmnt Isol Valve Manufacturer: Velan Valve Corp Model: B107144802AA Generic Model: Bi 07144B02AA Body Material: Carbon Steel Function/Application : Shutoff/Isolation/Stop Nominal Inlet Size (Range) :2 to 3.99 IN Operator: Electric Motor/Servo (MOV)
Type (Parts List) : Gate 3-FCV-001-0056 disc 3-FCV-001 -0056 mechanical stop(s) 3-FCV-001 -0056 seat Due to:
desIgn, inadequate original design management, delayed implementation of corrective actions resource management, resources not available or insufficient W
resource management, resources not available or
Failure Summary Report Page 9 of 12 Component Causing Failure:
Key:
Causes of Component Failure:
Component Causing Failure:
Key:
Causes of Component Failure:
EC'OS3. 1012, Revtisn a Function restored by:
Paue 90g O g repaired device (beyond recalibration) tested and restored to service Recurrence Prevented by:
administrative controls applied or evaluated established plan for replacement of components Primary Containment-GE Containment penetrations, air locks, hatches 3-EPEN-100-0101C loss of pressure boundary function After 11596 days in service Site Common Name: Recirc Pump Power Electrical Penetration Manufacturer General Electric Company Model: F01 Generic Model: F01 Subcategory (Parts List): Electrical 3-EPEN-100-0101C sealant Due to:
equipment aging - nonmetallic parts, abnormal or accelerated wear Function restored by:
tested and restored to service Recurrence Prevented by:
engineering analysis performed Primary Containment-GE Containment penetrations, air locks, hatches 3-STRU-303-DW/HEAD loss of pressure boundary function After 11596 days in service Site Common Name: Drywell Head Manufacturer: Pittsburgh - Des Moines Steel Co ( PDM)
Model: A Generic Model: A Subcategory (Parts List) : Other 3-STRU-303-DW/HEAD gaskeVsealo-ring(s)
Due to:
equipment aging - metallic parts, normal wear Component Causing Failure:
Key:
Function restored by:
installed temporary alternative to device function Recurrence Prevented by:
engineering analysis performed written instructions or documents revised Radwaste-GE Valves, dampers 3-FCV-077-0002A internal leakage when fully seated After 9862 days in service Site Common Name: Primary Cntmnt Isol Valve Manufacturer: Velan Inc Model: B1-0641-2TS Generic Model: 0064B Body Material: Carbon Steel Function/Application : Shutoff/Isolation/Stop Nominal Inlet Size (Range) :2 to 3.99 IN Operator: Pneumatic (Diaphragm or Cylinder) (AOV)
W Nominal Inlet Size (Range) : 2 to 3.99 IN fw+
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Failure Summary Report Pag 10 of 12 EC.053-1012 Revwsin 0 Pameg1 of 138 Causes of Component Failure:
Component Causing Failure:
Key:
Causes of Component Failure:
Component Causing Failure:
Key:
Causes of Component Failure:
Type (Parts List) : Gate 3-FCV-077-0002A disc 3-FCV-077-0002A seat Due to:
equipment aging - metallic parts, normal wear Function restored by:
modified the design Recurrence Prevented by:
design changes implemented Reactor Water Cleanup-GE Valves, dampers 3-CKV-069-0628 internal leakage when fully seated After 1546 days in service Site Common Name: Primary Cntmnt Isol Valve Manufacturer Anchor I Darling Co.
Model: 900/W9223821A Generic Model: 9001W9223821A Function/Application: One-Way Flow Nominal Inlet Size (Range): 4 to 11.99 IN Operator: None Program : Appendix J LLRT program SubType: Check-Swing Type (Parts List): Check 3-CKV-069-0628 bonnet Due to:
installation, improper assembly installation, inadequate assembly or installation instructions Function restored by:
recalibratedladjusted device tested and restored to service Recurrence Prevented by:
supplemental checks or inspections performed Reactor Water Cleanup-GE Valves, dampers 3-CKV-069-0629 internal leakage when fully seated After 1546 days in service Site Common Name: Primary Cntmnt Isol Valve Manufacturer: Anchor/Darling Valve Co.
Model: 900/w9223821a Generic Model: 900/W9223821A Function/Application: One-Way Flow Nominal Inlet Size (Range): 4 to 11.99 IN Operator: None Program: Appendix J LLRT program Service : Clean water SubType: Check-Swing Type (Parts List): Check Use : System, line, or component isolation check 3-CKV-069-0629 seat insert Due to:
W Failure:
,jL~~-v uow~o~t seai inseri
Failure Summary Report Component Causing Failure:
Key:
Causes of Component Failure:
Associated Maintenance:
Page 11 of 12 EC43 -1012 Revision 0 Paw e2 o 138 equipment aging - nonmetallic parts, abnormal or accelerated wear Function restored by:
repaired device (beyond recalibration)
Recurrence Prevented by:
overhauled or refurbished equipment Standby Liquid Control-GE Valves, dampers 3-CKV-063-0526 internal leakage when fully seated After9862 days in service Industry Common Name: 'SBLCS Cntmnt Isol Check Valve Manufacturer Velan Inc Model: W7234B1 3MS Generic Model: W723481 3MS Body Material: Carbon Steel Function/Application: One-Way Flow Nominal Inlet Size (Range): 1/2 to 1.99 IN Operator: None Type (Parts List): Check 3-CKV-063-0526 disc 3-CKV-063-0526 spring(s)
Due to:
management, delayed Implementation of corrective actions Function restored by:
repaired device (beyond recalibration)
Recurrence Prevented by:
overhauled or refurbished equipment Planned Manufacturer: Velan Valve Corp Unit: Duane Arnold 1 Generic Model Number: P1220N4 MR System: Standby Liquid Control EWpH g-rrevA Duane Arnold 1 Failure Number:-167 Bookmarks:
Abstract Abstract Contact Eauipment Details Duane Arnold 1-Failure Number :167 11/03/1999 - No plant effect, from coad shutdown. No generation capability was lost. A Velan Valve Corp model P1 220N4 (P1 220N4 ), failure caused the event Standby Liquid Control valves, dampers, V26-0008-internal leakage when fully seated.
Contact Bowman, Bob Project Engineering, Mechanical 319-851-7729 n/a Equipment Details Component Causing Failure:
Key:
Standby Liquid Control Valves, dampers V26-0008 W
Component Causing Failure:
Va., -
.4-----
Wj& fn1%0
Failure Summary Re-port Page 12 of 12 ECOS3-01 2 Revision 0 Pace 93 of 138 internal leakage when fully seated After 9380 days in service Industry Common Name: 'SBLCS Cntmnt Isol Check Valve Manufacturer: Velan Valve Corp Model: P1220N4 Generic Model: P1 220N4 Body Material: Austenitic Stainless STL-31 6 Function/Application: One-Way Flow Nominal Inlet Size (Range) :1/2 to 1.99 IN Operator: Mechanical (Differential-Press Open/Spring-Force Close)
Type (Parts List) : Check V26-0008 Not yet determined Due to:
equipment aging - metallic parts, normal wear mechanical process, leakage Function restored by:
repaired device (beyond recalibration)
Recurrence Prevented by:
actions to prevent recurrence not needed Planned I
Causes of Component Fdilure:
Associated Maintenance:
INPO Equipment Performance and Information
.Exchange 4.0 Production Read Only
91-DRESDEN 3-Valves, dampers Page 1 of 2 EC-053.1012 Revision o Pace 94 of 138
-NPRDS=
Failure Report with Unit Information Go to: System Information 1j Component Information 11 Failure Information 1t Failure Narrative MEN=
G. Size (Inlet):
Unit Information Utility:
Unit:
NSSS:
System Information System:
Utility System:
Commonwealth Edison Company DRESDEN 3 General Electric Return to Top Standby Liquid Control-GE 1100 Component Information Component:
Utility Component ID:
Application:
Data Start Date:
In-Service Date:
Out-of-Service Date:
Manufacturer:
Mfr Model ID:
Mfr Model No:
Mfr Serial No.
Drawing No.
Safety Class Engineering Characteristics A. Type:
B. Operator:
C. Function/Application:
D. Body Material:
F. Nominal Inlet Size (Range):
1.500 IN H. Maximum Design Pressure:
J. Maximum Design Temperature:
User Data/Comments Data/Comments 1:
Return to Top Valves, dampers 3-1101-15
- SBLCS Cntmnt Isol Check Valve 07/01/1974 10/05/1971 Crane Co 3888 3888XU PID-M-364 S
Check None One-Way Flow Austenitic Stnls Std-Other 1/2 to 1.99 IN 1500.000 PSIG 575.000 DEGF G,M V User Data/Comments
91-DRESDEN 3-Valves, dampers Page 2 of 2 EC-053.1012 RcjIsion 0 Paae 95 Of 138 Data/Comments 2:
Data/Comments 3:
Data/Comments 4:
Data/Comments 5:
Failure Information Discovery Date:
Discovery Time:
End Date:
Plant Effect:
System Affected:
System Effect:
Severity Level:
Failure Mode:
Failure Detection:
Failure Cause Category:
Failure Cause
Description:
Corrective Action:
Documentation:
LER Report Number:
C,G USAS B16.5 Go 3-1101-15 Return to Top 02/19/1991 12:00 12/12/1991 G - Resulted in No Significant Effect PCA - Standby Liquid Control-GE D - Degraded Train/Channel K - Degraded IL - Internal Leakage B - Maintenance/Test I - Other Devices AB - Foreign Material/Substance (incid AJ before 4/94)
BG - Corrosion AG - Repair Component/Part N - Other Documents or Records are Not Available Failure Narrative Return to Top UNIT WAS IN A REFUELING OUTAGE WITH THE STANDBY LIQUID CONTROL ( SBLC)
TRAIN IN TEST. THE SBLC INBOARD INJECTION CHECK VALVE WAS BEING LOCAL LEAK RATE TESTED (LLRT ) AND FAILED AT 40 SCFH.TIHIS WAS NOT LLRT TESTED THE LAST REFUELING OUTAGE AND HAD TO BE TESTED DURING THIS CURRENT OUTAGE.THE TRAIN WAS DEGRADED BUT THE FAILURE HAD NO EFFECT ON THE UNIT.
THE FAILURE WAS DUE TO A BUILD UP OF CORROSION AND MATERIAL ON THE VALVE SEAT.
THE VALVE WAS DISASSEMBLED AND CLEANED AND WAS THEN SUCCESSFULLY RETESTED. (WR D96746)
Contact at Time of Failure John Reid Return to Top 815-942-2920 x2380 V
92-QUAD CITIES 1-Valves, dampers
. Page I of 2 Re~~fEC053-1 012 Re-AIsn C Pace 96 of 13S
, =NPRDS=
Failure Report with Unit Information Go to: System Information ll Component Jnfonnation ll Failure [nformation 11 Failure Narrative G. Size (Inlet):
Unit Information Utility:
Unit:
NSSS:
System Information System:
Utility System:
Commonwealth Edison Company QUAD CITIES I General Electric Return to Top Standby Liquid Control-GE 1100 Component Information Component:
Utility Component ID:
Application:
Data Start Date:
In-Service Date:
Out-of-Service Date:
Manufacturer:
Mfr Model ID:
Mfr Model No:
Mfr Serial No.
Drawing No.
Safety Class Engineering Characteristics A. Type:
B. Operator:
C. Function/Application:
D. Body Material:
F. Nominal Inlet Size (Range):
1.500 IN H. Maximum Design Pressure:
J. Maximum Design Temperature:
User Data/Comments Return to Top Valves, dampers 1-1101-16
- SBLCS Cntmnt Isol Check Valve Primary Cntmnt Isol Valve 07/01/1974 10/0711971 Crane Co 3888 3888-XU M40 S
Check None One-Way Flow Austenitic Stnls Stl-316 1/2 to 1.99 IN 900.000 PSIG 1125.000 DEGF WF Temperature:
112.1).UUUVEU14
92-QUAD CITIES 1-Valves, dampers Page 2 of 2 ECC053-101z RevisionO Pawe 7 of 138 i
I I
Data/Comments 1:
Data/Comments 2:
Data/Comments 3:
A, B, F F, 4 LLRT Failure Information Discovery Date:
Discovery Time:
End Date:
Plant Effect:
System Affected:
System Effect:
Severity Level:
Failure Mode:
Failure Detection:
Failure Cause Category:
Failure Cause
Description:
Corrective Action:
Documentation:
LER Report Number:
Return to Top 11/13/1992 12:00 06/10/1994 G - Resulted in No Significant Effect PCA - Standby Liquid Control-GE E - System Function/Operation Unaffected K - Degraded IL - Internal Leakage B - Maintenance/Test K - Unknown (included Code X prior to 4/94)
AD - Normal Wear (included AH before 4194)
AK - Valve Seat Condition (code added 4194)
AH - Replace Part(s)
N - Other Documents or Records are Not Available Failure Narrative Return to Top UNIT SHUTDOWN FOR REFUELING. DURING LOCAL LEAK RATE TEST, STANDBY LIQUID CONTROL ( SBLC ) OUTBOARD ISOLATION VALVE (1 OF 2) FAIL TO MAINTAIN REQUIRED LEAK RATE INTEGRITY. VALVE LEAKED BY AT 16. 0 SCFH.
REQUIRED ACTION LIMIT IS 10. 0 SCFH. THESE CHECK VALVES ARE DESIGNED TO ISOLATE THE REACTOR FROM ANY LINE BREAK IN THE SBLC SYSTEM TO PREVENT LOSS OF VESSEL INVENTORY WHILE THE VESSEL IS AT PRESSURE. DUE TO SATISFACTORY INTEGRITY OF THE INBOARD ISOLATION CHECK VALVE, LEAKAGE DEGRADED ONLY ABILITY OF THIS CHECK VALVE TO ISOLATE THE VESSEL, THE ISOLATION CAPABILITY OF THE LINE WAS NOT DEGRADED. UNIT WAS NOT AFFECTED BECAUSE A SAFETY EVALUATION WAS PERFORMED WHICH ALLOWED CONTINUED OPERATION AT THE MEASURED LEAK RATE OF 16. 0 SCFH UNTIL THE NEXT SCHEDULED OUTAGE.
ON DISASSEMBLY THE DISC WAS FOUND NOT SEATING PROPERLY AND THE DISC WAS SCORED WHERE IT CONTACTED THE SEAT. ROOT CAUSE IS UNKNOWN. SUSPECTED CAUSES INCLUDE NORMAL WEAR AND EROSION. 1 THE IN-BODY SEATS WERE LAPPED. THE DISC AND DISC GUIDE WERE REPLACED. THE VALVE WAS REASSEMBLED AND INSTALLED. A LOCAL LEAK RATE TEST WAS PERFORMED AND PASSED AT 2. 9 SCFH. ( Q04090)
Contact at Time of Failure Kristal Moore Return to Top 309-654-2241 x3070 W
92-HOPE CREEK I-Valves, dampers Page 1 of 2 EC-053-10T2 Revisin o Pane 98 0138
,=NPRDS=
Failure Report with Unit Information Go to: System Information lo Component Information ll Failure Information ll Failure Narative
_._N G. Size (Inlet):
Unit Information Utility:
Unit:
NSSS:
System Information System:
Utility System:
Public Service Electric and Gas Company HOPE CREEK I General Electric Return to Top Standby Liquid Control-GE BH Component Information Component:
Utility Component ID:
Application:
Data Start Date:
In-Service Date:
Out-of-Service Date:
Manufacturer:
Mfr Model ID:
Mfr Model No:
1fr Serial No.
Drawing No.
Safety Class Engineering Characteristics A. Type:
B. Operator:
C. Function/Application:
D. Body Material:
F. Nominal Inlet Size (Range):
1.500 N H. Maximum Design Pressure:
J. Maximum Design Temperature:
User Data/Comments Data/Comments 1:
Return to Top Valves, dampers IBHV-029
- SBLCS Cntmnt Isol Check Valve 12/20/1986 06/28/1986 Rockwell Int/ Flow Control Div 36274 1.5-36274T1 P&ID M-48-1 S
Check None One-Way Flow Austenitic Stnls Stl-316 1/2 to 1.99 IN 1525.000 PSIG 575.000 DEGF S
W User Data/Comments
92-HOPE CREEK I-Valves, dampers Page 2 of 2 _
EC-0531012 Revision a Paae 9 of t138 Data/Comments 2:
Data/Comments 3:
Data/Comments 4:
A,F ASME IlI R3 0
Failure Information Discovery Date:
Discovery Time:
End Date:
Plant Effect:
System Affected:
System Effect:
Severity Level:
Failure Mode:
Failure Detection:
Failure Cause Category:
Failure Cause
Description:
Corrective Action:
Documentation:
LER Report Number:
Return to Top 10/07/1992 12-00 10/18/1992 G - Resulted in No Significant Effect PCA - Standby Liquid Control-GE E - System Function/Operation Unaffected K - Degraded IL - Internal Leakage B - Maintenance/Test H - Age/Nonnal Usage AD - Normal Wear (included AH before 4/94)
AG - Repair Component/Part N - Other Documents or Records are Not Available Failure Narrative Return to Top THE PLANT WAS IN MODE 5, REFUELING OUTAGE 4, WHEN THE INSERVICE TEST GROUP REPORTED THE STANDBY LIQUID CONTROL ( SBLC) SYSTEM INBOARD CONTAINMENT ISOLATION CHECK VALVE, I OF 2, FAILED THE LOCAL LEAK RATE TEST ( LLRT) DEGRADING THE CONTAINMENT FUNCTION OF THE VALVE. THERE WAS NO SIGNMICANT AFFECT ON THE OPERATION OF THE SYSTEM OR PLANT.
THE VALVE INTERNALS HAD LIGHT DEPOSITS OF DIRT THAT PREVENTED PROPER VALVE SEATING THE DIRT WAS ATTRIBUTED TO NORMAL WEAR.
THE SEAL WELD WAS CUT, THE VALVE DISASSEMBLED, INSPECTED, CLEANED INTERNALS, PERFORMED BLUE CHECK, INSTALLED INTERNALS AND REWELDED PER CODE JOB PACKAGE, SATISFACTORILY TESTED AND RETURNED TO SERVICE. (92 42 ) ; WO-921007215 Contact at Time of Failure Benjamin Tashjian Return to Top 609-339-5582 w
90-DRESDEN 2-Valves, dampers Page 1 of 2 ECc053-1012 Ravisin 0 PaOe 100 of 138
, =NPRDS=
Failure Report with Unit Information Go to: System Information ll Component Infonnation 11 Failure Information 11 Failure Narrative EEN=7 G. Size (Inlet):
Unit Information Utility:
Unit:
NSSS:
System Information System:
Utility System:
Commonwealth Edison Company DRESDEN 2 General Electric Return to Top Standby Liquid Control-GE 1100 Component Information O Component:
0 Utility Component ID:
Data Start Date:
In-Service Date:
Out-of-Service Date:
Manufacturer:
Mfr Model ID:
Wr Model No:
Mfr Serial No.
Drawing No.
Safety Class Engineering Characteristics A. Type:
B. Operator:
C. Function/Application:
D. Body Material:
F. Nominal Inlet Size (Range):
2.500 IN H. Maximum Design Pressure:
J. Maximum Design Temperature:
O User Data/Comments Data/Comments 1:
Data/Comments 2:
Return to Top Valves, dampers 2-1101-4 07/01/1974 01/07/1970 03/15/1994 Crane Co 47-1/2 47.5U PID-M-33 S
Globe Manual Shutoff/Isolation/Stop Carbon Steel 2 to 3.99 IN 150.000 PSIG 500.000 DEGF F,N A, F 1
br vssse.w (a
Ynstsl(nmmFe.nt-, I F. N
90-DRESDEN 2-Valves, dampers Page 2 of 2 EC4053-1012 Revisan 0 Pace 101 c 138 Data/Comments 4:
Data/Comments 5:
So 1101-4 Failure Information Discovery Date:
Discovery Time:
End Date:
Plant Effect:
System Affected:
System Effect:
Severity Level:
Failure Mode:
Failure Detection:
Failure Cause Category:
Failure Cause
Description:
Corrective Action:
Documentation:
LER Report Number:
Return to Top 1010711990 12:00 12/17/1990 G - Resulted in No Significant Effect PCA - Standby Liquid Control-GE C - Loss of One or More Train/Channel Functions J - Complete FC - Failed to Close B - Maintenance/Test J - Other Devices BF - Flow Obstruction (included BM before 4/94)
BE - Dirty AG - Repair Component/Part N - Other Documents or Records are Not Available Failure Narrative Return to Top UNIT WAS IN COLD SHUTDOWN WITH STANBBY LIQUID CONTROL ( SBLC ) TRAIN IN TEST. MAINTENANCE AND OPERATIONS PERSONNEL WERE PERFORMING AN OPERABILTY TEST, WHEN SBLC VALVE 1101 4, WHICH IS NORMALLY OPEN WOULD NOT GO CLOSED. THE VALVE WAS TRIED A SECOND TIME WITH NO SUCCESS.THE TRAIN ISOLATION FUNCTION WAS LOST BUT THERE WAS NO PLANT AFFECT.
THE FAILURE TO THE VALVE WAS DUE TO BUILD UP OF BORON IN THE INTERNAL PARTS OF THE VALVE.THIS BUILD UP OF BORON PREVENTED THE VALVE FROM OPERATING AS INTENDED.
THE VALVE WAS REMOVED, CLEANED AND WHELE THE VALVE WAS DISASSEMBLED THE PACKING WAS ALSO REPLACED.THE VALVE WAS REINSTALLED AND SUCCESSFULLY TESTED FOR OPERABILITY THE VALVE WAS THEN RETURNED TO SERVICE. (WR 88244)
Contact at Time of Failure John Reid Return to Top 815-942-2920 x2380 W
86-SUSQUEHANNA I -Valves, dampers Page 1 of 2 ECt53.¶0 2
FRsjston O Pace 102 of 138
- =NPRDS=
Failure Report with Unit Information Go to: System Information ll Component Information ll Failure Information 11 Failure Narrative G. Size (Inlet):
Unit Information Utility:
Unit:
NSSS:
System Information System:
Utility System:
PP&L, Inc.
SUSQUEHANNA I General Electric ReturnAtoo Standby Liquid Control-GE 153A Component Information Component:
Utility Component ID:
Data Start Date:
In-Service Date:
Out-of-Service Date:
Manufacturer:
Mfr Model ID:
Wr Model No:
Mfr Serial No.
Drawing No.
Safety Class Engineering Characteristics A. Type:
B. Operator:
C. Function/Application:
D. Body Material:
F. Nominal Inlet Size (Range):
3.000 IN H. Maximum Design Pressure:
J. Maximum Design Temperature:
User Data/Comments Data/Comments 1:
Data/Comments 2:
Return to Top Valves, dampers 148F031 06/08/1983 06/08/1983 03/15/1994 Aloyco Div.iWalworth Co.
N-226-SP P&W]D-M-148 S
Gate Manual Shutoff/Ilsolation/Stop Austenitic Stnls Stl-316 2 to 3.99 IN 100.000 PSIG 150.000 DEGF X
F, 4 W
User j1,uuz1...oj11"rUii.
OP 1%tn/fllf9'flmpno-nf I
Y
86-SUSQUEHANNA I-Valves, dampers PaeC.25of1 2 Data/Comments 3:
Data/Comments 4:
Data/Comments 5:
Failure Information Discovery Date:
Discovery Time:
End Date:
Plant Effect:
System Affected:
System Effect:
Severity Level:
Failure Mode:
Failure Detection:
Failure Cause Category:
Failure Cause
Description:
Corrective Action:
Documentation:
LER Report Number:
EC.053-1tO12 Revision 0 Pa 1032 of 139 ASME-SEC.M Wo C41-1F031 Return to Top 08/12/1986 12:00 09/10/1986 G - Resulted in No Significant Effect PCA - Standby Liquid Control-GE D - Degraded Train/Channel K - Degraded FC - Failed to Close B - Maintenance/Test K - Unknown (included Code X prior to 4/94)
BB - Mechanical Damage (included BK before 4/94)
BC - Out of Mechanical Adjustment AG - Repair Component/Part N - Other Documents or Records are Not Available
, Failure Narrative Return to Top ON AUGUST 12,1986, THERE WAS SODIUM PENTABORATE SOLUTION LEAKING FROM THE STANBY LIQUID CONTROL ( SBLC ) STORAGE TANK INTO THE SBLC TEST TANK.
TEST TANK OUTLET VALVE 148F031 WAS FOUND TO BE LEAKING THROUGH ALLOWING SBLC TANK LEVEL TO RISE.
AFTER INVESTIGATION IT WAS DETERMINED THE CAUSE OF THIS EVENT WAS DUE TO THE BOTITOM SIDE OF THE VALVE DISC MAKING CONTACT WITH THE BOTTOM OF THE VALVE BODY. ACTUAL ROOT CAUSE UNKNOWN.
GROUND THE VALVE DISC AND PERFORMED BLUE CHECK ON VALVE BODY UNTIL NO CONTACT WAS NOTED. STROKED VALVE AND VERIFIED NO BONNET GASKET LEAK AT SYSTE.M OPERATING PRESSURE. VALVE REIURNED TO SERVICE.
Contact at Time of Failure Terry Constance Return to Top 610-774-7608
EC-053-1C12 Revision 0 Paoe 104 o0 138 PP&L CALCULATION SHEET Dept.
PROJECT Carc. No.
EC 053:1012 Date Assessment of SBLC Rev. No.
0 Designed By,G Kwal System for Suppression Checked Pool pH Control Sh. No.
1-of 14-ATTACHMENT NO. 3 l
Susquehanna - Valve Operating Experience
EC.053-1012 Revision C Pace 105 of138 Kowal, George M From:
Missien, Ian C Sent:
Monday, March 21, 2005 3:59 PM To:
Kowal, George M Cc:
Vazquies, Ronald Allen; Maertz, Gerald G
Subject:
Standby Liquid Control (SLC) Outboard Containment Isolation Vatve, 1(2)48F0O7 Mr. Kowal, The SLC O/B Containment Isolation Valves, 1(2)46F007 have performed very well for PPL Susquehanna, LLC. A review of work history on these valves shows no failures. Typically, the leakage rates for these valves Is nil (0-10 cc/min).
Reference SE-1(2)59-047 (LLRT of Penetration X42) and the work history in NIMS via the CMPINFO screen.
Ian C. Missien 254-3396
PP&L,-
NIKS Component Data Sheet EC-053-1012 CP B3n ORCPE]CDAl Paos 10 oft 138 208 ST~DBT LICOMTO PMP Parent IDt Ey.:
153A Kanufactureri UNION PNP Model NoR.
2X3 TD-60 TRIPLEX Part No.s Serial No.:
Install Date:
TED 284222 26-JAN-1996 ASM-:
Y ASEC:
III Q:
Q
- Q:
N CcmW. Type:
PUMP Design 6tatuaw ASfLT Unit I 1
Area 29 Blev i149 Act. Clevs 750.5 Room :
I-513 Bldg :
RX Col/Line a 7S26.5/4NT Azimuth a Fail Code:
28 Maint Rules 1
CrIticality:
1 Duty Cycle:
Environment:
Loc a
==
Description:==
~Relateda(co0one Relationship MD Name Component Type IS BLOCKED BY 1B236081 STANDBY LIQUID CONTROL INJECTION PUMP SUBPNL A 1P208A BKR IS POWERED BY 28236081 STANDBY LIQUID CONTROL INJECTION PUMP WUBPNL A 1P2O0A BKR Category anae Value unit KOM MOTOR SPEED NULL Revolutions NOM POWER RATING 40 hp NOX SCAFFOLDING HEIGHT O0.0 foot NOM VOLTAGE 460 volt AC Category Name Value Unit N/A N/A N/A N/A N/A N/A NOM NOM N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A NON NOM MOTOR TYPE MANUFACTURER MODEL NUMBER SERIAL NUMBER MOTOR FRAME ORIENTATION STATOR FULL LOAD AMPS MOTOR LOCKED ROTOR AMPS MOTOR PHASE STATOR INSUL rHERMAL CLASS MOTOR ENCLOSURE TYPE MOTOR SERVICE FACTOR MOTOR TEMPERATURE RISE MOTOR SPACE HEATERS (Y/N)
OIL COOLING COILS UPPER OR O8 BEARING TYPE.
LOWER OR IB BEARING TYPE UPPER OR OB BEARING NO.
UPPER OR 08 BEARING CAPACITY.
LOWER OR 1 BEARING CAPACITY DC MOTOR FIELD AMPS DC MOTOR WINDING AMPS NULL NULL NULL NULL NULL NULL NULL NULL NULL NULL LULL NULL NULL NULL NULL NULL NULL NULL NULL NULL NULL NULL NULL n/a n/a n/a n/a n/a n/a Amp Amp n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a AMp Amp nTbmePon-t-Lube Location Lube Component Catalog Na=e BEARINGS MOTOR ALVANIA RL i 2 Catalog No.
0000935656 0091202198 Quantity U/K 7
PAC GR HARMONY 68 AW (DRUM)
P.acge 1 of A
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v;U&nL soam D1%V1k1AtlJN Kt^)>A ALVANTA RL i 2 Report Date: 23-MAR-2005 00 0 35 5
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PF&4 - NIXS Component Data Sheet CPX -
RCPECDA1 PaM 107 Of 1a CRANKCASE CRANKCASE HARMONY 68 AW (DRUM) 0091202198
?
Lateat ID Sheet Rev.
Rev.
AS No.
AS Sheet AZ Rev.
Description D107315 1
19 N
E-166 1
19 SCHEMATIC DIAGRAM STANDBY LIQUID CONTROL S E106179 5
26 Y
M-29-5 1
26 PLANT DESIGN DRAWING REACTOR BLDG AREA 29 E106253 1
27 N
M-148 1
27 P&ID STANDBY LIQUID CONTROL lOM5 1
2 N
M1-C41-221 1
2 TRIPLEX POWER PUMPS 7D-60 OR STANDBY LIQUI Type Name Description IST IST PROGRAM GROUP 1STP IST UNIT 1 PUMP GROUP NSEFEG IA SLC PM2 FEC NSEFEG 13236 REPORT KPRDS REPORTABLE GROUP Designs Physicals 1P208A
.ag 2 o_2Rpr ae 3MR20 Page 2 of 2 Report Date: 23-MAR-2005
PP&rl.-. NIMS I
EC-053-1012 Component Data Sheet RevsloriO CPX -
RCPECDDA1 Pawe 108 of 138 4
107 Parent ID:
eye:
Manufacturer:
Model NO.;
Part No.s Serial No.z Znstall Dates 153A BORG WAR TBD 08-MAR-1996 ASMEs Y
ASEC, IIIN3 0:
Q 1EQ x Colp. Type CR Design Status; ASBLT Unit Areas Elev Y
Act. zlev:
Room z Bldg s Col/Line t fticuth t i
26 739 7}39 1-400 CoNT Fail Coder Iaint Rule Criticality:
Duty Cycl-s Environment:
lB 1
IS 170 Lao:
Dencriptiors:
DesigI1 Gb Nacter.ist..
5 Category N/A N/A NORM N/A N/A NOM NOM NORM N/A N/A N/A Name PIPE CLASS PIPE LINE ID PRESSURE PIPE SCHEDULE BOXNET ATTACHMENT SCAFFOLDING HEIGHT SIZE TEMPERATURE VALVE TO PIPE ATTACHMENT VALVE CLASS VALVE OPERATOR TYPE Value DCA 106.
1005 SOS SLWLD 7.0 1.50 547 SOCKET WELD CCA SPRING OPERATED Unit n/a n/a psi n/a n/a foot inch deg F n/a n/a n/a Phs ca haratr Itc Category Name Value N/A N/A NOM NOM NOM NOM N/A NOM NOff KOM NOM NOM N/A NOM NOM NOM INOM N/A NOM N/A N/A N/A N/A N/A N/A N/A VALVE BODY MATERIAL VALVE TRIM MATERIAL STEM OUTSIDE DIAMETER STUFFING BOX INSIDE DIAMETER STUFFING BOX DEPTH LEAKCOFF PORT DEPTH LEAROFF ACTIVE LANTZRN RING HEIGHT STUD OUTSIDE DIAMETER
.NUT SIZE CRANE B-FACTOR GLAND LENGTH NUMBER OF STUDS LOWER BUSHING HEIGHT UPPER BUSHING HEIGHT PACKING SET HEIGHT (REPACK)
N`UMBER OF WASHERS/STUD VALVE PACKING TYPE (REPACK)
PACKING STRESS PACKING CONFIGURATION (REPACK)
TRANSFER RATIO (REPACK)
PACKING COEFFICIENT OF FRICTION (REPACK)
LOWER BusHING CAT
- UPPER BUSHING CAT
- PRIKARY PACKING CAT N FLAT WASHER CAT #
SA182-F316 STELL 0
0 NULL NULL NULL NULL NULL NULL NULL NULL NULL NULL NULL 0
NULL NULL 1
NULL 0
0 Uni t n/a n/a inch inch inch inch n/a inch inch inch n/a inch n/a inch inch inch n/a n/a lbs n/a n/a n/a n/a n/a n/a n/a NULL NULL NULL NULL Page N/A N/A 1 of 2 UPPER BUSHING CAT #
PRIMRY PACKING CAT U NULL NULL Report Date: 14-MAR-2005 n/a n/a
PP&I -
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RCPECDAI.
Category Name Value Unit N/A LIVE LOAD WASHER CAT #
NULL n/a NIA LANTERN RING CAT #
NULL n/a NOM PACKING SET HEIGHT (RETORQUE) 0 inch NON PACKING STRESS (RSTORQUE) 1 psi N/A TRANSFER RATIO (RETORQUE) 0 n/a N/A PACKING COEFFICIENT OF FRICTION 0
n/a (RETORQUE)
I I
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Quantity U/N Latest SD Sheet Rev.
Rev.
AR No.
AZ Sheet AZ Rev.
Description E106253 1
27 N
M-148 1
27 P&ID STANDBY LIQUID CONTROL IOM216 1
a N
P14B-S8 1
8 1 & 1 1/2 & 2 INCH STAINLESS GATE & Y TYPE FF110470 1001 3
Y P14B-10 1
3 ASSEMBLY 1 1/2 INCH Y TYPE LIFT CHECK VALV Type Namoe Description COND ENVIRONMENTAL CONDITION GROUP 6 100 -
140 DEGREES F/HIGH HUMIDITY COND RADIOLOGICAL CONDITION ZONE 5 DOSE RATE >100 =ren/hr.
GROUP IST IST PROGRAM GROUP NSEFEG Primary Containment Isolation Valves NSEPEG UNIT 1 SLC SYS FEG REPORT NPRDS REPORTABLE GROUP SURV LOCAL LEAK RATE TESTING GROUP Pre k Post LLRT required IAW MDAP-QA-0412 SURV VALVE I5}
CATAGORIES A and C apply Requirement Source Type Level LEAK RATE TESTING REQUIRED (LLRT/ILRT)
LEAK RATE TESTING LEAK RATE TESTING Design PROGRAM ione Nazis Status Type zone Uae Cczmant RADs RADIATION ZONE V RAD IN Design:
Physicals 148F007 Manufacturer:
Eng. Notes:
Type Covint Text Page 2 of 2 Report Date: 14-MAIZ-2005
PP&L -
NIMS Component Data Sheet.
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Sys :
Manufacturer:
Model So.:
Part No..
Serial No.g Install Dates 153A BORG WAR P/N 74680 TBD 17577 26-JAN-1996 ASME:
Y ASEC:
III,N3 0 Q EQ:
N Comp. Type GT Design Statuss ASBLT Act.
- Col, AZ Unit : 1 Area 1 26 916v :
738 I 1levs 742 Po=m a I-400 E1dg
- CNTMT Fail Code:
Maint Rules Criticality:
Duty Cycle:
Environnent:
1B 1
1
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inuth I 15 175 Loc s Descriptions STANDBY LIQUID CONTROL INJ ISO Desig Gaaacteist~ic Category Naxe Value Unit N/A N/A NORM N/A N/A KOM NOM NORM N/A N/A N/A PIPE CLASS PIPE LINE ID PRESSURE PIPE SCHEDULE 8ONNET ATTACHMENT SCAFFOLDING HEIGHT SIZE TEMPERATURE VALVE TO PIPE ATTACHMENT VALVE CLASS VALVE OPERATOR TYPE DCA 106 1005 8OS SLiWW 0.0 1.50 547 SOCKET WELD CCA HAND OPERATED n/a n/a psi n/a n/a foot inch deg F n/a n/a n/a Physical~haacte~is-ice Category N/A KOM N/A N/A NOM NOM NOM NOM N/A NOM NON NOM NOM SOM N/A NON NOM NON j
NOM N/A I
OM N/A N/A N/A N/A l
N/A N/A Name VALVE BODY MATERIAL SUGGESTED NUT TORQUE VALVE STEM MATERIAL VALVE TRIM MATERIAL STEM OurSIDE DIAMETER STUFFING BOX INSIDE DIXMETER STUFFISG BOX DEPTH LEAXOFF PORT DEPTH LEAXOFF ACTIVE LANTERN RING HEIGHT STUD OUTSIDE DIAMETER NUT SIZE CRANFE *3r FACTOR GLAND LENGTH NUMBER OF STUDS LOWER BUSHING HEIGHT UPPER BUSHING HEIGHT PACKING SET HEIGHT (REPACK)
NUMBER OF WASHERS/STUD VALVE PACXING TYPE (REPACK)
PACKING STRESS PACKING CONFIGURATION (RXPACX)
TRANSFER RATIO (REPACK)
PACKING COEFFICIENT OF FRICTION (REPACK)
LOWER BUSHING CAT #
UPPER BUSHING CAT #
Value SAI82-F316 85.a SA564-630 STALL 0.875 1.375 1.625 NULL NULL KNLL 0.ooa 1.25 NULL NULL 0
0.312 NULL 1.25 NULL COMPOSITE 4000 52
.8S
.05 Unit n/a ft-lbs n/a n/a inch inch inch inch n/a inch inch inch n/a inch n/a inch inch inch n/a n/a lbs n/a n/a n/a NULL NULL n/a n/a Page N/A 1 of 2 (REPACK)
LOWER BUSHING CAT #
Report Date: 14-MAR-2005 n/a NULL
PP&L -
NIMS Component Data Sheet ECt053-1012 Revision 0 Paw I1I of 138 CPX -
RCPECDAl r
Physical. ha.racter.ist4cu Category Name N/A N/A N/A N/A NON NOM N/A N/A PRIMARY PACKING CAT #
FLAT WASHER CAT #
LIVE LOAD WASHER CAT #
LANTERN RING CAT I PACKRING SET HEIGHT (RETORQUE)
PACKING STRESS (RETORQUE)
TRANSFER RATIO (RBTORQUE)
PACKING COEFFICIENT OF FRICTION (RETORQUE)
Value 00910218476 NULL NULL NULL 0
1 0
0 unit n/a n/a n/a n/a inch psi n/a n/a Lube oint~
Lube Location Lube Component Catalog Name Catalog No.
Quantity U/X Latest ID Sheet Rev.
Rev.
AX No.
AB Sheet AZ Rev.
Description E106253 1
27 N
M-14e 1
27 P&ID STANDBY LIQUID CONTROL IOM216 1
a N
P14B-58 1
8 1 & 1 1/2 & 2 INCH STAINLESS GATE & Y TYPE FF110470 801 13 Y
P14B-8 1
13 ASSEMBLY 1 1/2 INCH GATE VALVE Type Name Description COND ENVIRONMENTAL CONDITION GROUP 6 100 -
140 DEGREES F/HIGH HUMIDITY COND RADIOLOGICAL CONDITION ZONE 5 DOSE RATE >.1200 mrem/hr.
GROUP NSEFEG UNIT 1 SLC SYS FEG Zone Name Status Type Zone Use Cooment RAD5 RADIATION ZONE V kAD IN Design BUSHING INCLUDED IN PACKING SET Physical:
BUSHING INCLUDED IN PACKING SET Manufacturer; Eng. Notes:
Ad
.i na e t Type Comment Text OPS LOCATIO LOCI. AZ175 R742' OPERATIONS (FC)
Page 2 of 2 Report Date:
14-MAR--2005 Page 2 of 2 Report Date: 14 MR2005
PP&L. -
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Y ASECS IItNB Q:
Q I02 N
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Type:
Nov Design Statuss ASBLT Unit Area :
Elev I Act. Xlev:
Room Bldg:
Col/Line, Azimuth:
I 29 749 752 I-SQ6 RX IS25/14WT Fail Codes 1i Naint Rule:
1 Criticality:
1 Duty Cycle:
Environments Loc:
==
Description:==
SLC ISO VLV Relationship ID Name Component Type IS BLOCKED BY 1B236064 SELC 03 INJECTION VLV HV-140F006 8KR SUBPNL IS POWERED BY 18236064 SBLC OB INJECTION VLV HV-148F006 BER SUBPNL Category Name Value Unit NOK MOTOR SPEED NULL Revolutions N/A PIPE CLASS DCA n/a N/A PIPE LINE S1 106 n/a SORM PRESSURE 1005 psi N/A PIPE SCHEDULE SOS n/a N/A 0ONNET ATTACHMENT SLWlD a/a NOI SiZe 1.50 inch NORM TEMPERATURE 547 deg F N/A VALVE TO PIPE ATTACHMENT SOCKET WELD n/a N/A VALVE CLASS CCA n/a N/A VALVE OPERATOR TYPE MOTOR OPERATED n/a Cateoorv Name Value Unit I
N/A N/A N/A NOV N/A N/A N/A N/A N/A N/A
! N/A N/A lNOM l
NOM N/A N/A N/A N/A N/A N/A I
NfA ACTUATOR ORDER NO.
ACTUATOR SIZE VALVE BODY MATERIAL REMAINING GLOAND TAKE-UP FLAT WASHnR INSTALLED (Y/N)
LIVE LOADED (Y/N)
MOTOR TYPE MANUFACTURER MODEL NUMBER SERIAL NEMER MOTOR FRAME ORI3NTATION STATOR PULL LOAD AMPS MOTOR LOCXED ROTOR AMPS MOTOR P'ASE STATOR INSUL THERMAL CLASS MOTOR ENCLOSURE TYPE MOTOR SERVrCE FACTOR MOTOR MPERATUR-E RISE MOTOR SPACE REATERS (Y/N?
OIL COOLING COTLS 3A4681A SMB-OOO SA182-F316
.3125 y
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NULL n/a N/A LOWER OR IS BEARING TYPE NULL nf/a
-S/A UPPER OR 0 BEARING NO.
NULL n/a N/A LOWER OR IB BEARING NO.
NULL n/a N/A UPPER OR OB BEARING CAPACITY.
NULL n/a N/A LOWER OR IS BEARING CAPACITY NULL n/a NOM DC MOTOR FIELD AMPS NULL AMp NOM DC MOTOR WINDING AMPS NULL Amp NOM MOTOR VOLTAGE 460 volt NOM MOTOR HORSEPOWER
.17 hp NOM MOTOR START TORQUE 5
ft-lbs NOM MOTOR RUN TORQUE 1
ft-lbs NOM MOTOR SPEED 850 rpm KOM MOTOR DUTY RATING ismM n/a NON MOTOR INSUL TYPE/CLASS B
n/a NOM MOTOR FRAME M48 n/a NOM MOTOR FULL LOAD AMPS 1
Amp NOM MOTOR LOCKED ROTOR AMPS 2
Azp YOM MOTOR TE.MPERATVRE 40 deg C NOM SUGGESTED NUT TORQUE 59.0 ft-lbs NON POWER RATING 0.17 hp KIN LOWEST ALLOWED TORQUE SWITCH SETTING 1.5 n/a WAX HIGHEST ALLOWED TORQUE SWITCH SETTING 2.5 n/a NOM SPRING PACK GAP
.305 inch NON SPRING PACK NUMBER OF WASHERS 17 n/a N/A VALVE STEM MATERIAL SA564-630 n/a NOM SPRING PACK WASHER THICKNESS
.065 n/a N/A VALVE TRIM MATERIAL STELL n/a NOM TORQUE SWITCH ACTUAL OPEN SETTINGS 1.5 n/a NOM TORQUE SWITCH ACTUAL CLOSE SETTINGS 1.5 n/a NOM MOTOR PINION TEETH 22 n/a NOM WORM GEAR TEETH 23 n/a NOX VTR PINION TO WSG RATIO 1.04 n/a NOM VOLTAGE 460 volt AC NON STEM OUTSIDE DIAMETER 0.937 inch NO.M STUFFING BOX INSIDE DIAMETER 2.062 inch KOm STUFFING BOX DEPTH 2.125 inch NOM LEAKOFF PORT DEPTH N/A inch N/A LEAKOFF ACTIVE N/A n/a NON LANTERN RING HEIGHT N/A inch NON STUD OUTSIDE DIAMETER 0.75 indch NOM NUT SIZE 1.25 inch NOM CRANE "B" FACTOR 91 n/a NOM GLAND LENGTH NEeD inch N/A NU1EaR oF STUDS 2
n/a SOM LOWER BUSHING HEIGHT
.437 inch NOM UPPER BUSHING HEIGHT U/A inch NOM PACKING SET HEIGHT (REPACK) 1.25 inch NOM NUMBER OF WASHERS/STUD 3
n/a N/A VALVE PACKING TYPE (REPACK)
COMPOSITE n/a NON PACKING STRESS 4000 lbs N/A PACKING CONFIGURATION (REPACK) 37 I
n/a N/A TRANSFER RATIO (REPACK)
.85 n/a N/A PACKING COEFFICIENT OF FRICTION
.05 Dna (REPACK)
N/A LOWER BUSHING CAT #
0091219152 n/a N/A UPPER BUSHING CAT #
N/A n/a N/A PRIMARY PACKING CAT I 0091218662 n/a Paqe 2 of 4 Report Date: 14-MAR-2005 N/A LOWER BUSHING CAT I 0091219152 n/a nDva OTIBTurz
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EC.053.1012 Revtsion Paae 114 of 136 PP&L. -
NIMS Component Data Sheet CPX -
RCPECDA1 Category Name Value Unit N/A FLAT WASNER CAT U 0091219132 n/a N/A LIVE LQAD WASHER CAT #
0091217318 n/a N/A LANTERN RING CAT U N/A n/a N/A GRAPHITE WASHER CAT U N/A, NEEDS CUT n/a NON PACKING. SET HEIGHT (RETORQUE) 1.25 inch NOM PACKING STRESS (RETORQUE) 4000 psi N/A TRANSFER RATIO (RETORQUE)
.85 n/a N/A PACKING COEFFICIENT OF FRICTION
.05 n/a (RETORQUE)
Lube Locatios Lube Ccmponeat Catalog Name Catalog Nc.
Quantity U/M Latest ID Sheet Rev.
Rev.
As No.
AK Sheet AZ Rev, Description D107315 4
14 N
E-166 4
14 SCHEMATIC DIAGRAM STANDBY LIQUID CONTROL S E106253 1
27 N
M-14B 1
27 P&ID STANDBY LIQUID CONTROL IOM270-1 1
2 N
P14A-32 1
2 5500 SERIES MOTORIZED VALVES FOR STANDBY L FF110140 1001 8
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8 a1 1/2 INCH YARWAY WELBOND VALVE WITH LIMIT FF121010 3602 14 N
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14 ELEMENTARY DIAGRAM STANDBY LIQUID CONTROL Type Name Description IST ISS PROGRAM GROUP NSEPEG 13236 NSEFEG Primary Containment Isolation Valves NSEFEG UNIT 1 SLC SYS FEG REPORT NPRDS REPORTABLE GROUP SURV LOCAL LEAK RATE TESTING GROUP Pre & Post LLRT required IAW NDAP-QA-0412 SURV VALVE IS1 CATAGORIBS A and C apply
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Requirement Source Type Level 10.1 LIMITORQUE SMB AND SB NOV EQ PROGRAM EQAR-084 Design ACTUATOR INSTALLATION 10.1 T&B CRIMPED WIRE JOINT EQ PROGRAM EQAR-091 DeSign INSTALLATION 10.1 TERMINAL BLOCK INSTALLATION E0 PROGRAM EQAR-089 Design 20.2 T&B CRIMPED WIRE JOINT EQ PROGRAM EQAR-091 Design MAINTENANCE 10.2 TERMINAL BLOCK MAINTENANCE EQ PROGRAM EQAR-089 Design 10.2.1 LIMITORQUE SMB AND SB NOV EQ PROGRAM EQAR-084 Design ACTUATOR MAINTENANCE 10.3 TLB CRIMPED WIRE JOINT EQ PROGRAM EAR-091 Design CONFIGURATION 10.3 TERMINAL BLOCK CONFIGURATION EQ PROGRAM EQAR-089 Design 10.3.1 LIMITORQUE SMB, SB 460VAC NOV EQ PROGRAM EQAR-084 Design ACTUATOR CONFIGURATION 10.7 LIMITORQUE SMB AND SB NOV EQ PROGRAM EQAR-084 Design ACTUATOR PROCUREMENT 10.7 T&B CRIMPED WIRE JOINT EQ PROGRAM EQAR-091 Design PROCUREMENT 10.7 TERMINAL BLOCK PROCUREMENT EQ PROGRAM EQAR-089 Design LEAK RATE TESTING REQUIRED (LLRT/ILRT)
LEAK RATE TESTING LEAK RATE TESTING Design PROGRAM
_ag 3_f4Rpr ae 4MR20 I
Page 3 of 4 Report Date: 14-MAR-2005
PP&L v~xus Component Data Sheet EC4S3-1012 R"Slon 0 Pawe 1150o 138 CPX -
RCPECDA1 Designs SLC ISO VLV Pbysicali LAST REPACKED 3/28/04 CRRCHI* TORQUED TO 58 FT/LBS. ALL RINGS ARE.3125" TALL. GRAPHITE WASHER WILL NEED CUT.
A NEW STEM WAS INSTALLED U1-13RIO.
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SBLC LOC1: I-506 R752' Page 4 of 4 Report Date: 14-MAR-2005 Page 4 of 4 Report Date: 14 -MAR-2 005
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PROCESS SETPOINT TOL(-)
SETPOINT REVISION DATE DEVICE SETPOlNT TOLERANCE TOL(-)
DEVICE SETPOINT TOLERANCE TOL(+)
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27 PMID STANDBY LIQUID CONTROL 2162128 2
15 N
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15 rYOUT EMERGBNCi CORE COOLING BENCEBOARD 1 Type Na=e Description NSEPEG UNIT 1 SLC SYS FEG j
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EC-053-101?
Assessment of SBLC Rev. No.
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1-of 3-ATTACHMENT NO. 5 EXCEL Spreadsheet Results w
EC-053.1012 Revision 0 Pace 137 of 138 PP&L CALCULATION SHEET PROJECT Calc. No.
EC 053-1012 Assessment of SBLC Rev. No.
0 Designed By (G Kawal System for Suppression Checked By Pool pH Control Sh. No.
2-of 4
RESULTS OF COOLING FOR WATER TEMPERATURE AT 80F AND AMBIENT AT 60F (VARIABLE film coefficient)
(Ts-EXP(-
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4.5 5
5.5 6
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8.5 9
9.5 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 60 80 80 60.
80 80 80 80 80 80 80 80 60 s0 80 80 80 80 80 80 80 80 60 80 80 80 80 80 80 80 80 80 80 80 80 80 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 20 2.114743 2.114743 2.113798 2.112855 2.111913 2.110972 2.110033 2.109094 2.108157 2.107222 2.106287 2.105354 2.104422 2.103491 2.102561 2.101633 2.100706 2.09978 2.098856 2.097932 2.09701 2.096089 2.094242 2.092407 2.090578 2.088753 2.086933 2.085118 2.083307 2.081502 2.0797 2.077904 2.076112 2.074325 2.072542 0.003574 1
80 0.003574 0.998215 79.96429 0.003572 0.996434 79.92868 0.003571 0.994658 79.89316 0.003569 0.992887 79.85774 0.003568 0.991121 79.82242 0.003566 0.989359 79.78718 0.003564 0.987602 79.75204 0.003563 0.98585 79.717 0.003561 0.984102 79.68205 0.00356 0.982359 79.64719 0.003558 0.980621 79.61242 0.003556 0.978887 79.57774 0.003555 0.977158 79.54316 0.003553 0.975433 79.50867 0.003552 0.973713 79.47427 0.00355 0.971998 79.43996 0.003549 0.970287 79.40574 0.003547 0.968581 79.37161 0.003546 0.966879 79.33757 0.003544 0.965181 79.30362 0.003542 0.961783 79.23566 0.003539 0.958418 79.16836 0.003536 0.95507 79.10141 0.003533 0.95174 79.03481 0.00353 0.948428 78.96655 0.003527 0.945132 78.90264 0.003524 0.941854 78.83707
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EC-053-1012 Revtslon O Paoe 138of 138 PP&L CALCULATION SHEET PROJECT Caic. No.
EC-053-1012 Assessment of SBLC Rev. No.
0 Designed By G.Kawal System for Suppression Checked By Pool -pH Control Sh. No.
s--
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EXP(-
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60 80 20 18.75241 0.08588 0.917704 78.35409 2.5 60 80 20 18.35409 0.10735 0.898211 77.96422 3
60 80 20 17.96422 0.12882 0.879132 77.5264 3.5 60 80 20 17.58264 0.15029 0.860458 77.20917 4
60 80 20 17.20917 0.17176 0.842181 76.84363 4.5 60 80 20 16.84363 0.19323 0.824292 76.48585 5
60 80 20 16.48585 0.2147 0.806783 76.13567 5.5 60 80 20 16.13567 0.23617 0.789646 75.79293 6
60 80 20 15.79293 0.25764 0.772873 75.45747 6.5 60 80 20 15.45747 0.27911 0.756457 75.12913 7
60 80 20 15.12913 0.30058 0.740389 74.80777 7.5 60 80 20 14.80777 0.32205 0.724662 74.49324 8
60 80 20 14.49324 0.34352 0.709269 74.18539 8.5 60 80 20 14.18539 0.36499 0.694204 73.88407 9
60 80 20 13.88407 0.38646 0.679458 73.58916 9.5 60 80 20 13.58916 0.40793 0.665025 73.30051 10 60 80 20 13.30051 0.4294 0.6509 73.01799 11 60 80 20 13.01799 0.47234 0.623541 72.47083 12 60 80 20 12.47083 0.51528 0.597333 71.94667 13 60 80 20 11.94667 0.55822 0.572227 71.44453 14 60 80 20 11.44453 0.60116 0.548175 70.96351 15 60 80 20 10.96351 0.6441 0.525135 70.5027 16 60 80 20 10.5027 0.68704 0.503063 70.06126 17 60 80 20 10.06126 0.72998 0.481919 69.63837 18 60 80 20 9.638373 0.77292 OA61663 69.23326 19 60 80 20 9.233261 0.81586 0.442259 68.84518 20 60 80 20 8.845176 0.8588 0.42367 68A734 21 60 80 20 8.473404 0.90174 0.405863 68.11726 22 60 80 20 8.117257 0.94468 0.388804 67.77608 23 60 80 20 7.776079 0.98762 0.372462 67.44924 24 60 80 20 7.449242 1.03056 0.356807 67.13614 Ce x Re O
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