ML18101A750
| ML18101A750 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/20/1995 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18101A747 | List: |
| References | |
| GL-87-02, GL-87-2, SGS-SEIS.RPT, SGS-SEIS.RPT-R, SGS-SEIS.RPT-R00, NUDOCS 9506010514 | |
| Download: ML18101A750 (188) | |
Text
ATTACHMENT NO. 3 SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION 'ff~b~lt>tf12 IN RESPONSE TO:
NRC GENERIC LETTER 87-02/USI A-46 VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL EQUIPMENT IN OPERA TING REACTORS PREPARED FOR:
PUBLIC SERVICE ELECTRIC & GAS COMPANY P.O. BOX236 HANCOCKS BRIDGE, NJ 08038 REPORT NUMBER:
JOB NUMBER:
REVISION:
DATE:
PStiG SGS-SEIS,RPT 0014-00078 0
April 20, 1995
SEISMIC EVALUATiON REPORT FOR SALEM GENERATING STATION IN RESPONSE TO:
NRC GENERIC LETTER 87-02/USI A-46 VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL EQUIPMENT IN OPERA TING REACTORS
. PREPARED FOR:
PUBLIC SERVICE ELECTRIC & GAS COMPANY P.O. BOX 236 HANCOCKS BRIDGE, NJ 08038 REPORT NUMBER:
JOB NUMBER:
REVISION:
DATE:
SGS-SEIS.RPT 0014-00078 0
April 20, 1995
SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION SECTION TITLE PAGE
1.0 INTRODUCTION
.................................................................................................... 1 2.0 SCOPE/METHOD.................................................................................................. 1 3.0 PLANT DESCRIPTION AND DESIGN BASIS........................................................4 4.0 RESULTS............................................................................................................... 11
5.0 REFERENCES
....................................................................................................... 15 TABLES TITLE No. Paaes Table 4.1-1 Inaccessible Equipment 1
Tabie 4.4-1 Outlier Summary 1
FIGURES TITLE No. Paaes FIGURE 1 Plant Layout 3
FIGURE 2 Ground Response Spectra SSE 2
ATTACHMENT TITLE ATTACHMENT A* Excerpts from the PSE&G UFSAR ATTACHMENT B* Procedures and Criteria Used to Generate In-Structure Response Spectra for SGS Units 1 & 2 ATTJ\\CHMENT C Resumes and Training Records of Key VECTRAJStevenson &
Associates Personnel ATTJ\\CHMENT D Peer Review Report A TTJ\\CHMENT E* SEWS ATTACHMENT F SVDS ATTACHMENT G OSVS
("') Designates attachments not included in the NRC Submittal Page i Report SGS-SEIS.RPT, Rev. 0
SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION
1.0 INTRODUCTION
2.0 Page 1 The requirements for seismic design of nuclear power plants have evolved over the years from the application of commercial building codes earlier in the 1960's, to more sophisticated methods being used today. In view of the extent of these changes in design requirements, the NRC initiated Unresolved Safety Issue USI A-46, "Seismic Qualification of Equipment in Operating Plant," in December 1980. In early 1982, the Seismic Qualification Utility Group (SQUG) was formed to develop cost effective means of verifying the seismic adequacy of equipment in operating plants.
The results of the industry efforts in this area, have culminated in the issuance of Revision 2 of the Generic Implementation Procedure (GIP-2) and a number of supporting documents and reports.
Subsequently the USNRC has documented its review of the GIP in Supplemental Safety Evaluation Report No. 2 (SSER-2) and issued Supplement No. 1 to Generic Letter (GL) 87-02. Public Service Electric and Gas Company (PSE&G) provided their response to GL87-02 in a letter dated September 21, 1992 (Reference 5.1.9) outlining their proposed schedule and approach.
The objective of this report is to provide the necessary documentation of the A-46 effort at the Salem Nuclear Generating Station referred to hereafter as SGS.
It will consolidate the documentation required for the Seismic Evaluation Report.
SCOPE/METHOD The primary objective of the A-46 program at SGS is to verify the seismic adequacy of mechanical and electrical safe shutdown equipment. This program will provide a successful resolution of USI A-46, in addition, PSE&G will utilize the key elements and results to streamline the seismic qualification process for the life of the plant. As discussed in Reference 5.1.9,, SGS intends to comply with the SQUG commitments set forth in GIP-2 [5.2.2], including the clarifications, interpretations, and exceptions identified in SSER-2 [5.1.2].
The essential features of the SQUG approach, for the resolution of A-46, is the use of earthquake experience data, and generic equipment qualifications and fragility test data. To use these sources of data, SQUG and EPRI have collected and organized the associated information and have developed guidelines and criteria for its use. The GIP-2 summarizes the technical approach and provides detailed implementation and documentation requirements for the application of Report SGS-SEIS.RPT, Rev. 0
Page 2 SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION experience data to verify the seismic adequacy of the safe shutdown equipment.
Implementation of the GIP-2 requirements at SGS was performed by VECTRA and Stevenson & Associates in accordance with the Project instructions listed in Reference 5.2.6. The peer review was conducted by Messrs Harry Johnson and Paul Smith and concluded that the methods used for the Salem 1 & 2 USI A-46 implementation are appropriate, the methods have been correctly implemented and the results and recommended actions appear to be reasonable and consistent with what was anticipated. (See Attachment D).
The results and observations of the peer reviewers were consistent with the findings of the SRT.
The GIP approach for verifying the seismic adequacy of mechanical and electrical equipment is consistent with the intent of Generic Letter 87-02, "Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety Issue (USI) A-46", including NUREG-1030 (Reference 5.1.3) and NUREG-1211 (Reference 5.1.4 ). The approach is also consistent with the EPRI Seismic Margins Assessment Program (SMA) described in Reference 5.2.1. The four major steps used for the majority of the equipment to be evaluated are listed below:
Selection of Seismic Evaluation Personnel Identification of Safe Shutdown Equipment Screening Verification and Walkdown Outlier Identification and Resolution Several types of individuals, their qualifications, and their responsibilities for implementing this procedure are described in Section 2, part II of the GIP.
These individuals include: (1) Systems Engineers who identify the methods and the equipment needed for bringing the plant to a safe shutdown condition, (2)
Plant Operations Personnel who have a comprehensive understanding of the plant layout and the function and operation of the equipment and systems in the plant and who compare the plant operating procedures to the safe shutdown equipment list for compatibility, (3) Seismic Capability engineers who perform the Screening Verification and Vvalkdown of the safe shutdown equipment, and (4) Relay Evaluation Personnei who perform the relay functionality review.
The Seismic Capability Engineers must exercise sound engineering judgment during the Screening Verification and Vvalkdown. Therefore the selection and training of qualified Seismic Capability Engineers for participation on the Seismic Review Teams (SRTs) is an important element of the fa..-46 program.
Report SGS-SEJS.RPT, Rev~ 0
Page3 SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION The resumes and training records, of key individuals from the VECTRA and Stevenson & Associates staff that participated in the completion of the A-46 effort at SGS, are included as Attachment C.
The Safe Shutdown Equipment List (SSEL) Report, and the Relay Evaluation Report are documented in VECTRA Reports, References 5.3.3 & 5.3.4. This report will provide, by reference or as attachments, all the documentation associated with the Seismic Evaluation Report.
Report SGS-SEIS.RPT, Rev. 0
SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION 3.0 PLANT DESCRIPTION AND DESIGN BASIS Page4 3.1 General Plant Description 3.2 The SGS is comprised of two nuclear power units and uses pressurized water reactors. The plant is licensed to produce 3411 MW of thermal power per unit, and 2211 MW of total gross electrical power for both units.
This plant provides electrical power to all sponsoring utilities via the Pennsylvania/New Jersey/Maryland 500 kV interconnected system.
SGS was designed and constructed by PSE&G. Westinghouse Electric Corporation designed and furnished the nuclear steam supply system (NSSS) equipment and systems, including the fuel assemblies. PSE&G contracted United Engineers and Constructors, Inc. of Philadelphia, Pennsylvania, to supervise field erection.
PSE&G also engaged the consultants listed in UFSAR Section 1.4 to provide technical assistance in various areas.
Each unit incorporates a 4-loop, closed cycle, pressurized water type NSSS; a turbine generator and electrical systems; engineered safety features; radioactive and waste systems; fuel handling systems; structures and other on-site facilities; instrumentation and control systems; and the necessary auxiliaries required for a complete and operable nuclear power station. The only systems shared by the two units are the compressed air, demineralized water and solid radwaste handling systems. the site plan (Figures 1.2-1 of the UFSAR) shows the general arrangement of the units.
The Hope Creek Generating Station is located north of Salem Units 1 and 2 on the same site.
Site Location The Salem plant site is located on the southern part of Artificial Island on the east bank of the Delaware River in Lower Alloways Creek township, Salem County, New Jersey. The site is located on the southern tip of Report SGS-SEIS.RPT, Rev. 0
3.3 Page 5 SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION what was once a natural bar in the Delaware Estuary, adjacent to the western shore of New Jersey. In the past, the bar and the area between the bar and mainland has been used as a disposal area for material dredged from the Delaware Estuary or River.
No additional dredged material has been placed for at least the past 25 years.
The site consists of 700 acres. The minimum distance from the reactor containment to the site boundary is 4200 feet, and the distance to the nearest residence is over 3.4 miles. Except for three small towns and villages (Bay View Beach and Port Penn, DE and a portion of Hancocks' Bridge, NJ) the area within a 5.0 mile radius is predominantly rural, consisting of marshes and abandoned meadowland and some farmland.
Site Geology and Seismology The Salem plant site is located on the United States Geological Survey map designated "Wilmington, Delaware, 1966". The site is underlain by some 1800 feet of Cretaceous, Paleocene, Miocene and Quarternary-aged sediments. Crystalline basement rock outcrops near* the Fall Zone some 18 miles northwest of the site. A graphical representation of the site subsurface conditions is presented in UFSAR Figures 2.5-5 and 2.5-9, Columnar Sections. Conditions encountered at the site are completely consistent with the known regional picture.
No known faults exist within the basement rock or sedimentary deposits in the vicinity of the site. The closest known faulting to the site is about 25 miles away. At this distance, faults are found in the rocks of the piedmont west of the Fall Zone; however, a minor fault has been identified east of the Fall Zone, near Gibbstown, New Jersey, about 25 miles northeast of the site. This fault is in the crystalline basement, covered by about 300 feet of Coastal Plain sediments, and apparently parallels the general northeast-southeast trend of the Piedmont.
No major earthquake activity has affected the site area and no record of deleterious behavior of onsite soils (even the poorest surficial materials) is known. The site is situated in a region which has experienced only minor earthquake activity. Only one shock within 50 miles of the site has been large enough to cause even minor structural damage. Since the region has been populated for over 300 years, it is probable that any earthquake Report SGS-SEIS.RPT, Rev. 0
3.4 Page 6 SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION of moderate intensity, say VI or greater on the Modified Mercalli Scale, would have been reported during this period.
It is very likely that all earthquakes within the last 200 years, with intensities greater than V, in the region surrounding the site, have been reported.
The two largest earthquakes nearest the site were the 1871 Vv'ilmington, Delaware and the 1927 Asbury Park, New Jersey shocks.
Both had maximum epicentral intensities of VII. Intensity VII shocks are the largest that have occurred throughout the surrounding regions, and both from a deterministic and probabilistic standpoint, appear to be the largest credible earthquake.
Therefore, for purposes of seismic design, an Intensity VI! shock has been assumed to occur near the site.
For a safe shutdown of the reactor, the facility has been designed using a seismic factor of 20 percent of gravity at foundation level. This level of horizontal ground acceleration is significantly greater than that which would be expected upon the foundation soils at the site if the safe shutdown earthquake (SSE) were to occur. The corresponding vertical ground acceleration is taken as 13.3 percent of gravity.
For an operating basis earthquake (OBE), SGS has b~en designed to respond elastically with no loss of function to horizontal earthquake ground accelerations of 10 percent of gravity, and vertical ground accelerations of 6.7 percent of gravity. These values are conservatively greater than the level of ground motion which would be expected at the site during an earthquake similar to any historical event.
This ground acceleration is greater than what might be reasonably expected due to an earthquake similar to the 1871 Wilmington shock, Intensity VII, at an epicentral distance of about 15 to 20 miles.
Structures The major Category I structures of SGS are the Containment Buildings, Fuel Handling Buildings, Auxiliary Building and Service Water Screen Well. Figure 1 provides a representation of the general site layout.
Each Reactor Containment consists of a containment structure designed for an internal pressure of 47 psi gage. The containment is designed to limit the consequences of any release of radioactive material resulting Report SGS-SEIS.RPT, Rev. 0
Page 7 SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION from a postulated loss of coolant accident. The containment structure is a reinforced concrete vertical right circular cylinder with a hemispherical dome and a flat base. The nominal inside diameter is 140 feet and the nominal straight height is 142 feet.
The construction is reinforced concrete with an interior steel liner which acts as a leakage barrier. The liner is 1/4 in thick at the bottom, 1/2 in thick on the cylinder walls below ground level, 3/8 in thick on the cylinder walls above ground level and 1/2 in thick on the dome. Access to the containment structure is through a double door personnel hatch.
3.5 Plant Seismic Design Basis Attachment A contains a reproduction of appropriate sections from the SGS UFSAR which provide a comprehensive description of the plant seismic design basis. A brief summary description of the SGS Seismic Design Basis is presented here.
SGS was designed in 1967.
As discussed eariier, PSE&G was responsible for site development and design of buildings and secondary systems, and Westinghouse Electric Corporation was responsible for design of NSSS equipment and systems including fuel assemblies. SGS was designed in accordance with the Atomic Industrial Forum General Design Criteria, as published in a letter to the Atomic Energy Commission (AEC) from E. A. Wiggin, Atomic Industrial Forum, dated October 2, 1967.
In addition, SGS was designed to comply with PSE&G's understanding of the intent of the AEC's proposed General Design Criteria, as published for comment by the AEC in July, 1967.
The application of the AEC's proposed General Design Criteria to SGS is discussed in UFSAR Section 3.1.2. A comparison of the SGS design with 1 OCFR 50, Appendix A (General Design Criteria for Nuclear Power Plants dated July 7, 1971) is provided in UFSAR Section 3.1.3.
PSE&G's general criteria for the SGS are discussed in UFSAR Section 3.1.3.
3.6 Original Design Basis Seismic Input Report SGS-SE!S.RPT, Rev. 0
3.7 Pages SEISMIC EVALUATION REPORT FOR SALEM GENERA TING STATION A dynamic analysis of structures, systems and components was conducted for SGS.
The response spectra used in the design are presented on Fig. 2.5-12 and 2.5-13 of the UFSAR.
These spectra conform to the average spectra developed by Dr. G.W. Housner for the frequency range higher than about 0.33 cycles per second. The spectra for frequencies lower than about 0.33 cycles per second were prepared utilizing data suggested by Dr. N.M. Newmark.
The spectra have been normalized to a horizontal ground acceleration of 20% of gravity for the SSE and 10% of gravity for the OBE.
Vertical ground accelerations were taken as equal to 2/3 horizontal acceleration values and are considered to be acting simultaneously with the horizontal ground motion.
Original Design and Analysis of Structures The Seismic Category I structures at SGS consists of a Reactor Containment Building, Fuel Handling Building, for each unit, and a common Auxiliary Building and Service Water Intake Structure.
Class I structures and equipment supports are designed to resist the dynamic forces resulting from the earthquake conditions postulated for the site. The mathematical modal of an equivalent system is used to simulate the response.
The system consists of lumped masses at floor levels supported by weightless springs.
Floor rotations are neglected.
Both shear stiffness and flexure stiffness are included in the spring constants.
The lumped mass system is considered resting on the rigid base mat.
Average response spectra are used in the manual analysis while time history inputs are used in the computer analysis.
In the response spectra analysis, the total response for the structures and components is the square root of the sum of the square of all maximum values from all modes, provided there are three modes or more. In cases where there are only two modes contributing significantly, or when there are three contributing modes with only one dominant, the absolute sum of the maximum value is used for the design.
Report SGS-SEIS.RPT, Rev. 0
Page 9 SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION In the time history analysis, the corresponding response in each vibrating mode is calculated as a function of time.
The total response for any desired instant are evaluated by summing the response of all significant modes.
For soil structure interaction in the computer analysis, a series of studies were conducted in order to establish the free field soil boundaries. With the boundaries established, the finite element model, including the surrounding soil mass, was set up more accurately.
Response spectra at different floors in the structures are obtained as follows: the building is subjected to the input ground acceleration time history and the corresponding output acceleration time histories at the floors of interest are determined. The acceleration time histories are then used to derive single-degree-of-freedom system response spectra, which are the floor response spectra for each floor of interest.
A detailed description of spectra generation for SGS was submitted to the NRC as requested by Generic Letter 87-02, Supplement No. 1 and is included here as Attachment B.
3.8 Seismic Design of Systems and Components Detailed descriptions of the seismic design of safety-related mechanical components, as well as Category I instrumentation and electrical equipment are provided in Section 3.9 and 3.10 of the SGS UFSAR and are included as part of Attachment A.
In general, seismic qualification was performed for safety-related components using a combination of analysis and testing.
Seismic Category I instrumentation and electrical equipment, and their supports as listed in Table 3.10-1 of the UFSAR, were qualified in accordance with the methods described in IEEE Standard 344-1971.
Report SGS-SE!S.RPT, Rev. 0
Page 10 SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION 3.9 A-46 Seismic Input The seismic input used in the A-46 effort is the same input used in the seismic analysis and design for SGS as described in Reference 5.1.9 and section 3.7. Horizontal in-structure SSE spectra for 5% and 3% damping are used as the seismic input.
The site SSE is a Housner Spectrum anchored to 20% g as shown in Figure 2.
Effective grade for the Auxiliary building is at elevation 100'; for the containment internal structure effective grade is at elevation 56'.
For equipment located in pressurizer area at elevations above 130', the SEWS show elevation 130' since no spectra is available for higher elevations. This was judged acceptable by the SRT since the peak of the spectra for elevation 130' is in the frequency range of 0.8 to 1.2 Hz; the equipment of interest at the higher elevations have frequencies well above 2Hz and will still be acceptable even with higher response..
Report SGS-SEIS.RPT, Rev. 0
SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION 4.0 RESULTS In general, the plant equipment was found to be well anchored and seismically rugged. The general housekeeping practices were found to be satisfactory, reflecting a good awareness of seismic interaction issues.
The seismic screening of components is documented on Screening Evaluation Work Sheets (SEWS) in accordance with the requirements of the GIP, and provided as Attachment E.
The SEWS are sorted by equipment class. The results are further condensed and summarized on Screening Verification Data Sheets (SVDS), also sorted by class and presented as Attachment F. The plant Cable Tray and Conduit Raceway reviews were conducted on an area basis and samples were selected for limited analytical reviews. The approach used for this walkdown is documented in Reference 5.3.5.
The results demonstrated the seismic adequacy of the raceway systems. Large flat bottom storage tanks were evaluated using the detailed evaluation methods of EPRI NP-6041 [5.2.1] as documented in Reference 5.3.8.
Other tanks and heat exchangers were evaluated using GIP-2 methods. Summaries of the Tanks and Heat Exchangers reviews are included with the class 21 SEWS (Att. F).
Outliers were identified as a result of the equipment screening effort. All outliers are documented on Outlier Seismic Verification Sheets (OSVS) and have been included as Attachment G. All outliers were reviewed to determine compliance with design documentation, and none were found to present a significant risk to public health and safety.
A general summary of the walkdown findings and the results is provided in the following subsections:
4.1 Equipment Screening and Walkdowns Page 11 Based on the result of the walkdowns and reviews performed by the SRT's the plant equipment was found to have good original seismic design; electrical cabinets were generally welded to embedded steel members, mechanical equipment were typically anchored with cast in place bolts.
Equipment data such as vendor drawings was generally available and retrieved using plant databases; original qualification files Report SGS-SEIS.RPT, Rev. 0
Page 12 SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION were also well maintained and sorted.
The general housekeeping conditions in the plant were found to be satisfactory; all identified interactions were related to proximity concerns. All SSEL equipment with the exception of those listed in section 4.1.1 were walked down by at least two seismic capability engineers. The GIPPER software was used as the primary tool to record the results and generate the SEWS. Included in the SEWS are the capacity and demand spectra plots, all applicable caveats, field notes, photographs, and anchorage evaluations. The majority of the anchorage calculations were performed using the ANCHOR program and are attached to the SEWS. As stated earlier the SVDS are included 1n attachment F and provide an overall summary of the screening results.
4.1.1 Inaccessible Items A total of six components were located in High Rad areas and reviewed based on Health Physics photographs and vendor drawings.
Other inaccessible equipment included electrical cabinets which the SRT could not gain access to, due to the plant outage rescheduling as identified in Reference 5.1.1 O; these are scheduled for walkdown during 1R12. Table 4.1-1 provides a listing of all individual components.
4.1.2 Cases where the Intent of the Caveats are Met All Motor Control Centers at SGS and some of the floor mounted distribution panels are 12" deep. These are narrower than allowed by the equipment class caveat, but were judged to meet the intent of the caveat given original qualification testing and reviews performed by the SRT.
The majority of instrument stands have expansion anchors which are covered by concrete; these are small Hoffman enclosures supported by a short frame made of steel angles.
The inaccessible anchorage was judged to meet the intent of the installation caveats based on drawing reviews, large margins and the result of tightness checks performed on similar accessible anchorage.
Few Air Operated Valves (AOV) on the SSEL are mounted on 3/4" piping, these were judged to meet the intent of the caveat based on the well supported piping configuration in the vicinity of the valve body.
Report SGS-SEIS.RPT, Rev. 0
SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION 4.2 Tanks and Heat Exchangers Evaluations 4.3 Page 13 All tanks were evaluated using the GIP-2 screening criteria. A few of the heat exchangers had configurations that did not fit within the parameters of the GIP-2 but were evaluated using the same general methodology and acceptance criteria. The large flat bottom storage tanks on the SSEL did not meet the screening guidelines of the GIP and were identified as outliers.
Detailed evaluations were performed in accordance with Appendix H of EPRI NP-6041, and the High Confidence Low Probability of Failure HCLPF values for these tanks were calculated to be in excess of 0.28 g PGA (i.e. 40% margin over plant SSE). Also the air accumulator tanks on top of the pressurizer enclosure are being tracked as outliers since it was not possible to verify the preload value that exists in the U bolts which are used to secure these tanks to the supporting frame.
Raceways Evaluations The Raceway reviews were performed independent of the equipment effort. Reference 5.3.5 established the criteria for the walkdown effort.
The walkdowns were performed on an area basis and documented on a total of 43 area summary sheets; 23 configurations were selected for limited analytical reviews. The results of the raceway evaluations have been captured in Table 1 of Reference 5.3.6 and provide guidance for configuration control and any reviews of field changes.
Four outlier conditions were noted in each unit, corresponding OSVS sheets were generated. The majority of these conditions were related to hardware deficiencies which have been rectified using work requests and supplemental evaluations. One condition identified a potential interaction due to the proximity of a cable tray support and an electrical cabinet; the subject cabinet is not on the SSEL and therefore this condition is also resolved.
As described above all RacevJay outliers have been resolved and require no further action.
Report SGS-SEIS.RPT, Rev. 0
4.4 SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION Description of Outliers A number of equipment outliers were identified as described earlier. The majority of the outliers are related to proximity effects or are maintenance related. A detailed description of each outlier condition is provided in the attached OSVS and summarized in Table 4..4-1. The tank outliers were described in section 4.2 and are also captured in table 4.4-1. All outliers were determined to have no significant impact on the health and safety of the public.
Page 14 Report SGS-SElS.RPT, Rev. 0
SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION
5.0 REFERENCES
5.1 Codes, Standards and Regulatory Documents 5.1.1 USNRC Generic letter 87-02, Supplement 1, issued May 22, 1992.
5.1.2 Supplemental Safety Evaluation Report No. 2 (SSER No.2) on Revision 2 of the Generic Implementation Procedure (GIP-2), May 22, 1992.
5.1.3 NUREG-1030, "Seismic Qualification of Equipment in Operating Nuclear Power Plants, Unresolved Safety Issue A-46," U.S.
Nuclear Regulatory Commission, Washington, D.C., February, 1987.
5.1.4 NUREG-1211, "Regulatory Analysis for Resolution of Unresolved Safety Issue A-46, Seismic Qualification of Equipment in Operating Plants," U.S. Nuclear Regulatory Commission, Washington, D.C.,
February 1987.
5.1.5 IEEE 344-1971, "IEEE Recommended Practice for Seismic Qualification of Class 1 E Equipment for Nuclear Power Generating Stations," Institute of Electrical and Electronics Engineers. 1971 5.1.6 IEEE 344-1975, "IEEE Recommended Practice for Seismic Qualification of Class 1 E Equipment for Nuclear Power Generating Stations," Institute of Electrical and Electronics Engineers. 1975 5.1.7 NRC Regulatory Guide 1.100, Revision 1, Seismic Qualification of Electrical and Mechanical Equipment for Nuclear Power Plants,"
U.S. Nuclear Regulator Commission, August 1987.
5.1.8 J.C. Stone (USNRC) letter to PSE&G Docket 50-272 & 311, dated November 13, 1992.
5.1.9 S. LaBruna, PSE&G letters to the US NRC, NLR-N92134 dated September 21, 1992 and NLR-N93021 dated February 11, 1993.
5.1.10 PSE&G letters to the US NRC, NLR-N95045 dated February 1995.
Page 15 Report SGS-SEIS.RPT, Rev. 0
SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION 5.2 Technical Criteria and Design Basis Documents 5.2.1 EPRI NP-6041-SL R1, "A Methodology for Assessment of Nuclear Power Plant Seismic Margin", August 1991.
5.2.2 "Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment," Revision 2, as corrected on February 14, 1992.
5.2.3 PSE&G, Salem Generating Station Updated Final Safety Analysis Report.
5.2.4 Not Used 5.2.5 Not Used 5.2.6 VECTRA (formerly ABB lmpell) Project Instructions 0014-078-P001, P002 & P003, latest revision.
5.2.7 VECTRA (formerly ABB lmpell) Project Quality Plan 0014-00078, latest revision.
5.2.8 Not Used 5.3 Evaluation Reports and Calculations Page 16 5.3.1 Not Used 5.3.2 Not Used 5.3.3 VECTRA Report 0014-00078-R001, "Safe Shutdown Equipment List (SSEL) Report for Salem Generating Station Units 1 and 2",
Latest Revision.
5.3.4 VECTRA Report 0014-00078-R002, "Relay Evaluation report for Salem generating Station Units 1 and 2", Latest Revision.
Report SGS-SEIS.RPT, Rev. 0
Page 17 SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION 5.3.5 PSE&G Nuclear Department, Civil Engineering Directive No. 18, "Salem SQUG Walkdown and Analytical Review Criteria for Electrical Raceways".
5.3.6 PSE&G Nuclear Department, Technical Standard SC.DE-TS.ZZ-4706(0)., "Salem Design Analysis for New and Modified Electrical Raceways Supports Using SQUG GIP Methodology".
5.3.7 PSE&G Letter PMS-94-0273 from Tim Taylor to Jim Fiaherty dated July 27, 1994.
5.3.8 VECTRA Calculation 0014-00078-A46-01, "Equipment Anchorage Evaluation".
Report SGS-SEiS.RPT, Rev. 0
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7 1CV2 LETDOWN LINE !SOL VALVE Same as 2CVE23.
7 1CV277 LTDWN LINE !SOL VALVE Same as 2CVE23.
7 2CV2 LETDOWN LINE !SOL VLV
~ame as 2CVE23.
7 2CV277 L TOWN LINE !SOL V Same as 2CVE23.
21 1CVE23 EXCESS LETDOWN HX Same as 2CVE23.
2 1SWGR1C9X NO 1 C 460V VITAL BUS EXTENSION Walkdown to be performed during 1R12 outage.
14 12MAC 115VAC DISTRIBUTION CABINET Walkdown to be performed during 1R12 outage.
16 1DIS1A5YA NO 1A VITAL INSTRUMENT BUS (115V)
Walkdown to be performed during 1R12 outage.
16 1DIS1B11YA NO 1 D VITAL INSTRUMENT BUS (115V)
Walkdown to be performed during 1R12 outage.
16 1DIS1B5YA NO 1B VITAL INSTRUMENT BUS (115V)
Walkdown to be performed during 1R12 outage.
16 1DIS1C5YA NO 1C VITAL INSTRUMENT BUS (115V)
Walkdown to be performed during 1R12 outage.
14 22MAC 115VAC DISTRIBUTION CABINET Walkdown to be scheduled during Unit 2 outage.
7 23SW93 CH CNDSR SW RECIRC VLV Walkdown to be scheduled during Unit 2 outage.
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TABLE 4.4-1 DESCRIPTION OF OUTLIERS SALEM UNIT 1 A
Components in close proximity to structural elements Initiate modification/maintenance work requests lo 11107, 1'1137, 1 SWE3 which could result in seismic induced impact.
eliminate potential interactions by providing adequate clearances or restraining of the component.
B-- Componer:;!s.in-close proximity to overhead distributed systems which could result in seismic induced impact.
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E Components with missing hardware.
Air accumulator tanks restrained using double U-boll straps. No torque values were specified on design drawings Adjacent cabinets are not bolted together.
F Large flat bottom storage tanks did not meet the screening guidelines of the GIP.
G Component or attached piping is rusty.
H Air intake line supported with rod hangers.
Initiate modification lo eliminate potential interactions RC11, RC12, RC13, RC14, RC15, RC16, RC18 by providing adequate clearances between the affected component and the overhead distributed systems.
Initiate maintenance request to restore affected components to their original configuration.
Initiate maintenance request to ensure required preload on U-bolts.
Initiate necessary changes to provide bolting.
11105, 11133 1CA-EC-0398A, B; 1CA-EC-0148A, B 11126, 103-1, 131-1, 32-1, 58-1, 59-1, SEC-1A, 1B, 1C; 1PNL11828, 1PNL11829, 1PNL11830, 1PNL11831, 1PNL11832, 1PNL11833, 1ADE, 1CDE, 11NV1A5YB, 11NV1B11YB, 11NV185YB, 11NV1C5YB, 11NV1C6YC, 205-1; 206-1, 1SWGR1AD, 1SWGR1BD, 1SWGR1CD Performed detailed evaluation in accordance with EPRI 1AFE1, 1 SJE5 6041. HCLPF value was determined lo be > 0.28g.
Inspect the component to' aetermine if the rust has 1WGE17 affected the component integrity.
Item was identified prior to the start of the A-46 effort 1 DAE23, 1 DAE38, 1 DAE4 and mods have been initiated.
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Components in close proximity to structural elements Initiate modification/maintenance work requests to 12107, 12137 which could result in seismic induced impact.
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B Components in close proximity to overhead distributed systems whic\\1 could result in seismic induced impact.
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Initiate modification to eliminate potential interactions RC24, 12111 by providing adequate clearances between the affected component and the overhead distributed systems.
Initiate maintenance request to restore affected 12109, 12132, 12133 components to their original configuration.
Initiate maintenance request to ensure required preload on U-bolts.
Initiate necessary changes to provide bolting.
2CA-SC-1245A, 8, C, D 2ADE, 2CDE, 103-2, 131-2, 132-2, 32-2, 37-2, 38-2, 58-2, 59-2, SEC-2A, 28, 2C, 2PNL 11828, 2PNL 11829, 2PNL 11830, 2PNL 11831, 2PNL 11832, 2PNL 11833, 205-2; 206-2; RC21, RC22, RC23 2DIS2A5YA, 2DIS2811YA, 2DIS285YA, 2DIS2C5YA, 21NV2A5YB, 21NV2811YB, 21NV2B5YB, 21NV2C5Y8, 21NV2C6YC Performed detailed evaluation in accordance with EPRI 2AFE1, 2SJE5 6041. HCLPF value was. determined to be> 0.28g.
Item was identified prior to the start of the A-46 effort 2DAE23, 2DAE4, 2DAE38 and mods have been initiated.
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SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION ATTACHMENT C RESUMES AND TRAINING RECORDS OF KEY PERSONNEL PSE&G VECTRA TECHNOLOGIES, INC.
STEVENSON & ASSOCIATES AND STONE & WEBSTER ENGINEERING CORP.
James Flaherty (8 Pages)
Charbel Abou-Jaoude (5 Pages)
Aziz Saber (5 Pages)
Steve Reichle (7 Pages)
John G. Connolly (3 Pages)
Steve Anagnostis (3 Pages)
Walter Djordjevic (4 Pages)
Alan A. Johnson (2 Pages)
Robert H. Koch (2 Pages)
Chiman N. Antala (1 Page)
James F. Glova (5 Pages)
Sol M. Feldman (3 Pages)
Hsin-Hsiu Kuo (2 Pages)
JAMES A. FLAHERTY PROFESSIONAL EXPERIENCE Mr. Flaherty is a Technical Services Manager of VECTRA's Eastern Region Engineering Mechanics and Systems Division. He has over 25 years of nuclear and fossil power plant design experience. He is responsible for Project Management and Administrative Control for structural and mechanical design consulting services. He has particular expertise in the analysis and design of plant structures and mechanical components including containment vessels, tanks, piping systems and their supports to ASME BPVC Section Ill,Section VIII and Section XI requirements.
Mr. Flaherty is the Project Manager for the Individual Plant Examination for External Events (IPEEE), for Philadelphia Electric Company for Peach Bottom Atomic Power Station and the Limerick Generating Station. He is also the Project Manager for the Public Service Electric and Gas Company's USI A-46 SQUG Program for Saiem Units 1 and 2.
He has been trained by EPRl/SQUG and is certified as a Seismic Capability Engineer.
Mr. Flaherty is the Project Manager for the Boston Edison Company MOV Modifications Plant Design Change Package project. He is also the Project Manager for the Reactor Pressure Vessel Head Torquing evaluation and procedure evaluation at Pilgrim Nuclear Power Station.
Mr. Flaherty was the Lead Structural Engineer for the PECo Structural Topical Design Baseline Document tor Peach Bottom and Limerick Generating Stations.
Mr. Flaherty was the Project Manager for the Pressurizer PORV/SV thermal hydraulic piping reanalysis project for PSE&G Salem Unit 1 and 2. He was responsible for the analyses of Safety and Relief Valve actuation using RELAP4 and the subsequent pipe stress evaluations using VECTRA's SUPERPIPE Program. The objective of this analysis was to demonstrate Safety and Relief Valve Operability under all postulated loading conditions. He was the overall Project manager tor the DCP preparation and modifications for draining the PORV and SV loop seals at Salem Units 1 and 2.
He recently completed a project for PECo that developed the acceptance criteria and examination requirnments program for a BWR Mark I torus subjected to local and global corrosion.
Previously, Mr. Flaherty was Vice President of Engineering for Altran Corporation. He was responsible tor all engineering and design services for outside clients and had overall management responsibility for all of the parent company's engineering activities.
JAMES A. FLAHERTY Page 2 He was responsible for the permitting and design associated with the construction of four 50 ton per day Cogeneration Medical Waste Incinerator Facilities and the conceptual design and technical support activities for a 240 ton per day municipal solid waste cogeneration facility. His responsibilities included technical development, site investigation and environmental permitting. He was responsible for selection of the air quality control systems and compliance with state and federal regulations.
His duties included consulting engineering services for various fossil and nuclear power plant projects. These included failure analysis and recommended repair options for a 4 million gallon oil storage tank facility, snubber reduction program at a nuclear utility and various operability and functionality evaluations for several nuclear power plant systems.
Before joining Altran, Mr. Flaherty was associated with Teledyne Engineering Services from 1968 to 1987. In 1984 he became Vice President with responsibility for. all activities performed by Failure Analysis and Prevention Group, Experimental Mechanics Testing and Instrumentation Group and Brewer Engineering Laboratories.
Mr. Flaherty was also a Consulting Engineer in the area of pressure vessels and structural components with particular emphasis on stress analysis and the applicability of the ASME Boiler and Pressure Vessel Codes, AISC and Regulatory Requirements.
The analysis included the evaluation of heat exchangers, tube-to-tube sheet joints, steam generators, containment shells, ASME Class 1, MC, 2 and 3 component evaluation and high pressure closure joints. Various finite element Codes such as ANSYS, STARDYNE, STRUDL, and SAAS have been utilized for heat flow, structural analysis and structural dynamics.
From 1980 to i 984 he was Manager, Engineering Design and Testing. He had direct responsibility for repairs and replacements of nuclear power plant systems and their components including design, analysis, fabrication and examination requirements. As a Project Manager, Mr. Flaherty had the overall responsibility for the modifications, design, fabrication and installation of various components under the Mark I Torus Program for Boiling Water Reactors at five nuclear power plants.
Mr. Flaherty was the Project Manager for Independent Design Verification Programs at three nuclear power plants and a member of the review group for Diablo Canyon Program to determine the Adequacy of Construction.
JAMES A. FLAHERTY Page 3 Mr. Flaherty has been responsible as the Project Manager and Lecturer of more than twenty seminars for the electric power generating industry in the area of plant modifications and the applications and use of various codes and standards. Seminars were held in the United States, Germany and Sweden. Subjects presented included:
vessel design and analysis, component supports design and evaluation, methods of analysis, Design Specification development and Repair/Replacement/Modifications of components to the rules of ASME Section XI.
Mr. Flaherty was also a member of the Welding Research Council, Pressure Vessel Research Committee (PVRC) from 1971 to 1987. As a member of PVRC, he served on the Subcommittee on Elevated Temperature Design and was a member of the Subcommittee of Shells and Ligaments.
Mr. Flaherty was also the Project Manager for various analytical and experimental projects. He was responsible for the development of a data acquisition and control system for the investigation of ship slamming in high seas. He was the Program Coordinator for a Fifteen Utility Owners Group for the generic response t9 the USN RC for IE Bulletin 79-02. The program included the development of a finite element computer code for determining the flexibility of base plates and experimental testing of concrete expansion anchor bolt.
Mr. Flaherty served as a member of the NRC Review Team for determining the adequacy of the Comanche Peak Review Team Program Plan for Design.
Earlier in his career, Mr. Flaherty worked for both Avco Corporation of Wilmington, Massachusetts and Linethal-Becker-Eisenberg, Inc. of Boston, Massachusetts. While at Avco Corporation he was an Associate Engineer, Structures, Analytical Mechanics Section, Missile Systems Division. He formulated the necessary computer input for structural re-entry vehicle problems involving thermal, static and dynamic loadings; checking output for critical conditions. He also assisted in preparation of stress reports.
At Linethal-Becker-Eisenberg, Inc., Mr. Flaherty's position was that of Structural Engineer. He participated in the design of two shopping centers and an elementary school where he was responsible for overseeing the work of draftsmen, checking and approving shop drawings. He was also involved in design of structural steel and foundation members.
JAMES A. FLAHERTY Mr. Flaherty was commissioned a 1st Lieutenant, United States Army Corps of Engineers. He served as a Project Officer in the Directorate for Data Systems, Lexington - Blue Grass Army Depot, Lexington, Kentucky.
EDUCATION M.S., Civil Engineering Tufts University, Boston, MA B.S., Civil Engineering Northeastern University, Boston, MA Technology Managers Program Babson College, Boston, MA PUBLICATIONS Page 4 "A Method for Digitizing, Preparing and Using Library Tapes of Ship Stress and Environment Data," with Aldie E. Johnson, Jr. and Isaac J. Walters, Ship Structures Committee Report SSC-236, 1973.
"Computer Programs for the Digitizing and Using of Library Tapes of Ship Stress and Environment," with Aldie E. Johnson, Jr. and Isaac J. Walters, Ship Structure Committee Report SSC-237, 1973.
"An Assessment of the Effect of Plate Flexibility on the Design of Moment-Resistant Baseplates," with Louis J. Di Luna, ASME, for the presentation at the Pressure Vessel and Piping Conference, San Francisco, California, June 1979.
"The Field Installation of Concrete Anchorage Systems," with Louis J. DiLuna.
Presented at the ASCE Committee on Construction of Nuclear Facilities Conference, Pennsylvania State University, September 1981.
"Mechanical and Hydraulic Snubbers for Nuclear Applications," Chairman of Standards Writing Committee, Oak Ridge National Laboratory Standard NE-E7-9T, 1984.
JAMES A. FLAHERTY Page 5 REGISTRATION Professional Engineer In the State of Massachusetts PROFESSIONAL AFFILIATION American Society of Civil Engineers
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VECTRA CHARBEL M. ABOU-JAOUDE, P.E.
EXPERTISE Mr. Abou-Jaoude is a Project/SeNice Area Manager in VECTRA's Boston Office, with a broad technical and managerial experience in the power industry.
His areas of technical expertise are Structural Mechanics and Seismic Design; he has an in-depth knowledge of various industry codes/standards such as Sections Ill & XI of the ASME Code, ANSI B31.1, IEEE-344 and 382, various USNRC Reg. Guides and NUREG Reports, WRC Bulletins, AISC, and ACl-349.
He is well versed in the Generic Implementation Procedure developed by the Seismic Qualification Utility Group for the resolution of USl-A-46, and the methodologies developed by the industry for the response to Generic Letter 88-20 as outlined in NUREG-1407; he has completed the SQUG/EPRI sponsored A-46 and Seismic IPEEE training courses and has participated in several A-46/IPEEE walkdowns as an SRT member. While at VECTRA, he has lead the engineering efforts of various work scopes; his responsibilities have included:
Criteria development, training and personnel development, project execution, interface with regulators and outside organizations, and overall project management.
Currently, Mr. Abou-Jaoude is the Project Manager for the Northeast Utilities A-46 projects (Connecticut Yankee, Millstone Units 1 &2). He is also the Project Manager for the IP EEE peer review of the Perry Plant.
He is the Project Engineer for the PE Co (Peach Bottom 2&3) IPEEE/A-46 and PSE&G (Salem 1 &2) A-46 projects and an SRT member of the Wolf Creek and Limerick 1 &2 IPEEE efforts. At Connecticut Yankee, Mr. Abou-Jaoude has been instrumental in the successful completion of the project; he has provided cost effective resolutions to a number of outliers, and lead the development of implementation procedures for the procurement of new and replacement equipment.
Mr. Abou-Jaoude has also participated in Post-Earthquake Investigations at industrial facilities in California.
Mr. Abou-Jaoude was the Assistant Project Manager for the Civil/Structural effort at TU Electric CPSES Unit 2 Project. He had primary management responsibility for the work of 80 engineers in the Electrical Raceways, Seismic Equipment Qualification, and Seismic II/I disciplines. This effort involved the design validation of existing Raceway designs, issuance of new designs, establishing the qualification basis of all BOP Seismic Cat 1 and NSSS C1 E equipment, procurement of new and replacement equipment, structural evaluation of non seismic commodities using an A-46 walkdown based approach, and field engineering to support the completion and start-up of Unit 2.
Prior to his Unit 2 assignment at CPSES Mr. Abou-Jaoude was the Assistant Project Manager for the Secondary Water Chemistry Improvement Project at Consumers
\\'i VECTRA CHARBEL M. ABOU-JAOUDE Page Two EXPERTISE (Cont'd)
Power (Palisades).
This project involved modifications to the existing blowdown system, the addition of various equipment items, and the installation of 2000 ft. of piping. The design effort was completed in a period of six months with a peak staff of 40 engineers; the design has been successfully implemented and its operation has provided improvements beyond the plant's initial expectations.
In addition to this project he was involved in a number of projects for Consumers Power: He was the Project Engineer for consulting work related to the resolution of 79-i 4 piping and pipe support issues; he also was the Project Engineer for a modification to install a reactor head shielding which involved generating the amplified response spectra and performing the seismic analysis and qualification of the lifting ring/shielding structure.
Mr. Abou-Jaoude has also worked on a number of piping and equipment qualification projects for Commonwealth Edison and Northern States Power. He was the Project Engineer for the development of criteria to evaluate integral welded attachments for Prairie Island; the completion of this effort provided successful closure oJ an-NRG 79-14 issue.
Previously Mr. Abou-Jaoude lead a group of 18 engineers, working on the seismic qualification of BOP components, in support of a successful SQRT audit for TU Electric's Comanche Peak Station Unit 1.
He was responsible for the technical adequacy, budget and schedule of the following scope:
Preparation of summary packages and supporting calculations to demonstrate the seismic qualification of storage tanks, heat exchangers, pumps, valves, the diesel generator set, piping, and other electrical components (motors, battery racks, control panels, and instrumentation devices).
Evaluation of mechanical equipment rerating, under Section XI of the ASME Code, for revised design conditions such as pressures, temperatures, nozzle ioads, and or acceleration values (approx. 200 stress reports).
Mr. Abou-Jaoude was also involved in the Comanche Peak cable tray hanger design validation effort. He was a group lead responsible for qualifying cable tray systems.
This required detailed dynamic analysis and evaluation of structural members and anchorages. He was involved in the development of criteria for modification reduction techniques. He also worked on the dynamic testing of full scale cable tray systems and provided analytical results for correlation with measured test data.
CHARBELM.ABOU~AOUDE Page Three EXPERTISE <Cont'd)
Prior to joining ABB Impel!, Mr. Abou-Jaoude has worked in the Middle-East on the construction of several commercial and industrial reinforced concrete buildings. He has also worked as a field engineer responsibie for the installation and maintenance of equipment at an automotive refurbishing plant in the United Arab Emirates.
EDUCATION M.S., Civil Engineering, December 1985 University ot Michigan, Ann Arbor, Michigan B.E., Mechanical Engineering, July 1984 American University of Beirut. Box 11 0236, Beirut, Lebanon PROFESSIONAL AFFILIATIONS Professional Engineer - State of Connecticut, License No. 18527 American Society of Civil Engineers American Society of Mechanical Engineers Tau Beta Pi Honor Society Chi Epsilon Honor Society PUBLiCATIONS Lee, B. J., Abou-Jaoude, C. M., and De Estrada, M., "Issues of Control Panel Rigidity in Seismic Qualification," Proc. of 1991 Pressure Vessels and Piping (PVP) Conference, Vol. 220.
Lee, B. J., and Abou-Jaoude, C. M., "Effect of Base Uplift on Dynamic Response of Electrical and Mechanical Equipment," Proc. of 1992 Pressure Vessels and Piping (PVP) Conference, Vol. 237-2.
Roche, T. R., Abou-Jaoude, C.M., et al, " Comparison Between Analyticai and Test Results for Transformer Base Details," Proc. of 1993 Pressure Vessels and Plping (PVP) Conference, Vol. 256-2.
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AZIZ SABER PROFESSIONAL EXPERIENCE Mr. Saber is an Engineer IV in the Boston Office Civil/Structural Group. He has over eight years of experience in the power industry, and extensive experience in the design and installation of suspended distributed systems. He has an in depth knowledge of dynamic analysis and structural design; he is we!! versed in the use of various finite element codes (STRUDL, ANSYS, ADINA, NASTRAN) and the design criteria for nuclear power structures (Reinforced Concrete and Steel). Mr. Saber is an active member of ACI Committee 533 on precast panels.
Mr. Saber is currently involved in the IPEEE and A46 projects for NUSCo, PECo, NYPA and PSE&G. He is certified as SRT by the SQUG. Mr. Saber is responsible for review of the plant safe shutdown equipment list and the evaluation of equipment anchorage, concrete pedestals, and support details.
Mr. Saber has periormed detailed analysis on tanks, pumps, motor operated valves, heat exchangers and associated piping and supports using finite element anlaysis and detailed calculations.
Prior to his transfer to the Boston Office, Mr. Saber was assigned to the Comanche Peak Unit Civil/Structural Project as a site lead. He provided the coordination of the field engineering activities of the electrical raceways group in support of the construction and completion of the CPSES U2 designs.
Mr. Saber has worked on various other CPSES Unit 1 projects. He has worked on the Mechanical Equipment List project and with the Cable Tray and Cable Tray_Hangers Group. He was the lead engineer for the Field Engineering Group responsible for supporting activities and resolving any field problems with authorization to approve any design changes and assure their adherence with the design specifications and code Mr. Saber was also responsible for revising and updating the technical project design methodology and the installation and inspection specification tor eiectrical raceways.
He also designed and analyzed cable trays and components using computer aid programs and graphics and detailed calculations.
AZIZ SABER Page Two EXPERIENCE (Cont'd)
While assigned to the Train C Conduit project, Mr. Saber designed and analyzed conduit systems and supports for seismic loads using systems frequency, projected and/or tributary span methods. He was a lead engineer in the System Interaction Group for engineering evaluations of postulated interactions resulting from seismically induced failures of non-safety-related conduits incident upon safety-related systems, structures and components. His responsibilities included writing engineering design change notices to update and revise the project criteria, training personnel for using the field walkdown criteria and the plant documents; namely FSAR, structural drawings, composite piping drawings, HVAC iayout drawings, flow diagrams, Q-list and electrical wiring diagrams to resolve the postulated interactions based on field conditions along with engineering techniques.
Prior to joining VECTRA, Mr. Saber was a structural engineer responsible for designing and analyzing seismic loading structural supports in power plants utilizing computer programming and graphics. He supervised the installation of those supports.with the authorization to issue any field changes and assure their adherence with:the design specifications and code requirements.
EDUCATION M.S., Civil Engineering, University of Michigan, Ann Arbor B.S., Civil Engineering, The American University of Beirut, Lebanon PROFESSIONAL AFFILIATIONS Professional Engineer, State of Texas American Concrete Institute American Society of Civil Engineers The Masonry Society
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STEPHEN P. REICHLE PROFESSIONAL EXPERIENCE Mr. Reichle has over 20 years of power plant engineering, design, maintenance, and operations experience. As Technical Services Consultant for Mechanical Systems in VECTRA's Boston office he is currently assigned as the Project Manager for the Fire Hazards Analysis (FHA) project for the New York Power Authority. This project consists of updating the FHAs for both the James A. FitzPatrick and Indian Point 3 nuclear plants. The project also includes the preparation of an analysis that assesses the effects of pipe rupture, inadvertent actuation and manual use of fire protection systems on safety-related equipment at JAF and IP3.
Mr. Reichle is also currently serving as the Systems Project Engineer on the NRC's Unresolved Safety Issue (USI) A-46 projects for: Northeast Utilities (Millstone 1, 2 and Connecticut Yankee), Philadelphia Electric (Peach Bottom and Limerick) and Public Service Electric & Gas (Salem). In this role, he is responsible for the identification of safe shutdown paths and the development of a Success Path Component List for each unit. These NRC programs deal with the seismic adequacy, or margin of equipment in operating plants.
Mr. Reichle has prepared Design Baseline Documents (DBDs) for the feedwater and fire protection systems at the PECO Peach Bottom and Limerick nuclear plants. This project consisted of conducting the necessary research to identify the boundaries, interiaces and requirements of the individual systems. The documents also describe how each of the systems satisfies their design input and output requirements, and what modifications have impacted the system's original design basis. Mr. Reichle also participated in the Appendix R update project for the Limerick Nuclear Station by reviewing the new and updated shutdown methods identified for each fire area, and assisting in the resolution of shutdown concerns identified during the review process.
Previously, Mr. Reichle served as the Project Manager for the Appendix R Compliance Program and Fire Barrier Upgrade Projects at the Pilgrim Station. Mr. Reichle managed these programs for over two years, with tasks including the development of Appendix R. shutdown analyses, the development oi associated operating procedures, the review and upgrade of all Appendix R fire barriers, and the design of various electrical and mechanical system modifications. This project was staffed with approximateiy 25 engineers and technicians.
Mr. Reichle served as the Project Engineer, and managed the engineering resources, durina the uodate of the J. A. FitzPatrick Fire Protection Reference Manual, and supported the update of the Fire Protection Program Manual for Indian Point Unit 3.
STEPHEN P. REICHLE Page Two EXPERIENCE (Cont'd)
Both of these projects involved the update of fire protection and Appendix R programs to include the changes made by modifications, and the preparation of a new manual that included both programs.
Mr. Reichle also served as the Project Engineer for an Appendix R project for Northeast Utilities Millstone 3 Nuclear Power Plant. This project consisted of four major tasks: t) review the plant's safe shutdown methodology and equipment list to ensure completeness 2) identify which components might be affected for each fire area, 3) identify the worst case fire scenario (in terms of equipment loss) for each fire area, and
- 4) identify and prioritize the operator actions that need to be taken in each fire area.
Prior to this assignment, Mr. Reichle performed a design baseline verification of the Emergency Operating Procedures (EOP) for Nine Mile Point 1, and determined the impact of operating safety related systems with normally open manual valves at the system's interface with non-safety related portions of the system. His responsibilities on these projects included the preparation of verification packages to document design basis of input parameters to EOP flowcharts, preparation of various design calculations, and preparation of a report on the boundary valves. Also included within this project was a review of the plant's Service Water System and the effect of increased lake water temperature.
Mr. Reichle has also served as a technical specialist in support of triennial fire protection audits at the H.B. Robinson, Brunswick and Shearon Harris nuclear power plants. During these audits, he served as the Systems Engineer reviewing station operating practices, programs and procedures used to ensure safe shutdown of the plants in the event of a fire.
Mr. Reichle has also served as the Project Manager for the single failure analysis of the ECCS sub-systems, and their support systems, for the Connecticut Yankee plant. This project included the identification and revie\\N of potential equipment failures for each of the systems, including mechanical, electrical and instrumentation, during injection and recirculation modes in response to a LOCA.
In conjunction with the above single-failure analyses, a review of the CY surveillance procedures was periormed. This review was conducted to ensure that all ECCS redundant or required components were included in the appropriate procedure, and that proper surveillances were bein~ periormed to assure operability of the systems.
STEPHEN P. REICHLE Page Three EXPERIENCE fCont'd Prior to joining VECTRA, Mr. Reichle was a Senior Engineer at Cygna Energy Services and assisted in the preparation of the Appendix "R" review for various NUSCo generating stations. As a member of this project, he was assigned tasks such as developing safe shutdown scenarios and identifying equipment which needed to be protected, establishing safe shutdown fire areas, performing walkdowns of fire areas to verify the adequacy of existing barriers (including doors, dampers, and penetration seals), identifying barrier deficiencies, preparing justifications for exemption requests, and making recommendations for upgrading fire barriers or their penetrations to the required fire resistance rating.
Mr. Reichle also participated in preparing a conceptual design of a seismic hot shutdown system for the Yankee Rowe Nuclear Plant. This project reviewed the feasibility of providing a standby, portable pumping system made up of standard commercial grade components, that would deliver water to the steam generators and/or main coolant system in the event no other method was available. Included in this project was the identification system demands, sizing of components, identification of water sources, and providing an estimated cost to install the system.
In a previous assignment, Mr. Reichle served as Lead Engineer for the development of surveillance and maintenance procedures for the Shoreham Power Station. His responsibilities included the identification of maintenance and inspection requirements for all mechanical balance of plant equipment. He established the parts req_uirements, special tools, rigging and handling instructions for those procedures. Mr. Reichle also supervised additional tasks for the Shoreham Station including:
Development of Fire Protection Program Description and Associated procedures e
Development of Maintenance Program Description i\\JUREG-0612 Heavy Loads Analysis
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Rigging and Handling Procedures for NUREG-0612 Heavy Loads e
Preparation of Refueling Procedures Design, Analysis, and Fabrication of Fuel Handling and Reactor Head Strong back
STEPHEN P. REICHLE Page Four EXPERIENCE (Cont'd)
Before joining Cygna, Mr. Reichle held the position of Lead Applications Engineer for the Jamesbury Corp., a manufacturer of fluid control equipment. His responsibilities included supervising technical analysis, sizing equipment, selecting material and accessories, and resolving field installation and operational problems of motor-operated valves.
Mr. Reichle was responsible for sizing valve actuators (both pneumatic and electric) given the system operating conditions. For motor operated valves this task included determining the necessary torque output, then selecting the appropriate gear train configuration and motor size. For nuclear projects, motor sizing included considerations of both normal and degraded voltage conditions.
Earlier in his career, Mr. Reichie worked with Stone & Webster Engineering Corporation where he was the responsible engineer for liquid and solid radioactive waste systems.
Responsibilities associated with this position included: development of syste'm design and flow diagrams, engineering, selection of equipment and layout, preparation of equipment specifications and purchase requisitions. Other duties included review of system piping diagrams, and resolution of field installation problems. Mr. Reichle also assisted in the development of a spare parts program and database for Millstone Unit
- 3.
In his initial assignment at Stone and Webster, Mr. Reichle assisted in the preparation of a system operations manual for Connecticut Yankee. This work included. the writing of system descriptions and operating procedures for the waste evaporator degasifier, aerated drains, and steam generator blowoft.
Before Mr. Reichle's employment with Stone & Webster, he spent six years in the U. S.
Navy Nuclear Submarine Program where he qualified as an Engineering Watch Supervisor.
EDUCATION B.S., Mechanical Engineering, Central New England College AS., Mechanical Engineering, Worcester Junior College U.S. Navy Nuclear Power School and Prototype Training Graduate Work, Fire Protection Engineering, Worcester Polytechnic Institute
STEPHEN P. REICHLE PROFESSIONAL ACTIVITIES Member, American Society of Mechanical Engineers Member, Society of Fire Protection Engineers Page Five
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JOHN G. CONNOLLY PROFESSIONAL EXPERIENCE Mr. Connolly is an Engineer Ill with the Boston Office of VECTRA.
He is presently assigned to the Motor Operated Valve (MOV) Modification project (NRC G.L. 89-1 O) for Boston Edison Company's (BECo) Pilgrim Nuclear Power Station (PNPS).
He is responsible for preparing Plant Design Change (PDC) packages, Safety Evaluations and procurement specifications for MOV upgrades.
Prior to this project, Mr. Connolly was assigned to the NRC's Unresolved Safety Issue (USI) A-46 project for Public Service Electric & Gas' Salem Units 1 & 2.
His responsibilities included the identification of safe shutdown paths, the development of a Success Path Component List for each unit and performing the plant walkdowns.
These NRC programs deal with the seismic adequacy, or margin of equipment in operating plants.
He was previously assigned to the Design Basis Document project for Niagara Mohawk Power Corporation's Nine Mile Point Unit 2. He was responsible for the development of the design basis documents for the Foam, Halon and C02 Fire ProtEiction Systems.
This involved developing a concise technical document which summarized the basis for the plant design and operation devised from industry codes and standards, calculations, drawings, licensing documents, specifications, and design criteria documents.
Mr. Connolly was assigned to the NRC's USI A-46/SQUG project for Northeast Utilities Service Company, Millstone Unit 2 and Connecticut Yankee plants.
He was responsible for the identification of those systems and safe shutdown paths used to accomplish the plant safe shutdown functions as well as the components necessary to align these paths.
All paths and components were chosen based on a safety classification. approach with the application of the SGUG GIP criteria such that the integrity of the Reactor Coolant System pressure boundary is maintained and the reactor is shut down and maintained in a safe shutdown condition.
Prior to this project, Mr. Connolly was responsible for the development of the design basis document for the Standby Diesel Generator Air Start System at Niagara Mohawk's Nine Mile Point Unit 2.
In an earlier assignment at Niagara Mohawk's Nine Mile Point Unit 1, Mr. Connolly assisted in the start-up of the Design Basis Reconstitution Project. He was assigned to the development of the design basis documentation for the Turbine Building and Reactor Building Closed Loop Cooling Systems.
JOHN G. CONNOLLY PAGE2 EXPERIENCE (Cont.)
Mr. Connolly has held project assignments on various systems for Niagara Mohawk's Nine Mile Point Unit 1.
His responsibilities included performing mechanical design change requests, installation plans, and bills of material for various instrumentation and control modifications.
He was previously assigned to projects for Northeast Utilities Connecticut Yankee and Millstone 1, 2 and 3 nuclear Power Plants. His responsibilities included reviewing prior plant deficiencies to determine if they were erosion/corrosion related. This information was used to determine the operability status of Connecticut Yankee and Millstone Units 1, 2 and 3 after the Millstone 2 erosion/corrosion failure.
Mr. Connolly was previously assigned to the 1991 Millstone Ill Appendix R Update.
This involved defining fire areas and establishing operator activity matriqes for the Millstone Ill Appendix R Safe Shutdown Analysis.
Prior to this project, Mr. Connolly was assigned to projects for New York Power Authority's Indian Point Unit 3 and James A. FitzPatrick Nuclear Power Plant.
His responsibilities included a comprehensive review of the Appendix R Safe Shutdown Analysis and Fire Hazards Analysis. This included a review of modification packages to determine their effect on licensing commitments, safe shutdown capabilities and fire protection/detection. He also prepared fire area and fire zone analyses as well as fire protection and detection system descriptions.
In an earlier assignment at Niagara Mohawk Power Corporation's Nine Mile Point Unit 1, he performed a design baseline verification of their Emergency Operating Procedures (EOP).
His responsibilities included preparing verification packages to document design basis of input parameters, preparation of alternate calculations, generation of new calculations, and verifying design basis of EOP flow charts.
Mr.
Connolly also participated in the preparation of 1 OCFRS0.59 determinations and safety evaluations for pipe support modifications, and the resolution of problem reports for various mechanical systems.
He was previously assigned to the Engineering Programs Group at Seabrook Nuclear Generating Station where he was responsible for the evaluation of material and purchase specifications for plant systems, writing engineering procedures and reviewing applicable test methods and calculations.
This effort was part of the Commercial Grade Dedication Program.
JOHN G. CONNOLLY PAGE3 EXPERIENCE (Cont.)
Mr. Connolly also held an earlier assignment with the Engineering Services Department at New Hampshire Yankee's Seabrook Station. His responsibilities included planning &
scheduling Design Change Requests (DCR's), Requests for Engineering Services (RES's), and other engineering action items for the Plant Engineering Department using the Primavera Project Planner (P3) and dBaselll programs.
Other responsibilities included developing databases and reports as necessary for tracking in-house Engineering commitments, as well as representing Engineering at various interface meetings and performing special projects as necessary.
Mr. Connolly has also participated in the inspection and overhaul of non-safety class valves during the 1986 l.S.l./Refueling Outage at the J.M. Farley Nuclear Power Station, Unit 1, for the Alabama Power Company.
Mr. Connolly also has experience in evaluating Naval Propulsion Syst~ms.
This involved a comprehensive review of the system design criteria, calculatJons, applicable industry codes, i.e., ASME, ANSI, Code of Federal Regulations, etc., and actual system test data to improve efficiency and system performance. His responsibilities have also included the development of a Navy Standard Work Item for main feed pumps, a feasibility study to support the development of the Navy Valve Standardization Program, and an evaluation of high and low pressure air systems for naval vessels.
EDUCATION B.S., Marine Engineering, Massachusetts Maritime Academy, 1986 MISCELLANEOUS United States Coast Guard, Licensed Third Assistant Engineer, steam or motor vessels, unlimited horsepower.
STEPHEN ANAGNOSTIS EDUCATION:
B.S. - Civil Engineering, Columbia University School of Engineering, 1974 M.S. - Structural Engineering; Massachusetts Institute of Technology, 1976 PROFESSIONAL HISTORY:
Stevenson & Associates, Inc., Senior Consultant 1989 - present Project *Manager, 1983 - 1989
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URS I John A. Blume & Associates, Engineers, Boston, Massachusetts, Project Engineer 1982 - 1983; Senior Engineer, 1980 - 1982,
Charles Stark Draper Laboratory, Cambridge, Massachusetts, Technical Staff, 1976 - 1980; Draper Fellow, 1974-1976
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PROFESSIONAL EXPERIENCE:
Mr. Anagnostis joined Stevenson & Associates in February 1983 as Project Manager of the Boston
, area office. He is presently as Senior Consultant involved in numerous seismic walkdowns, and in developing S&A's software packages that automate the analytical effort to develop seismic fragilities and HCLPF's from field data. He is the principal author of S&A's GIPPER program, and of the PCMODAL family of programs for modal and vibration analysis.
Mr. Anagnostis participated on the pilot plant seismic walkdowns for the SQUG prog!"iim at both Zion and Nine Mile. Subsequent to the pilot plant walkdowns, he developed portions-of the Generic Implementation Procedure for the SQUG Program. He has recently conducted seismic walkdowns at the Salem, Pilgrim, and Ginna stations for both IPEEE and A-46 seismic considerations.
Mr. Anagnostis was extensively involved in both analysis (frequency domain and time domain structural dynamics) and testing (in-situ modal and full-scale shaking-table) at URS/Blume's Boston office. He had lead technical responsibility for a two year program to develop a seismic evaluation criteria for electrical raceway systems at eight of the oldest United States nuclear power stations. This program included the design, supervision, and data analysis of shaking-table tests of full-scale
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raooway systems, cyclic/fatigue tests of raceway components, and the development of analytical evaluation techniques incorporating the test results.
As a member of the technical staff of Charles Stark Draper Laboratory, Mr. Anagnostis was involved in the assessment of space based surveillance (infra-red and radar) and defense systems for the Defense Advanced Research Projects Agency. He was a major author of a software simulation system to assess the capabilities of spaced based optical systems including structural vibrations, control dynamics, and optical performance.
PROFESSIONAL GROUPS:
Committee, Working Group for the Analysis and Design of Electrical Cable Support Systems Member, American Society of Civil Engineers Nuclear Structures and Materials PUBLICATIONS AND REPORTS:
EPRI Report, HGENRS 1.0 Users Manual and Theoretical Development & Program Verification Manual,H Stev_enson & Associates, Woburn, MA (March 1991)
"Equipment Anchorage Evaluation Software", ANCHOR 3.0, Stevenson & Associates, Woburn, MA (July 1990)
"Vibration Engineering in the Semiconductor lndustry,"with W. Djordjevic and T. M, Tseng, Test and Measurement World, (May 1984)
"EDASP: Structural Modification Program,"withW. DjordjevicandT. M. Tseng, Proceedings, Second International Modal Analysis Conference, Orlando, Florida (February 1984).
"Implementation of Software to Account for Equipment Modifications," with W. Djordjevic, C. Gangone, R. Jenkins and A. Marion, Transactions, ANS 1983 Winter Meeting, San Francisco, California (October 1983)
"Theory and Implementation of Analytical Tools to Calculate Response Changes in Equipment Previously Evaluated by Testing,~ with W, Djordjevic, Transactions, 7th International Conference on
, Structural Mechanics in Reactor Technology (August 1983)
"Seismic Evaluation of Electrical Raceway Systems," with W. Djordjevic and F. Elsabee, 1983 ASME Pressure Vessel and Piping Conference, Portland, Oregon (June 1983)
"Space Radar Large Aperture Simulation/Analysis," with F. Ayer, CSDL R-1413 (~tober 1980)
"Large Beam Expander Technology Design, Analysis and Simulation Development Program" (U), with K. Soosaar, et al., CSDL R-1224 (Secret), (Aprii°1979)
"High Altitude Large Optics Integrated Simulations" (U). with K. Soosaar. eta I., CSDL R-1286 (Secret),
(July 1979)
"Passive and Active Suppression of Vibration Response in Precision Structures" (U), with K. Soosaar et al., CSDL R-889 (Secret) (February 1978)
"Optimal Actuator Locations for Mirror Surface Control," M.S. Thesis Massachusetts Institute of Technology (May 1976)
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WALTER DJORDJEVIC EDUCATION:
B.S. - Civil Engineering, University of Wisconsin at Madison, 197 4 M.S. - Structural Engineering, Massachusetts Institute of Technology, 1976 REGISTRATION:
State of California, State of Wisconsin, Commonwealth of Massachusetts, State of Michigan PROFESSIONAL HISTORY:
Stevenson & Associates, Inc., Vice President and General Manager of the Boston office, 1983 - present URS/John A. Blume & Associates, Engineers, Boston, Massachusetts, General Manager, 1980 - 1983; San Francisco, California, Supervisory Engineer, 1979, - 1980 lmpell Corporation, San Francisco, California, Senior Engineer, 1'975 - 1979 :
, Stone & Webster Engineering Co_rporation, Boston, Ma~sachusetts, Engineer, 1974-1976 PROFESSIONAL EXPERIENCE:
Mr. Djordjevic founded the Stevenson & Associates Boston office in 1983 and serves as Vice President and General Manager of the Boston area office.
Mr. Djordjevic is expert in the area of dynamic qualification of electrical and mechanical equipment.
He has participated in and managed over twenty major projects involving the evaluation and qualification of vibration sensitive equipment and seismic hardening of equipment. As demon-strated by his C9mmittee work and publications, Mr. Djordjevic has participated in and contributed steadily to the development of equipment qualification and vibration hardening methodology.
Mr. Djordjevic's previous walkdown experience included all of the SEP plants (8 plants), Nine Mi1e-Unit 1, D.C. Cook-Units 1 &2, the Hanford Reservation Purex facility and the Savannah River Plant Reservation L-Reactor.
Representative projects include overseeing the SEP shake-table testing of electrical raceways, in-situ testing of control panels and instrumentation racks at various nuclear facilities, equipment anchorage walkdowns and evaluations at various nuclear facilities, principal author of the CERTIVALVE software package to evaluate nuclear service valves, and contributing author in
=-
the development of the ANCHOR and EDASP software packages commercially distributed by
Stevenson & Associates.
Mr. Djordjevic has been involved extensively in the reassessment of safety-related equipment for commercial nuclear facilities and government U.S. Department of Energy facilities, for which he maintains an active Q-clearance status. He has served on advisory groups and review teams touring older existing nuclear facilities to assess safety and has performed earthquake reconnaissance at such installations. following seismic events.
PROFESSIONAL.GROUPS:
Member, Institute of Electrical and Electronics Engineers, Nuclear Power Engineering Committee Working Group SC 2.5 (IEEE-344)
Chairman, American Society of Civil Engineers Nuclear Structures and Materials Committee, Working Group for the Analysis and Design of Electrical Cable Support Systems Member, American Society of Mechanical Engineers Operation, Application, and Components Committee on Valves, Working Group SC-5
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CERTIFICATION:
EXPERIENCE:
ALAN A. JOHNSON SENIOR PROJECT ENGINEER Bachelor of Science, Engineering, 1977 Graduate courses (15) in Structural Dynamics and Engineering Mechanics Widener University, Chester, PA EPRI trained SQUG Seismic Capability Engineer Public Service Electric and Gas, Hancocks Bridge, NJ (January 1992 to Present) As Civil/Structural Senior Project Engineer responsible for coordinating civil and structural engineering tasks in support of BWR and PWR plants. Also perform analysis and design for civil items including concrete and steel structures, HV AC duct and supports, electrical raceways, and equipment supports.
Miller - Remick Corporation, Haddon Heights, NJ (September 1989 to December 1991)
As Senior Project Engineer responsible for management and technical support of multi-discipline projects in the manufacturing, petrochemical, water treatment, and environmental industries. Managed all aspects of projects from proposal to product delivery while assuring cost, schedule, and quality goals were met. Major design projects managed at Miller - Remick were: Site plan and structural design of reprocessing and storage facility for hazardous waste; Developed structural and mechanical design, drawings, and specifications for concrete and masonry fuel oil storage and chemical feed buildings for five water treatment plants; Designed of pile supported flare tower foundation, pipe supports, and heavy equipment foundations for a refinery's marine vapor recovery system; Removal, remediation,* and replacement of underground storage tanks for regional water company; Procured testing services, developed specifications for removal, and prepared site assessment and closure plans for underground tank removals; Designed new underground tank storage system enclosed in concrete vaults.
Primary technical duties were in industrial steel design; concrete foundation, retaining wall, pier, slab, and containment dike design; and both plain and reinforced masonry building design. Experienced with AISC, ACI, and BOCA codes. Skilled in use of STAAD, STRUDL, and STARDYNE structural analysis programs As Construction Manager, Management assignments included the construction of a waste water treatment facility and modification of a fiberglass manufacturing facility.
Responsibilities in these assignments were site engineering, safety, construction quality, labor relations, and client liaison.
Stone & Webster Engineering Corporation, Cherry Hill, NJ and Decatur, AL_(May 1980 to August 1989) As Lead Engineer at TV As Browns Ferry Nuclear Plant in Decatur, AL, responsible for design change request evaluations for structural, HV AC, and piping systems. Managed staff of engineers who provided 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> plant support to meet critical construction milestones. Directed small bore and tubing groups in their piping analysis, design modification, and design issuance activities. Also responsible for interface with plant operations and craft to assure coordination with plant startup activities.
AFFILIATIONS/
LICENSES:
Alan A. Johnson In Cherry Hill, NJ, headed the engineering mechanics technical evaluation of Browns Ferry Nuclear Plant's HV AC, pipe break restraint, seismic equipment, and piping system programs. This review provided part of BFNP's justification for restart.
As Assistant Lead Engineer directed an engineering group's design and verification of built-up steel plate structures used as pipe whip restraints and pipe anchors in a PWR.
Developed design criteria for break postulation and structural design of the restraint/ anchor.
As a Senior Engineer completed technical, procurement, and licensing assignments for a BWR plant. Tasks included development of primary containment and reactor response spectra from annulus pressurization loads, design and procurement responsibility for ASME VIII, ASME III, and fiberglass tanks, design and procurement of a remote operated gantry crane used for decontamination of refueling pools, pipe whip restraint structural design including nonlinear dynamic analysis to develop loading and structural response, design of seismic equipment supports that maintained validity of seismic qualification.
Widener University, Chester, PA (September 1977 to June 1979)Graduate Teaching Assistant Instructor in soils and mechanics laboratories. Developed structural analysis program for use on University computer.
American Nuclear Society American Society of Civil Engineers American Society of Testing Materials EIT Pennsylvania
EDUCATION:
REGISTRATION:
CERTIFICATION:
RESPONSIBILITIES:
EXPERIENCE:
ROBERT H. KOCH SENIOR STAFF ENGINEER BS, Civil Engineering, San Jose State, CA MS, Structures and Applied Mechanics, San Jose State, CA MBA, Management, Andrews University, MI Registered Professional Civil Engineer, New Jersey GE37244 EPRI trained SQUG Seismic Capability Engineer Mr. Koch is a Senior Civil/Structural Project Engineer responsible for coordination of civil, structural, and architeetural work at Artificial Island which includes Hope Creek (BWR) and Salem (PWR) Nuclear Generating Stations.
These responsibilities include assessing the scope of work for all new projects, assigning and directing in-house and contract engineers performing the work, providing coordination with other functional disciplines, monitoring budgets and schedules, and approving all design drawings and calculations. Mr.
Koch is also responsible for the development of the civil, structural and architectural programmatic and technical standards for the Salem Gen. Stations.
Mr. Koch has over fourteen years of experience in the structural analysis, design and installation of nuclear-fueled power plant structures and commercial buildings.
Presently, Mr. Koch is employed by Public Service Electric and Gas Co. in New Jersey and is the senior project engineer on the Salem Spent Fuel Pool Rerack Project, Structural Load Management Recovery Project, Seismic Verification of HV AC Duct and Supports Project, and Structural Configuration Baseline Document and Discrepancy Management Project.
Past projects completed while in this capacity include Artificial Island Warehouse Project and Seismic Verification of Salem Gen. Stations Electrical Raceway using SQUG Project. In his role of lead structural project engineer, he has been involved in many projects including Salem Service Water Piping Replacement, Configuration Baseline Documentation (CBD), Salem Appendix R Firewrap and Firedampers, Nuclear Department Administration Building Expansion, and Electrical Distribution Upgrades.
Prior to joining PSE&G, Mr. Koch was employed by Bechtel Power Corporation. In his last assignment he was seconded to PSE&G as the lead civil engineer on the Control Rod Drive Rebuild Facility Project at the Hope Creek Gen. Station.
Civil Scope of work included providing shield walls, bridge cranes and monorails, transfer casks and a control room.
Previous assignments for Bechtel Power Corp. included being a resident engineer at the Limerick and Hope Creek Gen.
Station jobsites. The responsibilities included providing construction support and approving field change documents.
The Limerick assignment involved coordinating with the piping and pipe support groups while the Hope Creek assignment entailed all structures inside and including the primary containment. He also worked as a design engineer on the Hope Creek project in San Francisco. This involved the design and analysis of a variety of structures such as pipe whip restraints, platforms, and the biological shield and pedestal. He was also involved in the administration and technical review of the plant unique analysis performed by NUTE CH.
He began his engineering career with Sargent and Lundy Engineers in Chicago, where he was a design engineer on the Fermi 2 Nuclear Power Plant and Zimmer Generating Station projects. On the Fermi 2 project, he approved field change requests for cable tray and conduit supports and generated calculations for small-bore pipe supports. At the Zimmer jobsite he provided structural support to the piping and pipe support group.
CHIMAN N. ANTALA LEAD ENGINEER EDUCATION: M.S.C.E. from Polytechnic Institute of Brooklyn, Brooklyn, New York in 1974.
CERTIFICATE EPRI trained SQUG Seismic Capability Engineer EXPERIENCE: Structural Engineer with 26 years of experience in engineering design and analysis of steel and concrete structures of Nuclear, Chemical, Process and Industrial plants.
2/81 to Present Public Service Electric and Gas Co. in New Jersey Presently, a lead engineer on civil, structural, architectural work at Artificial Island which, includes Hope Creek (BWR) and Salem (PWR) Nuclear Generating Stations.
Responsibilities include concrete and steel structures, pipe support, HV AC duct support and electrical raceway support analysis and design. Duties also include monitoring and coordinating of contract engineering services.
10/79 to 1/81 Untied Engineers & Constructors, Inc., Phila., Pennsylvania Pipe support engineer: Contract position on Salem Units 1&2 pipe supports and multiple supports,PASNY & WPPSS pipe supports 10/78 to 9/79 Research-Cottrell, Inc., Somerville, NJ 8/77 to 12/77 10/75 to 7/77 5/74 to 3/75 2/74 to 4/74 4/71to1/74 2/69 to 1/71 Structural engineer: V. Y. Dallman Station, duct and duct supports design.
Responsible for design of flues, slide plates, support steel and foundations.
Badger America, Inc., Cambridge MASS.
Structural engineer: Contract position on SASOL II plant of South Africa.
Responsible for steel and concrete structure design.
Buell Emission Control-Envirotech Division, Lebanon, PA Structural engineer: Contract position and later regular, on CIPS S02 removal system.
Responsibility included design of flues, slide plates, pipe supports, structural steel, concrete foundations, precoolers, precipitator test stands.
United Engineers & Constructors, Inc., Phila., PA Design engineer: Bethlehem Steel's 13" Bar Mill Project.
Duties included design of steel and concrete structures drafting and detailing, estimating quantities, bill of material, etc.
Lummus company, Bloomfield, NJ Designer: Chemical process facilities.
Duties included design of beams, slabs, pipe rack bents, steel framing for equipments, service platforms, spread and pile footings for tanks.
T. Moriarty & Son, Inc., Brooklyn, NY Estimator: Residential, commercial, industrial buildings, subway stations, etc Duties included quantity take-off and pricing for civil, structural and architectural trades, soliciting bids from other trades such as mechanical, electrical, instrumentation.
and equipment subcontractors and bid assembly.
Capitol Engineering Corp., Dillsburg, PA Structural engineer: Highway Bridges.
Duties included design of steel and concrete bridges for hiways.
JAMES F. GLOVA Project Structural Engineer Twenty-one years of experience in project supervision, structural engineering, advanced analytical techniques and design procedures for extreme load phenomena on major nuclear power plant facilities in the United States and overseas.
EXPERIENCE:
1990 to Present 1986-90 GILBERT/COMMONWEALTH since 1973 Project Structural Engineer -
Seconded to Public Service Electric and Gas's Civil/Structural Engineering Staff at Salem Generating Station Units 1 and 2.
Responsible for the complete technical bases of the project, coordinating with engineering service consultants and integrating the project modifications with the station requirements on major projects.
Appendix R Cable Separation Project -
Responsible for a cable tray testing program to determine section properties and ultimate capacity, and dynamic analyses to support system modifications for fire proofing.
Seismic Evaluation of Electrical Raceway Syste~s Project -
Responsible for the implementation of a SQUG seismic evaluation program in response to Unresolved Safety issue USI A-46, and the extension of the SQUG methods to modifications of raceway systems.
Appendix R Fire Damper Upgrade Project -
Responsible for the assessment of HVAC duct systems and supports for the addition of fire proofing material required to upgrade fire dampers to meet fire protection license conditions.
HVAC Discrepancy Issues Project -
Responsible for the development of an acceptance criteria to verify the seismic adequacy of existing HVAC duct systems and supports that is consistent with SQUGs Generic Implementation Procedure (GIP), implementation of a trial program to test the acceptance criteria, utilization of the refined acceptance criteria on the balance of plant systems, and extension of the methodology to the design of new HVAC duct systems and supports.
Structural Engineer - Pennsylvania Power and Light Company's Susquehanna Steam Electric Generating Station Units 1 and 2 - Responsible for the dynamic impact analyses required to assess different plant structures and components, including the reactor vessel head for heavy load drop evaluations that could occur during refueling.
JAMES F. GLOVA (Continued)
Structural Engineer - Cleveland Illuminating Company's Perry Nuclear Power Plant Unit 1 (1200 MW)
Responsible for the containment venting analysis which modeled the lower containment by finite elements to determine the ultimate pressure limit of containment by using a non-linear analysis solved by ADINA when subjected to the potentially severe combination of accident hydrostatic press and temperature.
Structural Engineer -
Responsible for the ASME qualification of the stiffened dome of the steel containment vessel using the finite element method to evaluate local stresses due to piping loads.
Responsible for the establishment of project criteria for the evaluation of HVAC duct and supports.
Performed seismic analysis of existing HVAC systems represented by a three dimensional model of duct and supports using the response spectrum analysis technique for Tennessee Valley Authority's Sequoyah Nuclear Power Plant Unit 2.
Structural Engineer - Co-authored the general design criteria document for civil structures using the FSAR, existing issued design criteria and issued commitment requirements for Tennessee Valley Authority's Brown Ferry Nuclear Power Plants Units 1, 2 and 3.
Structural Engineer -
Developed and implemented, as an independent contractor, the technical and project requirements for the qualification of existing Category I HVAC duct supports for the building housing the fifth diesel generator for Pennsylvania Power and Light Company's Susquehanna Steam Electric Station Units 1 and 2.
Structural Engineer -
Responsible for evaluation of cable tray raceway and supports for effects of additional weight due to fire protection wrapping material required for compliance with 10CFR50 Appendix R and seismic qualification of the loss of off-site power inverter and design of the frequency tuned inverter rack to maintain the existing qualification for Pennsylvania Power and Light Company's Susquehanna Steam Electric Station Units 1 and 2.
Structural Engineer - Tennessee Valley Authority, Browns Ferry Nuclear Power Plan Units 1, 2 and 3 -
Responsible for redesign of existing pipe supports for increased water hammer loads for piping systems in the service water tunnels.
1981-86 1980-81 1976-80 JAMES F. GLOVA (Continued)
Structural Engineer -
Texas Utilities Generating Company, Commanche Peak Steam Electric Station, Units 1 and 2 -
Performed as a consulting technical expert for an on-site third party design review of conduit raceway and support design for TERA Corporation.
Task Structural Engineer -
General Public Utilities Nuclear Corporation, Three Mile Island Nuclear Power Plant, Unit 1 (871 MW) -
Provided technical and project supervision for the qualification of existing unistrut conduit/cable tray supports to implement a comprehensive support load management program.
Project Structural Engineer -
Three Mile Island, Unit 1 -
Responsible for all aspects of structural modifications and additions.
Project Structural Engineer - Virginia Electric Power Company, North Anna Nuclear Power Plant, Units 1 and 2, and Surry Nuclear Power Plant, Units 1 and 2 -
Responsible for all structural engineering for plant modifications.
Group Supervisor -
Provided technical supervision for the non-linear time history dynamic analysis and restraint design for high-energy-pipe-systems subjected to postulated breaks on Cleveland Electric Illuminating Company, Perry Nuclear Power Plant, Units 1 and 2 (1200 MW); Florida Power Corporation, Crystal River Nuclear Power Station, Unit 3 (855 MW) and Omaha Public Power Plant, Units 1 and 2 (1200 MW); Florida Power Corporation, crystal River Nuclear Power Station, Unit 3 (855 MW) and Omaha Public Power District, Fort Calhoun Nuclear Station, Unit 1 (457 MW).
Structural Engineer -
Field engineering of Seismic Class I pipe support structures including drilled-in concrete anchors in response to Nuclear Regulatory Commission's Inspection and Enforcement Bulletins 79-02 and 79-14 for Three Mile Island, Unit 1.
Structural Engineer - Responsible for liaison with contractors during erection of the service and water treatment buildings, during fabrication and installation of reactor building penetrations, reactor building liner, and stainless steel fuel pool liners, and during preparation of the test procedure for the reactor building Structural Acceptance Test.
In charge of the maintenance of the structural concrete, structural steel, and other miscellaneous specifications in accordance with accepted industry codes and standards.
Responsible for non-linear time history dynamic analysis of ruptured high energy piping systems and restraints, design of reinforced concrete slabs, and miscellaneous building components
1974-75 1973-74 EDUCATION:
JAMES F. GLOVA (Continued) for the condenser circulating water intake screen and pumphouse.
Prepared Tornado Missile Impact Probability Study for South Carolina Electric and Gas Company, V. C. Summer Nuclear Station, Unit 1 (900 MW).
Electric Utilities of Croatia and Slovenia, KRSKO Nuclear Power Plant, Unit 1 (600 MW) - Design review of seismic resistant reinforced concrete building frames for the turbine building.
Structural Engineer -
Rochester Gas and Electric Corporation, R. E. Ginna Nuclear Station, Unit 1 9490 MW)
- Non-linear time history analysis and design of concrete, steel frame structures, including a building supported on caissons; and design of structural systems to support safety related conduits, ducts and pipes.
Structural Engineer - Crystal River, Unit 3 and Three Mile Island Nuclear Station, Unit 1 - Non-linear time history dynamic analysis of high energy piping systems with structural interfaces and building elements for the effects of pipe rupture and jet thrust transients.
B.S., Civil Engineering, Michigan Technological University, 1970 M.S., Civil Engineering, Structural Engineering, Michigan Technological University, 1973 Additional courses in:
Seminar on Extreme Load Design for Effects of Earthquake, Tornado, Missile, Jet Thrust, and Pipe Whip by American Society of Civil Engineers
{ASCE) in conjunction with Dr. J. D. Stevenson, Philadelphia, Pennsylvania, 1974 Computer Workshop in Earthquake and structural Dynamics, Union College Technical Institute in conjunction with ASCE, Schenectady, New York, 1975 Analysis and Design of Elastic Shell Structures, Lehigh University, 1976 Practical Steel Design for Buildings, 2-20 Stories, American Institute of Steel Construction, 1977 Fundamentals of Welding, Gilbert/Commonwealth, 1983 Foundations of Management, Gilbert/Commonwealth, 1983 Load and Resistance Factor Design, American Institute of steel Construction, 1987 SQUG Walkdown Screening and Seismic Evaluation Training Course, EPRI SQUG, 1992 Seismic PIE Add-on Training Course, EPRI SQUG, 1992
- REGISTRATION:
PUBLICATION:
CLEARANCES:
JAMES F. GLOVA (Continued)
Professional Engineer -
Pennsylvania (1976)
"Structural Analysis and Design of Pipe Whip Restraints", Specialty Conference on Structural Design of Nuclear Power Plant Facilities, Co-authored, Illinois, 1973.
"Seismic Design of Caissons for In-situ Conditions",
sixth World conference on Earthquake Engineering, International Association of Earthquake Engineers, Co-author, New Delhi, India, 1977.
"Seismic Adequacy Verification of HVAC Duet System and Support for an USI A-56 Nuclear Power Plant",
Fifth Symposium or current Issues Related to Nuclear Power Plant Structure Equipment and Piping, Co-author, Lake Buena Vista, Florida, 1994 Radiation Work Permit and Health Physics trained.
Sol M. Feldman Seismic Capability Engineer QUALIFICATIONS Mr. Feldman has more than 32 years of experience in the engineering industry, including over 21 years of diverse engineering experience in progressively responsible positions on both nuclear construction projects and operating nuclear projects. Mr. Feldman most recently completed an assignment as Team Leader for the seismic adequacy evaluation of essential communication facilities for a confidential client. The team assessed the adequacy. of the mechanical, electrical and controls equipment for key ~ommunications facilities in the Los Angeles, CA area following the North Ridge earthquake. In addition to equipment walkdowns and assessing the adequacy of essential equipment post earthquake, the team was tasked with identifying weak links and developing recommendations to improve the reliability of the communication facilities.
Mr. Feldman previously completed an assignment as Task Manager for the Seismic Verification of Electrical Raceways using SQUG Methodology Project at the Salem Generating Station. In this capacity he managed the work of a group of engineers and the work of a SQUG Consultant to successfully complete this project on schedule and within budget. He was a member of the walkdown team and was also responsible for developing budgets, schedules, and staffing requirements; attending project meetings, and preparing progress reports for the Project Mangers' approval; and for reviewing each work product for completion and consistency with the PSEStG requirements.
Most recently he completed an assignment at the Tennessee Valley Authority's Bellefonte Nuclear Station as a Senior Principal Mechanical Engineer. He was assigned to the Seismic Qualification Group in the Completions Department where he was responsible for evaluating and reconciling the seismic adequacy of mechanical and electrical equipment including equipment walkdowns and generating calculations to document adequacy.
Mr. Feldman previously completed an assignment as Task Manager for the Extraction Steam Piping Demolition/Replacement Constructibility Review Project for the Hope Creek Station. In this capacity he managed the work of a group of engineers and construction personnel in a fast tract effort for walkdowns of the plant area, development of rigging plans, identification of removal and load-in paths, and the detailed identification of interferences to be removed to facilitate the replacement of the extraction steam piping.
Previously, he was assigned to the Salem Unit 2 Turbine Generator Repair Project as Lead Mechanical Engineer at the site. In this capacity, he was responsible for supervising a staff of engineers and designers preparing DCPs and calculations for this project.
Prior to this assignment, he served as Senior Mechanical/Piping Engineer on Illinois Power Company's Clinton Power Station Design Transition Support Team where he provided assistance in developing and managing a plan to establish an internal design capability within their Nuclear Station Engineering Department.
- 2.
S. M. Feldman cont.
Previously, as a member of Division Staff, Mr. Feldman developed a plan for the implementation of a complete USI A-46 program for prospective client utilities. This required the gathering of reference information, researching important technical issues, and becoming familiar with the SQUG/NRC program for USI A-46 closure. A successful sample program was completed consisting of a component qualification using the GIP guidelines.
Previously, as Project Engineer on Tennessee Valley Authority's Browns Ferry Nuclear Plant hanger and analysis reconciliation program project, he had overall technical responsibility for the project personnel assigned to Stone & Webster's Cherry Hill office. The work involved reconciliation programs for analysis of safety-related Class 1 piping and associated supports and HV AC ducts and duct supports.
Previously, as Project Engineer for site activities at TU Electric's Comanche Peak Steam Electric Station - Units 1 and 2, he was responsible for all pipe stress analysis and pipe support design efforts assigned to the site, including large-bore and small-bore piping for both units.
Other efforts at the site included snubber reduction and hanger optimization, pipe stress analysis of small-bore piping supports, pipe support design modifications for large-bore pipe supports, and drafting of all pipe support design and location drawings.
As a collateral responsibility with the above, as Mechanical Section Manager, he managed all section 3ftivities, including programs for the reconciliation of mechanical equipment qualification and piping nozzle load for Nine Mile Point Nuclear Station and for River Bend Station. In this capacity, he was responsible for supervising a staff of engineers in areas of major equipment support design, pipe rupture restraint analysis and design, tank and vessel design, specialty equipment design, and the seismic qualification of mechanical and electrical equipment. This included the preparation of NRC SQRT and PVORT documentation packages and the subsequent presentation and discussion of this material with the NRC Review Team.
Since joining Stone & Webster, Mr. Feldman was also assigned to an 800-MW boiling water reactor plant and a 900-MW pressurized water reactor plant as Support Engineer, to an 830-MW pressurized water reactor plant project as Principal Engineer and Task Engineer, and to division management staff as Mechanical SupeIVisor. He was also Equipment Specialist for pipe rupture restraints and a division representative on the Equipment Qualification Review Board.
Prior to joining Stone & Webster, Mr. Feldman was Senior Scientist for the AVCO Corporation, where he performed stress analysis, structural dynamic analysis, 'and flight mechanics for various military applications. Earlier, as Research Engineer for the Boeing Company, he performed flight mechanics, performance, and aerothermodynamic analysis for the Minuteman Missile.
University of Washington - M.S. in Aeronautics and Astronautics Purdue University - B.S. in Aeronautical Engineering Vincennes University - A.S. in Engineering Professional Engineer - Massachusetts and Pennsylvania
3.
S. M. Feldman cont.
American Society of Mechanical Engineers - Member Dynamic Qualification Test Procedure for BWR Valves, ASME Paper 82-PVP-33.
Special Considerations for Dynamic Qualification of BWR Power Plant Equipment.
1985 Pressure Vessels and Piping Conference Proceedings PVP-Volume 98-6.
Review of Valve Operator Fragility Results, Workshop on Seismic and Dynamic Fragility of Nuclear Power Plant Equipment, NUREG-CP-0070 p. 123.
KUO, HSIN-HSIU EDUCATION March 1993 PRINCIPAL ENGINEERING MECHANICS ENGINEER CIVIL/STRUCTURAL DIVISION Taiwan Cheng-Kung University - Bachelor of Science, Civil Engineering - 1965 South Dakota School of Mines and Technology-Master of Science, Civil Engineering-1969 Northwestern University - Ph.D. in Applied Mechanics - 1973 Union College, Schenectady, New York-Courses in Fracture Mechanics and Its Application to Engineering Design ASME Section Ill - Course in Component Support American Welding Society - Course in Fitness-for-Service of Welded Structures University of Kansas - Course in Fracture and Fatigue Control in Structures EPRI SQUG Seismic Capability Engineering Training - August 1992 EPRI SQUG Add-on Training for Seismic Margin Assessment - Nov 1992 LICENSES AND REGISTRATIONS Professional Engineer - Massachusetts (1976)
EXPERIENCE
SUMMARY
Dr. Kuo has 27 years of experience in the engineering industry. Currently, he is assigned to division staff, involved in A-46 SQUG seismic qualification (including walkdown, LAR qualification, and outlier resolution) for PSE&G, and equipment and pipe support qualification for a PECo project. Previously, he was assigned to Savannah River Special Projects Office, involved in plant system evaluation and seismic qualifications of structures, system and components in support of the Department of Energy (DOE) oversight of the site operating Contractor. In this capacity he reviewed contractor technical documents and performed independent seismic analyses of variou~ safety-related structures and equipment. He is knowledgeable in A-46 SQUG seismic qualification procedures and seismic margin assessment (SMA) procedures and the application of various industry codes such as ASME Ill, IEEE-344, ASCE 4-86, ACI 318, etc.
Since joining Stone & Webster Engineering Corporation in 1973, he has been appointed Engineer in the Mechanical Analysis Section of the Power Division. He transferred with his Section to the Engineering Mechanics Division in August 1975 and to the Civil/Structural Division in January 1990. He was engaged in evaulation of pipe rupture, pipe impact, pipe restraint, support structure, and static and dynamic analyses for both PWR and BWR nuclear projects. In April 1979, he transferred to the Engineering Mechanics Division at the Cherry Hill Operations Center. His work assignments have included providing consultation in pipe A0000581.C01
.HHK rupture and dynamic analysis and performing plastic buckling analysis, snap-through buckling analysis of fueling pool liner, and fracture mechanics analysis for various commercial nuclear projects. Also included are assignments in pipe break analysis, moment restraint design, jet impingement analysis and jet shield design, missile probability calculations and *protection evaluations, tank nozzle and restriction orifice and ligh~ing feature seismic qualification.
Prior to joining Stone & Webster Engineering Corporation, Dr. Kuo was a Postdoctoral Research Associate in the School of Aeronautics, Astronautics, and Engineering Science of Purdue University working on wave and composite material.
PROFESSIONAL AFFILIATIONS Sigma Xi - Associate Member American Concrete Institute - Member American Society of Mechanical Engineers - Member PUBLICATIONS High-Quality High-Strength Concrete-Part I, Its Significant Attributes and Mix-Design Methods. ACl-SP-26, p 1100. 1970.
High-Strength Concrete-Part II, Its Applications to Design of Bridge Members and Piles. ACl-SP-26, p 1145. 1970.
Elastic Fields and Strain Energy of a Circular Wedge Disclination. Journal of Applied Physics, Vol 43, p 1454. 1972.
Circular Disclination and Interface Effects. Journal of Applied Physics, Vol 43, p 3936.
1972.
Moving Circular Twist Disclinations in Homogenous and Two-Phase Materials. International Journal of Engineering Science, Vol 11, p 193. 1973.
Circular Twist Disclination in Viscoelastic Material, Journal of Applied Physics, Vol 44, p 3586. 1973.
Correlation of Energy Balance Method to Dynamic Pipe Rupture Analysis, 7th SMIRT Conference Proceedings, August 1983, Chicago, IL (Coauthor - M. Durkee) Paper No. F5/3, Vol F, pp 199 - 206.
Stress Analysis of a Y-Shaped Reducing Pipe Fitting, ASME PVP Conference Proceedings, Vol 214, pp 53-60, June 1991 (Coauthor - B. Gutierrez of DOE SRS office).
A0000581.C01
SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION ATTACHMENT D PEER REVIEW REPORT (6 Pages)
Programmatic Solutions 24 Woodbine Avenue, Suite 12 Northport, NY 11768 Phone: 516 261 5536 Fax: 516 261 5732 May 19, 1995 Mr. Gary Luh Public Service Electric & Gas Company End of Buttonwood Road Mail Code N-27 Hancocks Bridge, NJ 08038 016-94-002-L
SUBJECT:
Third Party Audit Report of USI A46 - Salem Generating Station
Dear Mr. Luh:
This letter report summarizes the activities performed and the conclusions drawn from the Third Party Audit of the USI A-46 Implementation Program for Salem Units 1&2.
1.0 Scope of Third Party Audit The scope of the third party audit covers all USI A-46 topics that relate to the capacity of the equipment reviewed and the seismic demand that applies to these items.
Specifically, the following activities were reviewed as a part of this third party audit.
1.1 The Salem Seismic Design Bases The scope of the third party audit covers all USI*A-46 topics that relate to the capacity of the equipment reviewed and the seismic demand that applies to these items.
Specifically, the following activities were reviewed as a part of this third party audit.
1.1 The Salem Seismic Design Bases Site Seismicity Seismic Input to Structures and Equipment Seismic Design of Mechanical and Electrical Equipment Seismic Design of Tanks Seismic Spatial Interaction Issues Damping
Mr. GaryLuh May 19, 1995 Page2 1.2 The USI A-46 Evaluation Development of the SSEL's Relay Screening The overall approach used The screening criteria used The qualifications of the Seismic Review Team Screening walkdown implementation Results of the screening walkdown Outlier resolution Design enhancements 1.3 Control of the Work Procedures Documentation of work Interface of the seismic activities with the systems activities 1.4 Conclusions and Results Reasonableness of results Appropriateness of recommended resolutions 1.5 Structures, Systems, and Components Included in the Third Party Audit Electrical and mechanical equipment included on the SSEL Tanks and heat exchangers included on the SSEL Items which may have potential spatial interaction with SSEL items 2.0 Summary of Third Party Audit Activities The following summarizes the activities performed for the third party audit of USI A-46 activities for Salem Units 1 & 2.
Mr. GaryLuh May 19, 1995 Page 3 2.1 Review of Project Instructions The Project Instructions (References 1, 2, and 3) provide the methods to be used for (1) developing the SSEL, (2) performing the relay review, and (3) performing the seismic screening. A third party audit of these instructions was performed and comments were forwarded to PSE&G (References 4, 5, and 6).
2.2 Third Party Audit Walkdown of Salem Generating Station On March 23 and 24, 1994 a third party audit walkthrough of the plant was performed by Paul Smith and Harry Johnson. An additional walkthrough was performed by Mr. Johnson on November 14, 1994. The objectives of the walkthrough were the folloWing:
Gain a familiarity with the typical design and installation of equipment used at Salem.
Review the seismic interaction potential at Salem, Units 1 & 2 (particularly focusing on housekeeping issues).
Observe the SRT walkdown activities Review at least one of each of the equipment classes on the SSEL The conclusion from the third party walkthrough at Salem Units 1 & 2 is that, in general, Salem Units 1 & 2 are well designed for seismic loads and equipment and installation appears to be quite rugged.
2.3 Third Party Audit of the Methods Used The third party audit of the methods was based on review of the project instructions, on insights obtained during the third party audit walkdown of Salem Units 1
& 2, and on review of draft final reports (References 7, 8, and 9).
Observations regarding the methods used were provided in References 4, 5, 6, and
- 10. The observations regarding the method were related to: (1) method used for outlier resolution and (2) need for additional clarification of the method used for certain aspects of the evaluation.
Mr. GaryLuh May 19, 1995 Page4 2.4 Third Party Audit of Sample Documentation During the site visit and a visit to VECTRA's Boston office on April 13 & 14 by Paul Smith and Harry Johnson, a sample of the SEWS forms being filled out by the SRTwere reviewed to determine if the documentation being developed was appropriate.
The documentation ofwalkdown and results provided in the project report (References 7, 8, and 9) was reviewed. This documentation includes the following items:
Summary of Salem Units 1 & 2 seismic design basis Example SEWS forms Seismic Verification Data Sheets (SVDS)
Salem Unit 1 & 2 Safe Shutdown Equipment List Relay Evaluation Walkdown Resumes Walkdown Comments by SRT Summary of Outlier Recommendations Photographs Taken During the Walkdown 2.5 Third Party Audit of Results The results of the Salem Unit 1 & 2 USI A-46 Implementation are provided in the project reports (References 7, 8, and 9). A third party review of the seismic evaluation report was performed on the conceptual report of January 16, 1995 and the draft report of April 20, 1995. A third party review of the relay evaluation was performed on the draft report of January 19, 1995. A third party review of the safe shutdown evaluation was performed on the draft Safe Shutdown Report of November 28, 1994 and on Unit 1 & 2 SSEL reports of December 14, 1994.
3.0 Results of Third Party Audit 3.1 Methods Used The method used for Salem Unit 1 & 2 conforms with the SQUG GIP method.
This method has been accepted by the NRC as described in SSER Revision 2.
Mr. Gary Luh May 19, 1995 Page 5 3.2 Implementation of Program The Salem Unit 1 & 2 USI A-46 implementation program has been correctly implemented and documented.
3.3 Reasonableness of Results Based on the third party audit walkthrough and review of the methods used for the Salem Unit 1 & 2 USI A-46 implementation, the results appear to be reasonable and consistent with those anticipated.
3.4 Recommended Actions The recommended actions resulting from USI A-46 are documented in the project reports in Section 4.0 of the Seismic Evaluation Report and in Attachments L & M of the Relay Evaluation Report. These recommended actions are reasonable and consistent with those anticipated.
4.0 Conclusions The methods used for the Salem Unit 1 & 2 USI A-46 Implementation are appropriate, the methods have been correctly implemented, and the results and the recommended actions appear to be reasonable and consistent with those anticipated.
5.0 References
- 1. "Identification of Safe Shutdown Paths, Equipment and Preparation of Safe Shutdown Equipment List (SSEL) for Salem Generating Station (Units 1 and 2)", Project Instruction Number 0014-078-POOl, Rev 0.
- 2. "USI A-46 Relay Evaluation for Salem Generating Station Units 1 and 2", Project Instruction Number 0014-078-P002, Rev 0.
- 3. "Verification of Seismic Adequacy of Mechanical and Electrical Equipment at Salem Units 1 & 2, Project Instruction 0014-078-P003, Rev 3.
- 4. Programmatic Solutions Letter 042-93-002-L, 10/27/93, comments on PI 0014-078-POO 1, "Identification of Safe Shutdown Paths, equipment and Preparation of safe Shutdown Equipment List (SSEL) for Salem Generating Station (Units 1 and 2)".
- 5. Programmatic Solutions Letter 042-93-003-L, 11/12/93, comments on PI 0014-078-P002, "USI A-46 Relay Evaluation for Salem Generating Station Units 1 and 2".
Mr. Gary Luh May 19, 1995 Page 6
- 6. Programmatic Solutions Letter 042-94-001-L, 1/3/94, comments on PI 0014-78-P003, "Verification of Seismic Adequacy of Mechanical and Electrical Equipment at Salem Units 1 and 2".
- 7. "Seismic Evaluation Report for Salem Generating Station", Report Number: SGS-SEIS.RPT.
- 8. "Safe Shutdown Paths for Salem Generating Stations Units 1 & 2", Report Number 0014-00078-ROO 1.
- 9. "Relay Evaluation Report for Salem Generating Station Units 1 & 2", Report 0014-00078-12002.
- 10. Programmatic Solutions memo 070-001-M007, dated May 5, 1995.
SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION ATTACHMENT F SVDS SALEM UNIT 1 (23 Pages)
04120195.M Eq.
Eq. ID Rev Cl No 0
1BRE16 0
0 1BRE17 0
0 1BRE18 0
0 1SWE10 0
0 1SWE11 0
0 1SWE12 0
0 1SWE7 0
0 1SWE8 0
0 1SWE9 0
0 1WGE17 0
1 11101 0
1 11102 0
1 11103 0
1 11104 0
1 11105 0
1 11106 0
1 11107 0
1 11108 0
1 11109 0
Certification:
SyslEq. Desc CC I B. A. EVAP. CONDENSER CC I DISTILLATE COOLER CCI VENT CONDENSER SW 114 SW PMP DISCH STRAINER SW 115 SW PMP DISCH STRAINER SW 116 SW PMP DISCH STRAINER SW 111 SW PMP DISCH STRAINER SW 112 SW PMP DISCH STRAINER SW 113 SW PMP DISCH STRAINER CC I WASTE EVAP VENT GAS CLR EP I NO 1A SERV WTR INTAKE 230V VITAL CONTROL CENTER EP I NO 1 B2 SERV WTR INTAKE 230V VITAL CONTROL CENTER EP I NO 1C SERVWTR INTAKE 230VVITAL CONTROL CENTER EP I NO 1A DIESEL GENERATOR 230V VITAL CONTROL CENTER EP I NO 18 DIESEL GENERATOR 230V VITAL CONTROL CENTER EP I NO 1C DIESEL GENERATOR 230V VITAL CONTROL CENTER EP/NO 1A EAST VALVES & MISC. 230V VITAL CONTROL CENTER EP I NO 1C EAST VALVES & MISC. 230V VITAL CONTROL CENTER EP I NO 1 B WEST VALVES & MISC. 230V VITAL CONTROL CENTER SALEM NUCLEAR G.
- NG STATION - UNIT 1 SCREENIKG VERIFICATION DATA SHEET (SVDS)
Bldg.
FIEI.
Rm orRwlCI Aux 1 100.00 BAEvap Rm Aux 1 100.00 BAEvapRm Aux 1 100.00 BAEvapRm Yard 100.00 Srvc wtr Bldg Yard 100.00 Srvc wtr Bldg Yard 100.00 Srvc wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Aux 1 100.00 1 Cone Fltr Rm Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Aux 1 100.00 1A DIG Control Area Aux 1 100.00 1 B DIG Control Area Aux 1 100.00 1 C DIG Control Area IPA 1 78.00 A, B, C East Valves IPA 1 78.00 A, B, C East Valves Aux 1 84.00 Elec Contr Center Certification:
Page# 1123 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
100.00 NIA DOC RRS Yes Yes Yes Yes Yes 100.00 NIA DOC RRS Yes Yes Yes Yes Yes 100.00 NIA DOC RRS Yes Yes Yes Yes Yes 100.00 NIA DOC CRS Yes Yes Yes Yes Yes 100.00 NIA DOC CRS Yes Yes Yes Yes Yes 100.00 NIA DOC CRS Yes Yes Yes Yes Yes 100.00 NIA DOC CRS Yes Yes Yes Yes Yes 100.00 NIA DOC CRS Yes Yes Yes Yes Yes 100.00 NIA DOC CRS Yes Yes Yes Yes Yes 100.00 NIA DOC RRS No Yes Yes Yes No 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes No No Yes No 100.00 N/A ABS CRS Yes Yes Yes Yes Yes 78.00 N/A ABS CRS Yes Yes Yes No No 78.00 N/A ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to theJbest of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professional engineer.)
Aziz Saber
~
04/20/95 Print or Type Name Signature Date Steve Anagnostis 04/20/95 Print or Type Name Date Print or Type Name Signature Date Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
-Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date*
I:
Print or Type Name Signature Date
04120195 1.M Eq.
Eq. ID Rev Cl No 1
11110 0
1 11111 0
1 11112 0
1 11126 0
1 11131 0
1 11132 0
1 11133 0
1 11136 0
1 11137 0
2 1SWGR1CX 0
2 1SWGR1CY 0
3 1SWGR1CD 0
4 1XFR1C4DA 0
x 4
1XFR1C4DB 0
y 6
1SWE1 0
6 1SWE2 0
6 1SWE3 0
Certification:
SyslEq. Desc EP I NO 1C WEST VALVES & MISC. 230V VITAL CONTROL CENTER EP I NO 1A AIR COND 230V VITAL CONTROL CENTER EP I NO 1 BAIR COND 230V VITAL CONTROL CENTER EP I NO 1 B1 SERV WfR INTAKE 230V VITAL CONTROL CENTER EP I NO 1A VENTILATION 230V VITAL CONTROL CENTER EP I NO 1B VENTILATION 230VVITAL CONTROL CENTER EP I NO 1C VENTILATION 230VVITAL CONTROL CENTER EP I NO 1A WEST VALVES & MISC. 230V VITAL CONTROL CENTER EP I NO 1B EAST VALVES & MISC. 230V VITAL CONTROL CENTER EP I NO 1 C 460V VITAL BUS EP I NO 1 C 230V VITAL BUS EP I NO 1C 4160VVITAL BUS EP I TRANSFORMER TO NO. 1 B 460V VITAL BUS 1SWGR1CX EP I TRANSFORMER TO NO. 1C 230V VITAL BUS 1SWGR1CY SW 111 SERVICE WATER PUMP SW 112 SERVICE WATER PUMP SW 113 SERVICE WATER PUMP SALEM NUCLEAR GE **
NG STATION - UNIT 1 SCREENIN'G VERIFICATI DATA SHEET (SVDS)
Bldg.
Fl El.
RmorRwlCI Aux 1 84.00 12 Aux Fd Pmp Rm Aux 1 122.00 CRNCRm Aux 1 122.00 Aux Bldg Sup Vent Yard 100.00 Srvc Wtr Bldg IPA 1 100.00 CH Wtr Pmp Area IPA 1 100.00 CH Wtr Pmp Area IPA 1 100.00 CH Wtr Pmp Area Aux 1 84.00 Cor at Aux Fd Pmp Ar IPA 1 78.00 A, B, C East Valves Aux 1 84.00 4601230V Vital 12512 Aux 1 84.00 4601230V Vital 12512 Aux 1 64.00 4 KV Vital Bus & Bat Aux 1 84.00 4601230V Vital 12512 Aux 1 84.00 4601230V Vital 12512 Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Certification:
Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
84.00 NIA ABS CRS Yes Yes Yes Yes Yes 122.00 NIA ABS CRS Yes Yes Yes Yes Yes 122.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes No No 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes No No Yes No 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 78.00 NIA ABS CRS Yes Yes Yes No No 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 64.00 NIA ABS CRS Yes Yes Yes No No 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes No No All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and *belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRn are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professional engineer.)
Aziz Saber AeaLA-04120195 Print or Type Name Signature Date Steve Anagnostis 04120195 Print or Type Name Date Print or Type Name Signature Date Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
, Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04120195 1 **
111 Eq.
Eq. ID Rev Cl No 6
1SWE4 0
6 1SWE5 0
6 1SWE6 0
7 11GB4 0
7 11SW24 0
7 12GB4 0
7 12SW24 0
7 13GB4 0
7 13SW24 0
7 14GB4 0
7 14SW24 0
7 15SW24 0
7 16SW24 0
7 1SW308 0
8 11SW20 0
8 13SW20 0
8 1CV40 0
8 1CV41 0
8 1CV68 0
8 1CV69 0
8 1SW26 0
9 1VHE64 0
9 1VHE65 0
10 1CAA15-0 DMOP 10 1CAA16-0 DMOP Certification:
SyslEq. Desc SWl14SWPMP SWl15SWPMP SWl16SWPMP GB 111 SIG SLOWDOWN ISO VLV SW I SW STR BID CONT V GB 112 SIG SLOWDOWN ISO VLV SW I SW STR BID CONT V GB 113 SIG BLODOWN ISO VLV SW I SW STR BID CONT V GB 114 SIG SLOWDOWN ISO VLV SW I SW STR BID CONT V SW I SW STR BID CONT V SW I SW STR B/D CONT V SW I RECIRC CONTROL V PNL740-1GG SW I TG HOR SUP MOV SW I TG HOR SUP MOV CV I VCT OUTLET STOP MOV CV I VCT OUTLET STOP MOV CV I CHG HOR STOP MOV CV I CHG HOR STOP MOV SW I TG HOR INLET MOV VH 111 EMERG A/C SUP FAN VH 112 EMERG A/C SUP FAN VH 11 CONTRL AREA VENT EMER AIR COND SUP FAN 11 OUTLET DMOP VH 11 CONTRL AREA VENT EMER AIR COND SUP FAN 12 OUTLET DMOP SALEM NUCLEAR GE **
ollG STATION* UNIT 1 SCREENING VERIFICATION DATA SHEET (SVDS)
Bldg.
FIEI.
Rm orRwlCI Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg IPA 1 78.00 Mech Pen Area SG BO Yard 100.00 Srvc Wtr Bldg IPA 1 78.00 Mech Pen Area SG BO Yard 100.00 Srvc Wtr Bldg IPA1 78.00 Mech Pen Area SG BO Yard 100.00 Srvc Wtr Bldg IPA 1 78.00 Mech Pen Area SG BO Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc wtr Bldg Yard 100.00 Srvc Wtr Bldg Aux 1 100.00 Rm By BA XF Pmps Aux 1 100.00 Rm By BA XF Pmps IPA1 78.00 Mech Pen Area SG BO IPA 1 78.00 Mech Pen Area SG BO Yard 100.00 Srvc Wtr Bldg Aux 1 122.00 CRA/CRm Aux 1 122.00 CRAJCRm Aux 1 122.00 CRA/CRm Aux 1 122.00 CRA/CRm Certification:
Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 78.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 NIA ABS CRS Yes Yes NIA Yes Yes 78.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 NIA ABS CRS Yes Yes NIA Yes Yes 78.00 Yes BS GRS Yes Yes NIA Yes Yes NIA ABS CRS Yes Yes NIA Yes Yes 78.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 NIA ABS CRS Yes Yes NIA Yes Yes 100.00 NIA ABS CRS Yes Yes NIA Yes Yes 100.00 NIA ABS CRS Yes Yes NIA Yes Yes 100.00 NIA ABS CRS Yes Yes NIA Yes Yes 100.00 NIA ABS CRS Yes Yes NIA Yes Yes 100.00 NIA ABS RRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 78.00 Yes BS GRS Yes Yes NIA Yes Yes 78.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 NIA ABS CRS Yes Yes NIA Yes Yes 140.00 Yes BS GRS Yes Yes Yes Yes Yes 140.00 Yes BS GRS Yes Yes Yes Yes Yes 140.00 Yes
- BS GRS Yes Yes Yes Yes Yes 140.00 Yes BS GRS Yes Yes Yes Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
04120195 Date Steve Anagnostis Print or Type Name Print or Type Name Signature Date Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
-Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04/20/95 1.111 Eq.
Eq. ID Rev Cl No 10 1CAA17-0 DMOP 14 1AADC 0
14 1BBDC 0
14 1BDE 0
14 1CCDC 0
14 1DDE 0
14 1SWGR1ADE 0
14 1SWGR1BDE 0
18 401-1 0
20 103-1 0
20 131-1 0
20 132-1 0
20 1CC1 0
20 1CC2 0
20 1CC3 0
20 1PNL11828 0
20 1PNL11829 0
20 1PNL11830 0
20 1PNL11831 0
Certification:
Sys/Eq. Desc VH / 1 CONTRL AREA VENT EMER AIR FL TR INTK DMOP EP / 125VDC DISTRIBUTION CABINET EP / 125VDC DISTRIBUTION CABINET EP I NO 1 B 28VDC CONTROL BUS EP / 125VDC DISTRIBUTION CABINET EP I NO 10 28VDC CONTROL BUS EP I NO 1A 28VDC BUS EP I NO 1 B 28VDC BUS CC/ 1 CC SURGE TNK LVL INST PNL EP / 1 RAD WASTE LQUID AUX SUPM TNK LVL PANEL EP / 1 REACTOR PROT SOLID STATE PROT TRAIN A OUTPUT TEST PANEL 131 EP / 1 REACTOR PROT SOLID STATE PROT OUTPUT TEST CAB NO. 132
/ 1 REACTOR PROT CONTROL ROOM CONSOLE PANEL
/ 1 REACTOR PROT CONTROL ROOM CONSOLE PANEL
/ 1 MN STM & TRB BYPASS CONTROL ROOM CONSOLE PANEL EP / 1A D/G GENERATOR CONTROL PANEL EP / 1A D/G ENGINE CONTROL PANEL EP / 1B D/G GENERATOR CONTROL PANEL EP / 1 B D/G ENGINE CONTROL PANEL SALEM NUCLEAR GE*~{; STATION - UNIT 1 SCREENING VERIFICATION DATA SHEET (SVDS)
Bldg.
FIEI.
Rm orRw/CI Aux 1 122.00 CRA/C Rm Aux 1 100.00 1 RELAY RM Aux 1 100.00 1 RELAY RM Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 RELAY RM Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 122.00 1 CC Surge Tnk Area Aux 1 122.00 1 Control Rm Aux 1 122.00 1 Control Rm Aux 1 122.00 1 Control Rm Aux 1 122.00 1 Control Rm Aux 1 122.00 1 Control Rm Aux 1 122.00 1 Control Rm Aux 1 100.00 1A D/G Control Rm Aux 1 100.00 1A DIG Control Rm Aux 1 100.00 1 B D/G Control Rm Aux 1 100.00 1 B D/G Control Rm Certification:
.Page#4/23 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
140.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 N/A ABS CRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 N/A ABS CRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes No Yes No No 122.00 Yes BS GRS Yes No Yes No No 122.00 Yes BS GRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes No Yes No No 100.00 Yes BS GRS Yes No Yes No No 100.00 Yes BS GRS Yes No Yes No No 100.00 Yes BS GRS Yes No Yes No No All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professional engineer.)
Aziz Saber k%.ai'4'A--
04/20/95 Print or Type Name Signature Date Steve Anagnostis 04/20/95 Print or Type Name Date Print or Type Name Signature Date Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
- Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04/20/951 *.
- I SALEM NUCLEAR GE *.*
G STATION - UNIT 1 SCREENIN~ VERIFICATION DATA SHEET (SVDS) t>age # 5/23 Eq.
Eq. ID Rev Sys/Eq. Desc Bldg.
Fl El.
Cl No 20 1PNL11832 0
EP / 1C D/G GENERATOR CONTROL Aux 1 100.00 PANEL 20 1PNL11833 0
EP / 1 C D/G ENGINE CONTROL PANEL Aux 1 100.00 20 1PNL11834 0
EP / 1A D/G 230V CONTORL CENTER AUX Aux 1 100.00 PANEL 20 1PNL 11835 0
EP / 1 B D/G 230V CONTORL CENTER AUX Aux 1 100.00 PANEL 20 1PNL11836 0
EP / 1 C D/G 230V CONTORL CENTER AUX Aux 1 100.00 PANEL 20 1RP1 0
EP / 1 REACTOR PROT CONTROL ROOM Aux 1 122.00 RECORDER PANEL 20 1RP2 0
EP / 1 AUX BLDG VENT CONT RM Aux 1 122.00 RECORDER PNL 20 1TRCC 0
EP / 1 CABINET RELAY ROOM TERMINAL Aux 1 100.00 RACK1TRCC 20 1TRDD 0
EP / 11-14 MN STM & TRB BY PASS STY V Aux 1 100.00 HYO PMP OVRD RL Y TERM RACK 20 205-1 0
EP / 11 AUX FEEDWATER PANEL 205 Aux 1 84.00 20 206-1 0
EP / 12 AUX FEEDWATER PANEL 206 Aux 1 84.00 20 207-1 0 AF/ 13AUX FEEDWATER PANEL Aux 1 84.00 20 32-1 0
EP / 1 REACT PROT SOLID STATE PROT Aux 1 122.00 INTERFACE CAB NO. 32 20 37-1 0
EP / 1 REACT PROT SOLID STATE PROT Aux 1 122.00 TRAIN B OUTPUT CAB NO. 37 20 378-1 0 SJ / 1 SAFETY INJ RWST 230V AC, 1 KW Yard 100.00 PANEL 20 379-1 0
SJ / 1 SAFETY INJ RWST 230V AC, 1 KW Yard 100.00 PANEL Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Rm orRw/CI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
1 C D/G Control Rm 100.00 Yes BS GRS Yes No Yes No No 1 C D/G Control Rm 100.00 Yes BS GRS Yes No Yes No No 1A D/G Control Bldg 100.00 Yes BS GRS Yes Yes Yes Yes Yes 1 B D/G Control Bldg 100.00 Yes BS GRS Yes Yes Yes Yes Yes 1 C D/G Control Bldg 100.00 Yes BS GRS Yes Yes Yes Yes Yes 1 Control Rm 122.00 Yes BS GRS Yes Yes Yes Yes Yes 1 West Elevator 122.00 Yes BS GRS Yes Yes Yes Yes Yes 1 Relay Rm 100.00 N/A ABS CRS Yes Yes Yes Yes Yes 1 Relay Rm 100.00 N/A ABS CRS Yes Yes Yes Yes Yes 12 Aux Fd Pmp Rm 84.00 N/A ABS CRS Yes No Yes No No 12 Aux Fd Pmp Rm 84.00 N/A ABS CRS Yes No Yes No No 12 Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 1 Control Rm 122.00 Yes BS GRS Yes No Yes No No 1 Control Rm 122.00 Yes BS GRS Yes Yes Yes Yes Yes Fire Pmp/Fresh Water 100.00 N/A ABS CRS Yes Yes Yes Yes Yes 1 RWSTArea 100.00 N/A ABS CRS Yes Yes Yes Yes Yes Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the
-Engineers deem it neces~ary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Aziz Saber 04/20/95 Print or Type Name Date Print or Type Name Signature Date Steve Anagnostis 04/20/95 Print or Type Name Date Print or Type Name Signature Date*
Print or Type Name Signature Date Print or Type Name Signature Date
04/20/95 1.M Eq.
Eq. ID Rev Cl No 20 38-1 0
20 58-1 0
20 59-1 0
20 SEC-1A 0
20 SEC-1B 0
20 SEC-1C 0
Certification:
Sys/Eq. Desc EP / 1 REACT PROT SOLID STATE PROT TRAIN B INTERFACE CAB NO. 38 EP / 1 CABINET AUX RELAY RACK EP / 1 CABINET AUX RELAY RACK EP I SAFEGUARDS EMERGENCY CABINET
-1A EP I SAFEGUARDS EMERGENCY CABINET
-1B EP I SAFEGUARDS EMERGENCY CABINET
-1C SALEM NUCLEAR GEN.NG STATION - UNIT 1 SCREENIN~ VERIFICATION DATA SHEET (SVDS)
Bldg.
FIEI.
Rm orRw/CI Aux 1 122.00 1 Control Rm Aux 1 122.00 1 Control Rm Aux 1 122.00 1 Control Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Certification:
Base El.
122.00 122.00 122.00 100.00 100.00 100.00 Page#6/23
<40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
Yes BS GRS Yes Yes Yes Yes Yes Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professional engineer.)
k$Q.f~
Aziz Saber 04/20/95 Print or Type Name Signature Date Steve Anagnostis 04/20/95 Print or Type Name Date Print or Type Name Signature Date Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
- Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04/20/95 1 **
111 SALEM NUCLEAR GE.NG STATION* UNIT 1 SCREENING VERIFICAT DATA SHEET (SVDS)
Page#7/23 Eq.
Eq. ID Rev Sys/Eq. Desc Bldg.
FIEI.
Cl No 0
1DAE14 0
DA I EXHAUST SILENCER - 1A DIESEL Aux 1 122.00 0
1DAE15 0
DA I EXPANSION TANK - 1A DIESEL Aux 1 122.00 0
1DAE24 0
DA I EXHAUST SILENCER - 1 B DIESEL Aux 1 122.00 0
1DAE33 0
DA I EXPANSION TANK - 1 B DIESEL Aux 1 122.00 0
1DAE47 0
DA I EXHAUST SILENCER - 1 C DIESEL Aux 1 122.00 0
1DAE48 0
DA I EXPANSION TANK - 1 C DIESEL Aux 1 122.00 0
1DFE3 0
DF I NO. 1A DIESEL FUEL OIL DAY TANK Aux 1 122.00 0
1DFE4 0
OF I NO. 1B DIESEL FUEL OIL DAY TANK Aux 1 122.00 0
1DFE5 0
OF I NO. 1C DIESEL FUEL OIL DAY TANK Aux 1 122.00 0
1WGE14 0 CC I WASTE EVAP CONDENSER Aux 1 100.00 0
1WGE22 0
CC I WASTE EVAP SUB CLR Aux 1 100.00 5
1CHE17 0 SW/ 11 CH CNDSR RECIRC PUMP IPA 1 100.00 5
1CHE18 0 SW/ 12 CH CNDSR RECIRC PUMP IPA 1 100.00 5
1CHE19 0 SW/ 13 CH CNDSR RECIRC PUMP IPA 1 100.00 5
1CHE5 0 CH/ 11 CH WTR PMP IPA 1 100.00 5
1CHE6 0 CH/ 12 CH WTR PMP IPA 1 100.00 7
11MS10 0
MS I MS PWR RELIEF V IPA 1 100.00 7
11MS11 0
MS I MS SAFETY VLV IPA 1 100.00 7
11MS12 0
MS I MS SAFETY VLV IPA 1 100.00 7
. 11MS13 0
MS I MS SAFETY VLV IPA 1 100.00 7
11MS14 0
MS I MS SAFETY VLV IPA 1 100.00 7
11MS15 0
MS I MS SAFETY VLV IPA 1 100.00 7
11MS167 0 MS/MS ISOL V IPA 1 100.00 7
11MS169 0
MS I MS INLET V 3-WAY MOV AIR OPRD IPA 1 100.00 STM ASSIST VLV 7
11MS171 0
MS I MS INLET V 3-WAY MOV AIR OPRD IPA 1 100.00 STM ASSIST VLV Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRn are required; there should be at least two on the SRT. All signatories should agree with all the-entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude
~ /??. ;QJ.... -../~~ I 04/20/95 Print or Type Name 7 Signature Date Steve Anagnostis 04/20/95 Print or Type Name Date Print or Type Name Signature Date Rm orRw/CI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
1AD/G Rm 122.00 N/A DOC RRS Yes Yes Yes Yes Yes 1A D/G Rm 122.00 N/A DOC RRS Yes Yes Yes Yes Yes 12 D/G Exh Fan Rm/1B 122.00 N/A DOC RRS Yes Yes Yes Yes Yes 1B D/G Rm 122.00 N/A DOC RRS Yes Yes Yes Yes Yes 13 D/G Exhst Fan Rm/
122.00 N/A DOC RRS Yes Yes Yes Yes Yes 13 D/G Exhst Fan Rm/
122.00 NIA DOC RRS Yes Yes Yes Yes Yes 1AD/G Rm 122.00 N/A DOC RRS Yes Yes Yes Yes Yes 1B D/G Rm 122.00 N/A DOC RRS Yes Yes Yes Yes Yes 13 D/G Exhst Fan Rm/
122.00 NIA DOC RRS Yes Yes Yes Yes Yes Waste Evap Rm 100.00 NIA DOC RRS Yes Yes Yes Yes Yes Waste Evap Rm 100.00 N/A DOC RRS Yes Yes Yes Yes Yes CH Wtr Pmp Area 100.00 Yes BS GRS Yes Yes Yes Yes Yes CH Wtr Pmp Area 100.00 Yes BS GRS Yes Yes Yes Yes Yes CH Wtr Pmp Area 100.00 Yes BS GRS Yes Yes Yes Yes Yes CH Wtr Pmp Area 100.00 Yes BS GRS Yes Yes Yes Yes Yes CH Wtr Pmp Area 100.00 Yes BS GRS Yes Yes Yes Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes NIA Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 NIA DOC RRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04/20/95 1.1v1 SALEM NUCLEAR GE **
r.IG STATION - UNIT 1 SCREENIN(; VERIFICATION DATA SHEET (SVCS)
Page#B/23 Eq.
Eq. ID Rev Sys/Eq. Desc Bldg.
Fl El.
Cl No 7
11SW92 0 SW I CH CNDSR SW CONT V IPA 1 100.00 7
11SW93 0 SW/ 11 CH CNDSR SW RECIRC V IPA 1 100.00 7
12MS10 0
MS I MS PWR RELIEF V CPA 1 100.00 7
12MS11 0
MS I MS SAFETY VLV CPA 1 100.00 7
12MS12 0
MS I MS SAFETY VLV CPA 1 100.00 7
12MS13 0 MS I MS SAFETY VLV CPA 1 100.00 7
12MS14 0
MS I MS SAFETY VLV CPA 1 100.00 7
12MS15 0
MS I MS SAFETY VLV CPA 1 100.00 7
12MS167 0 MS/MS ISOLV CPA 1 100.00 7
12MS169 0
MS I MS INLET V 3-WAY MOV AIR OPRD IPA 1 100.00 STM ASSIST VLV 7
12MS171 0
MS I MS INLET V 3-WAY MOV AIR OPRD IPA 1 100.00 STM ASSIST VLV 7
12SW92 0 SW I CH CNDSR SW CONT V IPA 1 100.00 7
12SW93 0 SW/ 12 CH CNDSR SW RECIRC V IPA 1 100.00 7
13MS10 0
MS I MS PWR RELIEF V IPA 1 100.00 7
13MS11 0
MS I MS SAFETY VLV IPA 1 100.00 7
13MS12 0
MS I MS SAFETY VLV IPA 1 100.00 7
13MS13 0 MS I MS SAFETY VLV IPA 1 100.00 7
13MS14 0 MS I MS SAFETY VLV IPA 1 100.00 7
13MS15 0 MS I MS SAFETY VLV IPA 1 100.00 7
13MS167 0 MS/MS ISOLV IPA 1 100.00 7
13MS169 0
MS I MS INLET V 3-WAY MOV AIR OPRD IPA 1 100.00 STM ASSISTVLV 7
13MS171 0
MS I MS INLET V 3-WAY MOV AIR OPRD IPA 1 100.00 STM ASSIST VLV 7
13SW92 0
SW I CH CNDSR SW CONT V IPA 1 100.00 Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Rm orRw/CI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
CH Wtr Pmp Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes CH Wtr Pmp Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes NIA Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes NIA Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 NIA DOC RRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes CH Wtr Pmp Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes CH Wtr Pmp Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes NIA Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes MS Pen Area 100.00 N/A DOC RRS Yes Yes N/A Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes NIA Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes CH Wtr Pmp Area 100.00 Yes BS GRS Yes Yes N/A Yes Yes Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment con~ained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer Is required If the Seismic Capability are required; there should be at least two on the SRT. All signatorie.s should agree with all the
-Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude I C. h1. A.-.vL.,ua 04/20/95 Print or Type Name I
Signature Date Print or Type Name Signature
~~h6=
Date Steve Anagnostis 04/20/95 Print or Type Name 7
~aTe Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
041201951 *
.it Eq.
Eq. ID Rev Cl No 7
14MS10 0
7 14MS11 0
7 14MS12 0
7 14MS13 0
7 14MS14 0
7 14MS15 0
7 14MS167 0
7 14MS169 0
7 14MS171 0
7 1CH168 0
9 1VHE25 0
9 1VHE26 0
9 1VHE27 0
9 1VHE28 0
9 1VHE29 0
9 1VHE30 0
10 1VHE315 0
10 1VHE838 0
11 1CHE7 0
11 1CHEB 0
11 1CHE9 0
12 1CAE5 0
17 1DAE23 0
Certification:
SyslEq. Desc MS I MS PWR RELIEF V MS I MS SAFETY VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS/MS ISOLV MS I MS INLET V 3-WAY MOV AIR OPRD STM ASSIST VLV MS I MS INLET V 3-WAY MOV AIR OPRD STMASSISTVLV CH I EMER A/C COIL RET CONT V VH / 11 D/G AREA EXH FAN VH / 12 DIG AREA EXH FAN VH / 13 DIG AREA EXH FAN VH / 11 DIESEL CONTROL AREA EXH FAN VH / 12 DIESEL CONTROL AREA EXH FAN VH / 13 DIESEL CONTROL AREA EXH FAN VH / 1 CONTRL AREA VENT EMER AIR FL TR COOLING COIL VH / 1 CONTRL AREA VENT SWGR RM SUP FAN FILTER ENCLOSURE CH 111 CHILLER CH 112 CHILLER CH / 13 CHILLER CH / 1 ECAC LP & HP CYL COOLING EP I NO. 1B DIESEL GENERATOR SALEM NUCLEAR GE-~;G STATION - UNIT 1 SCREENING VERIFIC~ATA SHEET (SVDS)
Bldg.
FIEI.
Rm orRwlCI OPA 1 100.00 MS Pen Area OPA 1 100.00 MS Pen Area OPA 1 100.00 MS Pen Area OPA 1 100.00 MS Pen Area OPA 1 100.00 MS Pen Area OPA 1 100.00 MS Pen Area OPA 1 100.00 MS Pen Area IPA 1 100.00 MS Pen Area IPA 1 100.00 MS Pen Area Aux 1 122.00 CRA/CRm Aux 1 122.00 11 DIG Exh Fn Rm/1A Aux 1 122.00 12 D/G Exh Fan Rml1B Aux 1 122.00 13 D/G Exh Fan Rm/1C Aux 1 122.00 11 D/G Exh Fn Rml1A Aux 1 122.00 12 D/G Exh Fan Rml1B Aux 1 122.00 13 DIG Exh Fan Rml1C Aux 1 122.00 CRA/CRm IPA 1 100.00 CH Wtr Pmp Area IPA 1 100.00 CH Wtr Pmp Area IPA 1 100.00 CH Wtr Pmp Area IPA 1 100.00 CH Wtr Pmp Area IPA 1 100.00 Ch Wtr Pmp Area Aux 1 100.00 1B D/G Rm Certification:
.r'age#9123 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes N/A Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 NIA DOC RRS Yes Yes N/A Yes Yes 100.00 Yes BS GRS Yes Yes N/A Yes Yes 100.00 Yes BS GRS Yes Yes N/A Yes Yes 122.00 Yes BS GRS Yes Yes NIA Yes Yes 122.00 NIA ABS CRS Yes Yes Yes Yes Yes 122.00 NIA ABS CRS Yes Yes Yes Yes Yes 122.00 NIA ABS CRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes Yes Yes Yes Yes 140.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes No Yes Yes No All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the
-Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude 04120195 Print or Type Name Date Print or Type Name Signature Date Steve Anagnostis 04/20/95 Print or Type Name Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04/20/95 1...
j Eq.
Eq. ID Rev Cl No 17 10AE38 0
17 1DAE4 0
18 684-1A 0
18 684-1B 0
18 684-1C 0
18 684-10 0
18 685-1A 0
18 685-1B 0
18 685-1C 0
18 685-10 0
18 686-1A 0
18 686-1B 0
18 686-1C 0
18 686-10 0
20 1R11 0
Certification:
Sys/Eq. Desc EP I NO. 1C DIESEL GENERATOR EP I NO. 1A DIESEL GENERATOR MS / 11 MN STM & TRB BY PASS STM GEN PRESS CONTRL PNL MS/ 12 MN STM & TRB BY PASS STM GEN PRESS CONTRL PNL MS/ 13 MN STM & TRB BY PASS STM GEN PRESS CONTRL PNL MS/ 14 MN STM & TRB BY PASS STM GEN PRESS CONTRL PNL MS / 11 MN STM & TRB BY PASS STM GEN OUTLET HEAD PRESS CONTRL PNL MS/ 12 MN STM & TRB BY PASS STM GEN OUTLET HEAD PRESS CONTRL PNL MS/ 13 MN STM & TRB BY PASS STM GEN OUTLET HEAD PRESS CONTRL PNL MS/ 14 MN STM & TRB BY PASS STM GEN OUTLET HEAD PRESS CONTRL PNL MS / 11 MN STM & TRB BY PASS STM GEN STM OUTLET HEAD PRESS CONTRL PNL MS/ 12 MN STM & TRB BY PASS STM GEN STM OUTLET HEAD PRESS CONTRL PNL MS / 13 MN STM & TRB BY PASS STM GEN STM OUTLET HEAD PRESS CONTRL PNL MS/ 14 MN STM & TRB BY PASS STM GEN STM OUTLET HEAD PRESS CONTRL PNL EP / 14KV1CDD, 11CSD & 12CSD BKR FAIL PROT RELAY RACK 1R11 PANEL SALEM NUCLEAR GE *
.* G STATION - UNIT 1 SCREENING VERIFICAT DATA SHEET (SVDS)
Bldg.
Fl El.
Rm orRw/CI Aux 1 100.00 1C D/G Rm Aux 1 100.00 1AD/G Rm IPA 1 100.00 MS Pen Area OPA 1 100.00 MS Pen Area IPA 1 100.00 MS Pen Area OPA 1 100.00 MS Pen Area IPA 1 100.00 MS Pen Area OPA 1 100.00 MS Pen Area IPA 1 100.00 MS Pen Area OPA 1 100.00 MS Pen Area IPA 1 100.00 MS Pen Area OPA 1 100.00 MS Pen Area IPA 1 100.00 MS Pen Area OPA 1 100.00 MS Pen Area Aux 1 100.00 1 Relay Rm Certification:
age#10/23 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
100.00 N/A ABS CRS Yes No Yes Yes No 100.00 N/A ABS CRS Yes No Yes Yes No 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the
-Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude e_ hl. tGJ....,Jl...,..,,u.c... I 04/20/95 I
Print or Type Name I Signature Date Print or Type Name Signature Date Steve Anagnostis 04/20/95 Print or Type Name Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04120195 1.M Eq.
Eq. ID Rev Cl No 20 1R24 0
20 1RB 0
20 407-1 0
20 RC11-3 0
20 RC11-4 0
20 RC11-5 0
20 RC11-6 0
20 RC11-7 0
20 RC12-3 0
20 RC12-4 0
20 RC12-5 0
20 RC12-6 0
20 RC12-7 0
20 RC13-3 0
Certification:
SyslEq. Desc EP 11 4KV VITAL BUS 1 BOD, 11 BSD &
12BSD BKR FAIL PROT RELAY RACK EP I 1'4KV 1ADD, 11ASD & 12ASD BKR FAIL PROT RELAY RACK 1RB (PANEL)
VH 11 CONTRL AREA VEN CONT RM AC CONTPNL EP / 11 AUX CONTROL SYSTEM RELAY CABINET RC11-3 EP 111 AUX CONTROL SYSTEM RELAY CABINET RC11-4 EP / 11 AUX CONTROL SYSTEM RELAY CABINET RC11-5 EP 111 AUX CONTROL SYSTEM RELAY CABINET RC11-6 EP 111 AUX CONTROL SYSTEM RELAY CABINET RC11-7 EP / 12 AUX CONTROL SYSTEM RELAY CABINET RC12-3 EP 112 AUX CONTROL SYSTEM RELAY CABINET RC12-4 EP / 12 AUX CONTROL SYSTEM RELAY CABINET RC12-5 EP 112 AUX CONTROL SYSTEM RELAY CABINET RC12-6 EP 112 AUX CONTROL SYSTEM RELAY CABINET RC12-7 EP / 13 AUX CONTROL SYSTEM RELAY CABINET RC13-3 SALEM NUCLEAR GE.ING STATION - UNIT 1.
SCREENING VERIFICATION DATA SHEET (SVDS)
Bldg.
Fl El.
RmorRwlCI Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 122.00 CRA/C Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Certification:
Base El.
100.00 100.00 122.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00 Page# 11/23
<40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
NIA ABS CRS Yes Yes Yes Yes Yes NIA ABS CRS Yes Yes Yes Yes Yes NIA ABS CRS Yes Yes Yes Yes Yes Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No
.Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all th'e
- Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude 04/20195 Print or Type Name Date Print or Type Name Signature Date Steve Anagnostis 04120195 Print or Type Name Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04/20/951.
Eq.
Eq. ID Rev Cl No 20 RC13-4 0
20 RC13-5 0
20 RC13-6 0
20 RC13-7 0
20 RC14-3 0
20 RC14-5 0
20 RC14-6 0
20 RC14-7 0
20 RC15-3 0
20 RC15-4 0
20 RC15-6 0
20 RC15-7 0
20 RC16-5 0
20 RC16-6 0
Certification:
Sys/Eq. Desc EP / 13 AUX CONTROL SYSTEM RELAY CABINET RC13-4 EP / 13 AUX CONTROL SYSTEM RELAY CABINET RC13-5 EP / 13 AUX CONTROL SYSTEM RELAY CABINET RC13-6 EP / 13 AUX CONTROL SYSTEM RELAY CABINET RC13-7 EP / 14 AUX CONTROL SYSTEM RELAY CABINET RC14-3 EP / 14 AUX CONTROL SYSTEM RELAY CABINET RC14-5 EP / 14 AUX CONTROL SYSTEM RELAY CABINET RC14-6 EP / 14 AUX CONTROL SYSTEM RELAY CABINET RC14-7 EP / 15 AUX CONTROL SYSTEM RELAY CABINET RC15-3 EP / 15 AUX CONTROL SYSTEM RELAY CABINET RC15-4 EP / 15 AUX CONTROL SYSTEM RELAY CABINET RC15-6 EP / 15 AUX CONTROL SYSTEM RELAY CABINET RC15-7 EP / 16 AUX CONTROL SYSTEM RELAY CABINET RC16-5 EP / 16 AUX CONTROL SYSTEM RELAY CABINET RC16-6 SALEM NUCLEAR GE.~G STATION - UNIT 1 SCREENING VERIFICATION DATA SHEET (SVDS)
Bldg.
Fl El.
Rm orRw/CI Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Certification:
Base El.
100.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00
.'age# 12/23
<40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes Yes Yes No No Yes BS GRS Yes Yes Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes Yes Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes Yes Yes No No Yes BS GRS Yes Yes Yes No No All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the
-Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude I c7. /??. At1.-JJ..-~ I 04/20/95 Print or Type Name I
Signature Date Print or Type Name Signature Date Steve Anagnostis
,~
<::: :+
04/20/95 Print or Type Name Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
Eq.
Eq. ID Rev Cl No 20 RC16-7 0
20 RC18-4 0
20 RC18-5 0
20 RC18-6 0
Certification:
Sys/Eq. Desc EP / 16 AUX CONTROL SYSTEM RELAY CABINET RC16-7 EP / 18 AUX CONTROL SYSTEM RELAY CABINET RC18-4 EP / 18 AUX CONTROL SYSTEM RELAY CABINET RC18-5 EP / 18 AUX CONTROL SYSTEM RELAY CABINET RC18-6 SALEM NUCLEAR GE.G STATION - UNIT 1 SCREENIN'G VERIFICATION DATA SHEET (SVDS)
Bldg.
FIEI.
Rm orRw/CI Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Certification:
Base El.
100.00 100.00 100.00 100.00
- age# 13/23
<40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
Yes BS GRS Yes Yes Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the
-Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude I ~ /h. 6J-& v°]..u~
04/20/95 Print or Type Name I
Signature Date Print or Type Name Signature Date 7~2£?
~~
Steve Anagnostis 04/20/95 Print or Type Name Date Print or Type Name Signature Date*
Print or Type Name Signature Date Print or Type Name Signature Date
04/20/95 1.M SALEM NUCLEAR GE.r.IG STATION - UNIT 1 SCREENING VERIFICATION DATA SHEET (SVDS)
.,..;age# 14/23 Eq.
Eq. ID Rev Sys/Eq. Desc Bldg.
FIEI.
Cl No 0
1DAE25 0 DA/ 12A DIESEL START AIR RCVR Aux 1 100.00 0
1DAE26 0 DA/ 12B DIESEL START AIR RCVR Aux 1 100.00 0
1DAE39 0 DA/ 13A DIESEL START AIR RCVR Aux 1 100.00 0
1DAE40 0
DA I 13B DIESEL START AIR RCVR Aux 1 100.00 0
1DAE5 0 DA/ 11A DIESEL START AIR RCVR Aux 1 100.00 0
1DAE6 0
DA 111 B DIESEL START AIR RCVR Aux 1 100.00 7
11SW39 0 SW/ 1A DG SW INLET TO COOLER Aux 1 100.00 7
11SW42 0 SW/ 1A DG CLG SWTHROT PNL 740-1Z Aux 1 100.00 7
12SW39 0 SW/ 1 B DG SW INLET TO COOLER Aux 1 100.00 7
12SW42 0 SW/ 1 B DG CLG SW CONTROL PNL Aux 1 100.00 7401AA 7
13SW39 0
SW/ 1C DG SW INLET TO COOLER Aux 1 100.00 7
13SW42 0 SW/ 1C DG CLG SWTH PNL 740-1BB Aux 1 100.00 7
1CV114 0
RCS I RCP SEAL WTR BYP STOP V Cntmnt 1 78.00 7
1CV2 0
CV I LETDOWN LINE ISOLATION VALVE Cntmnt 1 78.00 7
1CV277 0
CV IL TOWN LINE ISOL VALVE Cntmnt 1 78.00 7
1PR1 0
PR I PZR PWR OP RELIEF V Cntmnt 1 130.00 7
1PR2 0
PR I PZR PWR OP RELIEF V Cntmnt 1 130.00 7
1PR3 0
I PRESSURIZER RELIEF VALVE Cntmnt 1 130.00 7
1PR4 0
PR I PRESSURIZER RELIEF VALVE Cntmnt 1 130.00 7
1PR5 0
PR I PRESSURIZER RELIEF VALVE Cntmnt 1 130.00 8
11SJ54 0
SJ I ACCUM OUTLET VALVE Cntmnt 1 78.00 8
12SJ54 0
SJ I ACCUM OUTLET VALVE Cntmnt 1 78.00 8
13SJ54 0
SJ I ACCUM OUTLET VALVE Cntmnt 1 78.00 8
14SJ54 0 SJ I ACCUM OUTLET VALVE Cntmnt 1 78.00 8
1PR6 0
PR I PZR PWR OP RELIEF STOP MOV Cntmnt 1 130.00 8
1PR7 0
PR I PZR PWR OP RELIEF STOP MOV Cntmnt 1 130.00 Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professional engineer.)
Jim Flaherty (6-04/20195 Print or Type Name Date Steve Anagnostis 04120195 Print or Type Name Date Print or Type Name Signature Date Rm orRw/CI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
1B D/G Rm 100.00 N/A DOC RRS Yes Yes Yes Yes Yes 1B D/G Rm 100.00 N/A DOC RRS Yes Yes Yes Yes Yes 1C DIG Rm 100.00 NIA DOC RRS Yes Yes Yes Yes Yes 1C DIG Rm 100.00 NIA DOC RRS Yes Yes Yes Yes Yes 1ADIG Rm 100.00 NIA DOC RRS Yes Yes Yes Yes Yes 1ADIG Rm 100.00 NIA DOC RRS Yes Yes Yes Yes Yes 1AD/G Rm 100.00 Yes BS GRS Yes Yes NIA Yes Yes 1AD/G Rm 100.00 Yes BS GRS Yes Yes NIA Yes Yes 1B D/G Rm 100.00 Yes BS GRS Yes Yes N/A Yes Yes 18 D/G Rm 100.00 Yes BS GRS Yes Yes N/A Yes Yes 1C D/G Rm 100.00 Yes BS GRS Yes Yes N/A Yes Yes 1C D/G Rm 100.00 Yes BS GRS Yes Yes N/A Yes Yes Cor at Elevator 78.00 N/A ABS CRS Yes Yes N/A Yes Yes Regen Hx Rm 78.00 N/A ABS CRS Yes Yes NIA Yes Yes Regen Hx Rm 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 1 Pzr Area 130.00 N/A ABS CRS Yes Yes NIA Yes Yes 1 PzrArea 130.00 NIA ABS CRS Yes Yes N/A Yes Yes 1 PzrArea 130.00 N/A ABS CRS Yes Yes N/A Yes Yes 1 PzrArea 130.00 N/A ABS CRS Yes Yes N/A Yes Yes 1 PzrArea 130.00 N/A ABS CRS Yes Yes NIA Yes Yes 11 Accumulator 78.00 N/A ABS CRS Yes Yes N/A Yes Yes 12 Accumulator 78.00 N/A ABS CRS Yes Yes NIA Yes Yes 13 Accumulator 78.00 N/A ABS CRS Yes Yes NIA Yes Yes 14 Accumulator 78.00 NIA ABS CRS Yes Yes N/A Yes Yes 1 Pzr Area 130.00 N/A ABS CRS Yes Yes NIA Yes Yes 1 Pzr Area 130.00 N/A ABS CRS Yes Yes NIA Yes Yes Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
, Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04/20/95 1.
1v1 Eq.
Eq. ID Rev Sys/Eq. Desc Cl No 8
1RH1 0
1RH2 0
1SV1198 0
PR I PORV ACCUM OUTLET SOL VLV 8
1SV1199 0
PR I PORV ACCUM OUTLET SOL VLV 9
1VHE15 0
VH / 11 CFCU FAN 9
1VHE16 0
VH"/ 12 CFCU FAN 9
1VHE17 0
VH / 13 CFCU FAN 9
1VHE18 0
VH / 14 CFCU FAN 9
1VHE19 0 VH / 15 CFCU FAN 10 1SWE24 0 SW/ 11 FCU 10 1SWE25 0 SW/ 12 FCU 10 1SWE26 0 SW/ 13 FCU 10 1SWE27 0 SW/ 14CFCU 10 1SWE28 0 SW/ 15CFCU 18 1PD9859 0
PR I PRESSURE SWITCH FOR 1 SV1198 18 1PD9860 0
PR I PRESSURE SWITCH FOR 1 SV1199 18 440-1A 0 VH / 11 CNTMNT VENT FCU DAMPER CONTRLPNL 18 440-1B 0 VH / 12 CNTMNT VENT FCU DAMPER CONTRLPNL 18 440-1C 0 VH / 13 CNTMNT VENT FCU DAMPER CONTRLPNL 18 440-10 0
VH / 14 CNTMNT VENT FCU DAMPER CONTRLPNL 18 440-1E 0 VH / 15 CNTMNT VENT FCU DAMPER CONTRLPNL 18 444-1A 0 AF/ 11 S/G FEED & COND PNL NARROW RANGE 1 Certification:
SALEM NUCLEAR G*
.* ~G STATION* UNIT 1 SCREENINC3 VERIFICATION DATA SHEET (SVDS)
Bldg.
Fl El.
RmorRw/CI Cntmnt 1 78.00 13 S/G, RCP & PZR Su Cntmnt 1 78.00 Cor at Elevator Cntmnt 1 130.00 1 Pzr Area Cntmnt 1 130.00 1 Pzr Area Cntmnt 1 130.00 11 CFCU Cntmnt 1 130.00 12 CFCU Cntmnt 1 130.00 13 CFCU Cntmnt 1 130.00 14 CFCU Cntmnt 1 130.00 15 CFCU Cntmnt 1 130.00 11 CFCU Cntmnt 1 130.00 12 CFCU Cntmnt 1 130.00 13 CFCU Cntmnt 1 130.00 14 CFCU Cntmnt 1 130.00 15 CFCU Cntmnt 1 130.00 1 Pzr Area Cntmnt 1 130.00 1 PzrArea Cntmnt 1 130.00 11 CFCU Cntmnt 1 130.00 12 CFCU Cntmnt 1 130.00 13CFCU Cntmnt 1 130.00 14 CFCU Cntmnt 1 130.00 15 CFCU Cntmnt 1 130.00 11 S/G Area Cert1ficat1on:
age#15/23 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
78.00 N/A ABS CRS Yes Yes N/A Yes Yes 78.00 N/A ABS CRS Yes Yes N/A Yes Yes 130.00 NIA ABS CRS Yes Yes N/A Yes Yes 130.00 N/A ABS CRS Yes Yes N/A Yes Yes 130.00 N/A ABS CRS Yes Yes Yes Yes Yes 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 130.00 N/A ABS CRS Yes Yes Yes Yes Yes 130.00 N/A ABS CRS Yes Yes Yes Yes Yes 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 130.00 N/A ABS CRS Yes Yes Yes Yes Yes 130.00 N/A ABS CRS Yes Yes Yes Yes Yes 130.00 N/A ABS CRS Yes Yes Yes Yes Yes 130.00 N/A ABS CRS Yes Yes Yes Yes Yes 130.00 N/A ABS CRS Yes Yes Yes Yes Yes 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 130.00 N/A ABS CRS Yes Yes Yes Yes Yes 130.00 N/A ABS CRS Yes Yes Yes Yes Yes 130.00 N/A ABS CRS Yes Yes Yes Yes Yes 130.00 N/A ABS CRS Yes Yes Yes Yes Yes 130.00 NIA ABS CRS Yes Yes
.Yes Yes Yes 130.00 N/A ABS CRS Yes Yes Yes Yes Yes 130.00 N/A ABS CRS Yes Yes Yes Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment containe~ in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the, Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Jim Flaherty 04/20/95 Print or Type Name Date Print or Type Name Signature Date Steve Anagnostis 04/20/95 Print or Type Name Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
SALEM NUCLEAR GE.NG STATION - UNIT 1 SCREENING VERIFICATION DATA SHEET (SVDS)
Page# 16123 Eq.
Eq. ID Rev SyslEq. Desc Bldg.
Fl El.
Cl No 18 444-1B 0 AF 111 SIG FEED & COND PNL NARROW Cntmnt 1 130.00 RANGE2 18 444-1C 0 AF 111 SIG FEED & COND PNL NARROW Cntmnt 1 130.00 RANGE3 18 444-10 0 AF 112 SIG FEED & COND PNL NARROW Cntmnt 1 130.00 RANGE 1 18 444-1E 0 AF 112 SIG FEED & COND PNL NARROW Cntmnt 1 130.00 RANGE2 18 444-1F 0 AF 112 SIG FEED & COND PNL NARROW Cntmnt 1 130.00 RANGE3 18 444-1G 0 AF 113 SIG FEED & COND PNL NARROW Cntmnt 1 130.00 RANGE 1 18 444-1H 0 AF 113 SIG FEED & COND PNL NARROW Cntmnt 1 130.00 RANGE2 18 444-1J 0 AF 113 SIG FEED & COND PNL NARROW Cntmnt 1 130.00 RANGE3 18 444-1K 0 AF 114 SIG FEED & COND PNL NARROW Cntmnt 1 130.00 RANGE 1 18 444-1L 0 AF 114 SIG FEED & COND PNL NARROW Cntmnt 1 130.00 RANGE2 18 444-1M 0 AF 114 SIG FEED & COND PNL NARROW Cntmnt 1 130.00 RANGE3 19 1TE413A 0
RC I TEMPERATURE ELEMENT, RCS LOOP Cntmnt 1 78.00 11 HOT LEG 19 1TE413B 0
RC I TEMPERATURE ELEMENT, RCS LOOP Cntmnt 1 78.00 11 COLD LEG 19 1TE423A 0
RC I TEMPERATURE ELEMENT, RCS LOOP Cntmnt 1 78.00 12 HOT LEG Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory ould be a licensed professional engineer.)
Jim Flaherty O~
04120195 Print or Type Name Date Steve Anagnostis 04/20195 Print or Type Name Date Print or Type Name Signature Date Rm orRwlCI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
11 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 11 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 12 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 12 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 12 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 13 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 13 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 13 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 14 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 14 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 14 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 11 SIG & RCP Support 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 11 SIG & RCP Support 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 12 SIG & RCP Support 78.00 NIA ABS CRS Yes Yes NIA Yes Yes Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
-Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
041201951&
Eq.
Eq. ID Rev SyslEq. Desc Cl No 19 1TE423B 0 RC I TEMPERATURE ELEMENT, RCS LOOP 12 COLD LEG 19 1TE433A 0 RC I TEMPERATURE ELEMENT, RCS LOOP 13 HOT LEG 19 1TE433B 0
RC I TEMPERATURE ELEMENT, RCS LOOP 13 COLD LEG 19 1TE443A 0
RC I TEMPERATURE ELEMENT, RCS LOOP 14HOTLEG 19 1TE443B 0
RC I TEMPERATURE ELEMENT, RCS LOOP 14 COLD LEG 20 335-1 0 PR 11 REACT COOL PZR PROTECTION PANEL 20 EC-1A 0 EP I EXCITER CABINET - 1A 20 EC-1B 0 EP I EXCITER CABINET-1B 20 EC-1C 0 EP I EXCITER CABINET-1C Certification:
SALEM NUCLEAR GE.NG STATION - UNIT 1 SCREENING VERIFICATION DATA SHEET (SVDS)
Bldg.
Fl El.
Rm orRwlCI Cntmnt 1 78.00 12 SIG & RCP Support Cntmnt 1 78.00 13 SIG & RCP Support Cntmnt 1 78.00' 13 SIG & RCP Support Cntmnt 1 78.00 14 SIG & RCP Support Cntmnt 1 78.00 14 SIG & RCP Support Cntmnt 1 100.00 Elevator Passage Are Aux 1 100.00 1ADIG Rm Aux 1 100.00 1B DIG Rm Aux 1 100.00 1C DIG Rm Certification:
Base El.
78.00 78.00 78.00 78.00 78.00 100.00 100.00 100.00 100.00
.r'age# 17123
<40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
NIA ABS CRS Yes Yes NIA Yes Yes NIA ABS CRS Yes Yes NIA Yes Yes NIA ABS CRS Yes Yes NIA Yes Yes NIA ABS CRS Yes Yes NIA Yes Yes NIA ABS CRS Yes Yes NIA Yes Yes NIA ABS CRS Yes Yes Yes Yes Yes Yes BS GRS Yes Yes Yes Yes Yes Yes BS GRS Yes Yes Yes Yes Yes Yes BS GRS Yes Yes Yes Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professi nal engineer.)
Jim Flaherty
'.f.
04120195 Print or Type Name Date Steve Anagnostis 04120195 Print or Type Name Date Print or Type Name Signature Date Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
-Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04120195
- SALEM NUCLEAR G..Ai AG STATION* UNIT 1 SCREENING VERIFI~
DATA SHEET (SVDS)
'age# 18123 Eq.
Eq. ID Rev SyslEq. Desc Bldg.
Fl El.
Cl No 2
1SWGR1ADC 0 EP I NO 1A 125VDC BUS Aux 1 84.00 2
1SWGR1BDC 0 EP I NO 1B 125VDC BUS Aux 1 84.00 2
1SWGR1C9X 0 EP I NO 1C460V VITAL BUS EXTENSION Aux 1 64.00 2
1SWGR1CDC 0 EP I NO 1C 125VDC BUS Aux 1 84.00 5
1AFE6 0 AF 113 AUX FEED PMP Aux 1 84.00 7
13AF21 0 AF I AUX FEED - SIG LEVEL CONTROL V Aux 1 84.00 7
1MS132 0 MS/ 13 AF PMP START/STOP V Aux 1 84.00 7
1MS53 0 MS/ 13 AF PMP TURB GOV Aux 1 84.00 8
1MS52 0 MS/ 13 AF PMP TURB TRIP VALVE (SV)
Aux 1 84.00 14 1ADE 0 EP I NO 1A 28VDC CONTROL BUS Aux 1 84.00 14 1CDE 0 EP I NO 1 C 28VDC CONTROL BUS Aux 1 84.00 14 1DDC 0 EP I 125VDC DISTRIBUTION CABINET Aux 1 84.00 15 1BTRY1CDC 0 EP I NO 1 C 125VDC BATTERY Aux 1 64.00 16 1BTRY1A10Y 0 EP I NO 1A1125VDC BATTERY CHARGER Aux 1 84.00 16 1BTRY1B10Y 0 EP I NO 1B1125VDC BATTERY CHARGER Aux 1 84.00 16 1BTRY1C12Y 0 EP I NO 1C1125VDC BATTERY CHARGER Aux 1 84.00 18 230-1 0 VH 11 AUX BLDG VENT SWGR RM INST Aux 1 84.00 PANEL Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Rm orRwlCI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
4601230V Vital 12512 84.00 N/A ABS CRS Yes Yes Yes Yes Yes 4601230V Vital 125/2 84.00 N/A ABS CRS Yes Yes Yes Yes Yes 4 KV Vital Bus & Bat 64.00 NIA ABS CRS No Unk Unk Unk No 460/230V Vital 125/2 84.00 N/A ABS CRS Yes Yes Yes Yes Yes 13 Aux Fd Pmp Rm 84.00 N/A ABS CRS Yes Yes Yes Yes Yes 12 Aux Fd Pmp Rm 84.00 N/A ABS CRS Yes Yes NIA Yes Yes 13Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 13 Aux Fd Pmp Rm 84.00 N/A ABS CRS Yes Yes N/A Yes Yes 13 Aux Fd Pmp Rm 84.00 N/A ABS CRS Yes Yes NIA Yes Yes 4601230V Vital 12512 84.00 N/A ABS CRS Yes No Yes Yes No 4601230V Vital 12512 84.00 NIA ABS CRS Yes No Yes Yes No 460/230V Vital 12512 84.00 NIA ABS CRS Yes Yes Yes Yes Yes C Bat Rm; Vital Bus 64.00 N/A ABS CRS Yes Yes Yes Yes Yes 4601230V Vital 125/2 84.00 N/A ABS CRS Yes Yes Yes Yes Yes 4601230V Vital 125/2 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 4601230V Vital 125/2 84.00 N/A ABS CRS Yes Yes Yes Yes Yes 4601230V Vital 125/2 84.00 NIA ABS CRS Yes Yes Yes Yes Yes Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the.Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Aziz Saber 04120195 Print or Type Name Date Print or Type Name Signature Date Walter Djordjevic 04/20195 Print or Type Name Date Print ~r Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04120195 1 **
11'1
..;l SALEM NUCLEAR GE
.* ~G STATION* UNIT 1 SCREENIN'G VERIFICATION DATA SHEET (SVDS)
'age# 19123 Eq.
Eq. ID Rev SyslEq. Desc Bldg.
Fl El.
Cl No 2
1SWGR1AX 0
EP I NO 1A 460V VITAL BUS Aux 1 84.00 2
1SWGR1AY 0
EP I NO 1A 230V VITAL BUS Aux 1 84.00 2
1SWGR1BX 0
EP I NO 1 B 460V VITAL BUS Aux 1 84.00 2
1SWGR1BY 0
EP I NO 1 B 230V VITAL BUS Aux 1 84.00 2
1SWGR1EPX 0
EP I NO. 1 EP 480V PRESSURIZER HTR IPA 1 78.00 BUS (BACK-UP GROUP 2) 2 1SWGR1GPX 0
EP I NO. 1 GP 480V PRESSURIZER HTR IPA 1 78.00 BUS (BACK-UP GROUP 1) 3 1SWGR1AD 0
EP I NO 1A 4160V VITAL BUS Aux 1 64.00 3
1SWGR1BD 0
EPINO 1B4160VVITALBUS Aux 1 64.00 4
1XFR1A4DAX 0 EP I TRANSFORMER TO NO. 1A 460V Aux 1 84.00 VITAL BUS 1SWGR1AX 4
1XFR1A4DBY 0 EP I TRANSFORMER TO NO. 1A 230V Aux 1 84.00 VITAL BUS 1SWGR1AY 4
1XFR1B4DAX 0
EP I TRANSFORMER TO NO. 1 B 460V Aux 1 84.00 VITAL BUS 1SWGR1BX 4
1XFR1B4DBY 0 EP I TRANSFORMER TO NO. 1 B 230V Aux 1 84.00 VITAL BUS 1SWGR1BY Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professional engineer.)
1 Signature Date
,c. /?7-A~~~_,,
Charbel Abou-Jaoude 04120195 Print or Type Name Aziz Saber
~-
04120195 Print or Type Name Signature Date Print or Type Name Signature Date Rm or RwlCI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
4601230V Vital 12512 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 4601230V Vital 12512 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 4601230V Vital 12512 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 4601230V Vital 12512 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 4601230V Vital 12512 84.00 NIA ABS* CRS Yes
. Yes Yes Yes Yes A. B. C East Valves 78.00 NIA ABS CRS Yes Yes Yes Yes Yes 4 KV Vital Bus & Bat 64.00 NIA ABS CRS Yes Yes Yes No No 4 KV Vital Bus & Bat 64.00 NIA ABS CRS Yes Yes Yes No No 4601230V Vital 12512 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 4601230V Vital 12512 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 4601230V Vital 12512 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 4601230V Vital 12512 84.00 NIA ABS CRS Yes Yes Yes Yes Yes Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
-Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
041201951 *.
"1 Eq.
Eq. ID Rev Cl No 5
1AFE4 0
5 1AFE5 0
5 1CCE2 0
5 1CCE3 0
5 1CCE4 0
5 1CSE1 0
5 1CSE2 0
5 1CVE20 0
5 1CVE21 0
5 1CVE22 0
5 1DFE9 0
5 1RHE1 0
5 1RHE2 0
5 1SJE101 0
5 1WGE2 0
5 1WGE3 0
7 11AF21 0
7 11RH18 0
7 11SW122 0
7 11SW127 0
7 11SW129 0
7 11SW153 0
7 12AF21 0
Certification:
SyslEq. Desc AF 111 AUX FEED PMP AF 112 AUX FEED PMP CC I CC PMP NO. 11 CC I CC PMP NO. 13 CC I CC PMP NO. 12 CV I CONTAINMENT SPRAY PUMP, NO. 11 CV I CONTAINMENT SPRAY PUMP, NO. 12 CV 111 CHG PMP, CENTRIFUGAL CV 112 CHG PMP, CENTRIFUGAL CV I CHARGING PUMP, RECIPROCATING DF I NO. 11 DIESEL FUEL OIL TRANSFER PUMP RH 111 RHR PMP RH 112 RHR PMP SW 112 SJ PMP LUBE OIL CLR CC I NO. 11 WASTE GAS COMPRESSOR HX CC I NO. 12 WASTE GAS COMPRESSOR HX AF I AUX FEED - SIG LEVEL CONTROL V RH 111 RHR HX FLOW CONT V SW I CC HX SW INLET CONTROL VALVE SW 111 CCHX SW OUTLET CONTROL VALVE SW 111 CC PMP RM CLR SW CONT V SW 111 RHR PMP RM CLR SW CONT V AF I AUX FEED - SIG LEVEL CONTROL V SALEM NUCLEAR G---.. G STATION - UNIT 1 SCREENING VERIFI~
DATA SHEET (SVCS)
Bldg.
FIEI.
Rm orRwlCI Aux 1 84.00 11 Aux Fd Pmp Rm Aux 1 84.00 12 Aux Fd Pmp Rm Aux 1 84.00 11 CCPmpRm Aux 1 84.00 12 & 13 CC Pmp Rm Aux 1 84.00 12 & 13 CC Pmp Rm Aux 1 84.00 11 Cont Spray Pmp Rm Aux 1 84.00 11 Cont Spray Pmp Rm Aux 1 84.00 11 Chrg Pmp Rm Aux 1 84.00 12 Chrg Pmp Rm Aux 1 84.00 13 Chrg Pmp Rm Aux 1 84.00 11 DIF X Pmp Rm Aux 1 45.00 11RHRPmpRm Aux 1 45.00 12 RHRPmp Rm Aux 1 84.00 12 SI Pmp Rm Aux 1 64.00 11 Waste Gas Cmpsr R Aux 1 64.00 12 Waste Gas Cmpsr R Aux 1 84.00 11 Aux Fd Pmp Rm Aux 1 45.00 11 RHRPmp Rm Aux 1 84.00 11 CC Pmp Rm Aux 1 84.00 11 CC Pmp Rm Aux 1 84.00 12 Aux Fd Pmp Rm Aux 1 45.00 11 RHRPmpRm Aux 1 84.00 12 Aux Fd Pmp Rm Certification:
~ge#20/23 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 45.00 NIA ABS CRS Yes Yes Yes Yes Yes 45.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 64.00 NIA ABS CRS Yes Yes Yes Yes Yes 64.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 45.00 NIA ABS CRS Yes Yes NIA Yes Yes 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 45.00 NIA ABS CRS Yes Yes.
NIA Yes Yes 84.00 NIA ABS CRS Yes Yes NIA Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRn Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the, Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Jim Flaherty 04120195 Print or Type Name Signature Date Print or Type Name Signature Date Aziz Saber 4!2>rak 04120195 d
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
Eq.
Eq. ID Rev Cl No 7
12RH18 0
7 12SW129 0
7 12SW153 0
7 12SW376 0
7 12SW379 0
7 12SW380 0
7 12SW383 0
7 14AF21 0
7 1CV55 0
7 1SW137 0
7 1SW191 0
7 1SW205 0
7 1SW213 0
8 11CC16 0
8 11CC3 0
8 12CC16 0
8 12CC3 0
8 1CC17 0
8 1CC18 0
8 1SJ1 0
8 1SJ2 0
10 1SWE13 0
10 1SWE14 0
Certification:
SyslEq. Desc RH/ 12 RHR HX FLOW CONT V SW/ 12 & 13 CC PMP RM CLRSWCONTV SW/ 12 RHR PMP RM CLR SW INLET VALVE SW/ 12B HX INLET VALVE SW/ 12B HX OUTLET VALVE SW/ 12A HX INLET VALVE SW/ 12A HX OUTLET VALVE AF I AUX FEED - SIG LEVEL CONTROL V CV I CENT CHG PMP FLOW CONT V SW I AF PMP RM CLR SW CONT V SW I CHG PMP RM CLR SW CONT V SW I CHG PMP ROOM CLR SW INLET V SW I CHG PMP RM CLR SW CONT V CC / 11 RHR HEAT EXCHANGER COMPONENT COOLING OUTLET VAVLE (MOV)
CC/ 11-13 HEADER X-OVER VLV CC 112 RHR HEAT EXCHANGER COMPONENT COOLING OUTLET VAVLE (MOV)
CC/ 12-13 HEADER X-OVER VLV CC I CC PMP SUCT X-OVER V CC I CC PUMP SUCTION X-OVER VLV CV I RWST TO CHG PMPS STOP MOV CV I RWST TO CHG PMPS STOP MOV SW/ 11 RHR PMP RM CLR SW/ 12 CHRG PMP RM CLR SALEM NUCLEAR G.'ING STATION - UNIT 1 SCREENING VERIFICATION DATA SHEET (SVDS)
Bldg.
Fl El.
Rm or Rw/CI Aux 1 45.00 12 RHR Pmp Rm Aux 1 84.00 11 Aux Fd Pmp Rm Aux 1 45.00 12 RHR Pmp Rm Aux 1 84.00 12 & 13 CC Pmp Rm Aux 1 84.00 12 & 13 CC Pmp Rm Aux 1 84.00 12 & 13 CC Pmp Rm Aux 1 84.00 12 & 13 CC Pmp Rm Aux 1 84.00 11 Aux Fd Pmp Rm Aux 1 84.00 Chrg Pmp Viv Alley Aux 1 84.00 12 Aux Fd Pmp Rm Aux 1 84.00 Chrg Pmp Viv Alley Aux 1 84.00 Chrg Pmp Viv Alley Aux 1 84.00 Chrg Pmp Viv Alley Aux 1 55.00 11 RHRVlv Rm Aux 1 84.00 11 CC Pmp Rm Aux 1 55.00 12 RHRVlv Rm Aux 1 84.00 12 & 13 CC Pmp Rm Aux 1 84.00 11 CC Pmp Rm Aux 1 84.00 12 & 13 CC Pmp Rm Aux 1 84.00 WIM Tk & Pmp Rm Aux 1 84.00 WIM Tk & Pmp Rm Aux 1 45.00 11 RHRPmp Rm Aux 1 84.00 12 Chrg Pmp Rm Cert1ficat1on:
Page# 21123 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
45.00 NIA ABS CRS Yes Yes NIA Yes Yes 84.00 NIA ABS CRS Yes Yes N/A Yes Yes 45.00 NIA ABS CRS Yes Yes NIA Yes Yes 84.00 NIA ABS CRS Yes Yes N/A Yes Yes 84.00 N/A ABS CRS Yes Yes NIA Yes Yes 84.00 NIA ABS CRS Yes Yes N/A Yes Yes 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 84.00 N/A ABS CRS Yes Yes NIA Yes Yes 84.00 N/A ABS CRS Yes Yes NIA Yes Yes 84.00 N/A ABS CRS Yes Yes NIA Yes Yes 84.00 N/A ABS CRS Yes Yes NIA Yes Yes 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 84.00 NIA ABS CRS Yes Yes N/A Yes Yes 55.00 N/A ABS CRS Yes Yes N/A Yes Yes 84.00 NIA ABS CRS Yes Yes N/A Yes Yes 55.00 NIA ABS CRS Yes Yes NIA Yes Yes 84.00 N/A ABS CRS Yes Yes N/A Yes Yes 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 45.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the
- Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Jim Flaherty 04120/95 Print or Type Name Date Print or Type Name Signature Date Aziz Saber 04/20/95 Print or Type Name Date Print.or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
SALEM NUCLEAR GE.ING STATION - UNIT 1 SCREENl~G VERIFICATION DATA SHEET (SVDS)
Page# 22123 Eq.
Eq. ID Rev Sys/Eq. Desc Bldg.
Fl El.
Cl No 10 1SWE15 0 SW/ 11 CONT SPRAY PMP RM CLR Aux 1 84.00 10 1SWE16 0 SW/ 11 CC PMP RM CLR Aux 1 84.00 10 1SWE17 0 SW/ 11 & 12 AF PMP RM CLR Aux 1 84.00 10 1SWE18 0 SW/ 12 & 13 CC PMP RM CLR Aux 1 84.00 10 1SWE19 0 SW/ 12 RHR PMP RM CLR Aux 1 45.00 10 1SWE21 0 SW/ 1 SJ PMP RM CLR Aux 1 84.00 10 1SWE22 0 SW/ 12 CONT SPRAY PMP RM CLR Aux 1 84.00 10 1VHE31 0 VH / 11 RHR PMP RM CLR Aux 1 45.00 10 1VHE32 0 VH / 12 RHR PMP RM CLR Aux 1 45.00 10 1VHE33 0 VH / 11 CC PMP RM CLR FAN UNIT Aux 1 84.00 10 1VHE34 0 VH / 12 & 13 CC PMP RM CLR FAN UNIT Aux 1 84.00 10 1VHE36 0 VH / 11 & 12 AUX FEED WTR PMP RM CLR Aux 1 84.00 FAN UNIT 10 1VHE37 0 VH / 11 CHRG PMP RM CLR FAN UNIT Aux 1 84.00 10 1VHE38 0 VH / 12 CHRG PMP RM CLR FAN UNIT Aux 1 84.00 10 1VHE39 0 VH / 13 CHRG PMP RM CLR FAN UNIT Aux 1 84.00 18 203-1 0 CC/ PANEL Aux 1 84.00 20 216-1 0 CV/ 1 eve CHG PMPS FL & PR INST Aux 1 84.00 PANEL 20 229-1A 0
/PANEL Aux 1 84.00 20 229-1B 0
I PANEL Aux 1 84.00 Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Rm orRw/CI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
11 Cont Spray Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 11 CC Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 12 Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 12 Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 12 RHR Pmp Rm 45.00 NIA ABS CRS Yes Yes Yes Yes Yes 11 SI Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 12 Cont Spray Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 11 RHRPmp Rm 45.00 NIA ABS CRS Yes Yes Yes Yes Yes 12 RHRPmp Rm 45.00 NIA ABS CRS Yes Yes Yes Yes Yes 13Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 12Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 12 Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 11 Chrg Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 12 Chrg Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 13 Chrg Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes RM11CCHX 84.00 NIA ABS CRS Yes Yes Yes Yes Yes Chrg Pmp Viv Alley 100.00 NIA ABS CRS Yes Yes Yes Yes Yes Chg Pmp Viv Alley 100.00 NIA ABS CRS Yes Yes Yes Yes Yes Chg Pmp Viv Alley 100.00 NIA ABS CRS Yes Yes Yes Yes Yes Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRn Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the, Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Jim Flaherty 04/20/95 Print or Type Name Signature Date Print or Type Name Signature Date Aziz Saber
~A 04/20/95 Print or Type Name Signature
~
Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04120195 1**M Eq.
Eq. ID Rev Cl No 15 1BTRY1ADC 0
15 1BTRY1ADE 0
15 1BTRY1BDC 0
15 1BTRY1BDE 0
16 1BTRY1A12Y 0
16 1BTRY1B14Y 0
16 11NV1A5YB 0
16 11NV1B11YB 0
16 11NV185YB 0
16 11NV1C5YB 0
16 11NV1C6YC 0
Certification:
SyslEq. Desc EP I NO 1A 125VDC BATTERY EP I NO 1A 28VDC BATTERY EP I NO 1B 125VDC BATTERY EP I NO 1 B 28VDC BATTERY EP I NO 1A1 28VDC BATTERY CHARGER EP I NO 181 28VDC BATTERY CHARGER EP I NO 1A VITAL INSTRUMENT INVERTER EP I NO 1 D VITAL INSTRUMENT INVERTER EP I NO 1 B VITAL INSTRUMENT INVERTER EP I NO 1C VITAL INSTRUMENT INVERTER EP I NO 11 & 12 STATION ESSENTIAL CONTROL INVERTER SALEM NUCLEAR G~.NG STATION - UNIT 1 SCREENING VERIFIC~
DATA SHEET (SVDS)
Bldg.
Fl El.
Rm or RwlCI Aux 1 100.00 125 VDC Bat Rm Aux 1 100.00 125 voe Bat Rm Aux 1 100.00 1 B 125V Bat Rm (Sout Aux 1 100.00 18 125V Bat Rm (Sout Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Aux 1 100.00 1 Relay Rm Certification:
2age # 23/23 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes No No 100.00 NIA ABS CRS Yes Yes Yes No No 100.00 NIA ABS CRS Yes Yes Yes No No 100.00 NIA ABS CRS Yes Yes Yes No No 100.00 NIA ABS CRS Yes Yes Yes No No All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the, Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Jim Flaherty 04120195 Print or Type Name Date Print or Type Name Signature Date Charbel Abou-Jaoude 04/20/95 Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION ATTACHMENT F SVDS SALEM UNIT2 (25 Pages)
04120195 O.NI Eq.
Eq. ID Rev Cl No 0
2BRE16 0
0 2BRE17 0
0 2BRE18 0
0 2SWE10 0
0 2SWE11 0
0 2SWE12 0
0 2SWE7 0
0 2SWE8 0
0 2SWE9 0
1 12101 0
1 12102 0
1 12103 0
1 12104 0
1 12105 0
1 12106 0
1 12107 0
1 12108 0
1 12109 0
Certification:
SyslEq. Desc CCIB.A.EVAP.CONDENSER CC I DISTILLATE COOLER CC I VENT CONDENSER SW I 24 SW PMP DISCH STRAINER SW 125 SW PMP DISCH STRAINER SW 126 SW PMP DISCH STRAINER SW 121 SW PMP DISCH STRAINER SW I 22 SW PMP DISCH STRAINER SW 123 SW PMP DISCH STRAINER EP I NO 2A SERV WTR INTAKE 230V VITAL CONTROL CENTER EP I NO 2B1 SERV WTR INTAKE 230V VITAL CONTROL CENTER EP I NO 2C SERV WTR INTAKE 230V VITAL CONTROL CENTER EP I NO 2A DIESEL GENERATOR 230V VITAL CONTROL CENTER EP I NO 28 DIESEL GENERATOR 230V VITAL CONTROL CENTER EP I NO 2C DIESEL GENERATOR 230V VITAL CONTROL CENTER EP I NO 2A EAST VALVES & MISC. 230V VITAL CONTROL CENTER EP I NO 2C EAST VALVES & MISC. 230V VITAL CONTROL CENTER EP I NO 28 WEST VALVES & MISC. 230V VITAL CONTROL CENTER SALEM NUCLEAR G **
r'G STATION - UNIT 2 SCREENING VERIFICATION DATA SHEET (SVDS)"
Bldg.
Fl El.
Rm orRw/CI Aux2 100.00 BAEvap Rm Aux2 100.00 BAEvap Rm Aux2 100.00 BAEvap Rm Yard 100.00 Srvc wtr Bldg Yard 100.00 Srvc wtr Bldg Yard 100.00 Srvc wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc wtr Bldg Yard 100.00 Srvc Wtr Bldg Aux2 100.00 2A D/G Control Area Aux2 100.00 28 D/G Control Area Aux2 100.00 2C D/G Control Area IPA2 78.00 A, B, C East Valves CC IPA2 78.00 A, B, C East Valves CC Aux2 84.00 Elec Contr Center Certification:
Page#1/25 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
100.00 NIA DOC RRS Yes Yes Yes Yes Yes 100.00 N/A DOC RRS Yes Yes Yes Yes Yes 100.00 NIA DOC RRS Yes Yes Yes Yes Yes 100.00 NIA DOC CRS Yes Yes Yes Yes Yes 100.00 NIA DOC CRS Yes Yes Yes Yes Yes 100.00 NIA DOC CRS Yes Yes Yes Yes Yes 100.00 NIA DOC CRS Yes Yes Yes Yes Yes 100.00 NIA DOC CRS Yes Yes Yes Yes Yes 100.00 NIA DOC CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 78.00 NIA ABS CRS Yes Yes Yes No No 78.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 N/A ABS CRS Yes Yes No Yes No All the information contained on this Screening Verification Data Sheet (SVCS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVCS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Aziz Saber 04120195 Print or Type Name Date Steve Anagnostis 04120195 Print or Type Name Date Print or Type Name Signature Date Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
-Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04120195 0.111 Eq.
Eq. ID Rev Cl No 1
12110 0
1 12111 0
1 12112 0
1 12126 0
1 12131 0
1 12132 0
1 12133 0
1 12136 0
1 12137 0
6 2SWE1 0
6 2SWE2 0
6 2SWE3 0
6 2SWE4 0
6 2SWE5 0
6 2SWE6 0
7 21GB4 0
7 21SW24 0
7 22GB4 0
7 22SW24 0
Certification:
SyslEq. Desc EP I NO 2C WEST VALVES & MISC. 230V VITAL CONTROL CENTER EP I NO 2A AIR COND 230V VITAL CONTROL CENTER EP I NO 28 AIR COND 230V VITAL CONTROL CENTER EP I NO 282 SERV WTR INTAKE 230V VITAL CONTROL CENTER EP I NO 2A VENTILATION 230V VITAL CONTROL CENTER EP I NO 28 VENTILATION 230V VITAL CONTROL CENTER EP I NO 2C VENTILATION 230V VITAL CONTROL CENTER EP I NO 2A WEST VALVES & MISC. 230V VITAL CONTROL CENTER EP I NO 28 EAST VALVES & MISC. 230V VITAL CONTROL CENTER SW 121 SERVICE WATER PUMP SW 122 SERVICE WATER PUMP SW 123 SERVICE WATER PUMP SWl24SWPMP SWl25SWPMP SWl26SWPMP GB 121 SIG SLOWDOWN ISO VLV SW I SW STR BD CONT V GB 122 SIG SLOWDOWN ISO VLV SW I SW STR BD CONT V SALEM NUCLEAR GE.4G STATION - UNIT 2 SCREENING VERIFICATION DATA SHEET (SVDS)
Bldg.
FIEI.
Rm orRwlCI Aux2 84.00 22 Aux Fd Pmp Rm Aux2 122.00 CRA/CRm Aux2 122.00 Aux Bldg Sup Vent Yard 100.00 Srvc Wtr Bldg IPA2 100.00 CH Wtr Pmp Area IPA2 100.00 CH Wtr Pmp Area IPA2 100.00 CH Wtr Pmp Area Aux2 84.00 Cor at Aux Fd Pmp Area IPA2 78.00 A, B, C East Valves CC Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg Yard 100.00 Srvc Wtr Bldg IPA2 78.00 Mech Pen Area Yard 100.00 Srvc Wtr Bldg IPA2 78.00 Mech Pen Area Yard 100.00 Srvc Wtr Bldg Certification:
Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
84.00 NIA ABS CRS Yes Yes Yes Yes Yes 122.00 NIA ABS CRS Yes Yes Yes No No 122.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes No No Yes No 100.00 NIA ABS CRS Yes No No Yes No 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 78.00 NIA ABS CRS Yes Yes Yes No No 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 78.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 NIA ABS CRS Yes Yes NIA Yes Yes 78.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 NIA ABS CRS Yes Yes NIA Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Aziz Saber 04120195 Print or Type Name Date Steve Anagnostis 04120195 Print or Type Name Date Print or Type Name Signature Date Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
-Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date*
Print or Type Name Signature Date
04/20/95 08.1111 SALEM NUCLEAR GE-~G STATION - UNIT 2 SCREENING VERIFICATION DATA SHEET (SVDS)
Page#3/25 Eq.
Eq. ID Rev Sys/Eq. Desc Bldg.
FIEI.
Cl No 7
23GB4 0 GB/ 23 S/G SLOWDOWN ISO VLV IPA2 78.00 7
23SW24 0
SW I SW STR BO CONT V Yard 100.00 7
24GB4 0
GB 124 SIG SLOWDOWN ISO VLV IPA2 78.00 7
24SW24 0 SW I SW STR BO CONT V Yard 100.00 7
25SW24 0 SW I SW STR BO CONT V Yard 100.00 7
26SW24 0
SW I SW STR BO CONT V Yard 100.00 7
2SW308 0
SW I SW PRESS CONT HOR REG V Yard 100.00 8
21SW20 0 SWITG HDRSUPV Yard 100.00 8
23SW20 0 SW ITG HOR SUP V Yard 100.00 8
2CV40 0
CV I VCT OUTLET STOP V Aux2 100.00 8
2CV41 0
CV I VCT OUTLET STOP V Aux2 100.00 8
2CV68 0
CV I CHG HOR MOT OPER STOP V IPA2 78.00 8
2CV69 0 CV I CHG HOR MOT OPER STOP V IPA2 78.00 8
2SW26 0
SW I TURB AREA SW MOV STOP V Yard 100.00 9
2VHE64 0 VH I 21 EMERG A/C SUP FAN Aux2 122.00 9
2VHE65 0
VH 122 EMERG A/C SUP FAN Aux2 122.00 10 2CAA15-0 VH I 2 CONTRL AREA VENT EMER AIR Aux2 122.00 DMOP COND SUP FAN 21 OUTLET DMOP 10 2CAA16-0 VH 12 CONTRL AREA VENT EMER AIR Aux2 122.00 DMOP COND SUP FAN 22 OUTLET DMOP 10 2CAA17-0 VH I 2 CONTRL AREA VENT EMER AIR Aux2 122.00 DMOP FL TR INTK DMOP 14 2AADC 0
EP I 125VDC DISTRIBUTION CABINET Aux2 100.00 14 2BBDC 0
EP I 125VDC DISTRIBUTION CABINET Aux2 100.00 14 2BDE 0
EP I NO 28 28VDC CONTROL BUS Aux2 100.00 14 2CCDC 0
EP / 125VDC DISTRIBUTION CABINET Aux2 100.00 Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Aziz Saber 04/20195 Print or Type Name Date Steve Anagnostis 04/20195 Print or Type Name Date Print or Type Name Signature Date Rm orRw/CI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
Mech Pen Area 78.00 Yes BS GRS Yes Yes NIA Yes Yes Srvc Wtr Bldg N/A ABS CRS Yes Yes NIA Yes Yes Mech Pen Area 78.00 Yes BS GRS Yes Yes NIA Yes Yes Srvc Wtr Bldg 100.00 NIA ABS CRS Yes Yes NIA Yes Yes Srvc Wtr Bldg 100.00 NIA ABS CRS Yes Yes NIA Yes Yes Srvc Wtr Bldg 100.00 NIA ABS CRS Yes Yes NIA Yes Yes Srvc Wtr Bldg 100.00 NIA ABS CRS Yes Yes NIA Yes Yes Srvc Wtr Bldg 100.00 NIA ABS CRS Yes Yes NIA Yes Yes Srvc wtr Bldg 100.00 NIA ABS CRS Yes Yes NIA Yes Yes Rm By BA XF Pmps 100.00 Yes BS GRS Yes Yes NIA Yes Yes Rm By BA XF Pmps 100.00 Yes BS GRS Yes Yes NIA Yes Yes Mech Pen Area SG BO 78.00 Yes BS GRS Yes Yes NIA Yes Yes Hx Mech Pen Area SG BO 78.00 Yes BS GRS Yes Yes NIA Yes Yes Hx Srvc Wtr Bldg 100.00 NIA ABS CRS Yes Yes NIA Yes Yes CRA/CRm 140.00 Yes BS GRS Yes Yes Yes Yes Yes CRA/CRm 140.00 Yes BS GRS Yes Yes Yes Yes Yes CRA/CRm 140.00 Yes BS GRS Yes Yes Yes Yes Yes CRA/C Rm 140.00 Yes BS GRS Yes Yes Yes Yes Yes CRA/CRm 140.00 Yes BS GRS Yes Yes Yes Yes Yes 2 Relay Rm 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 2 Relay Rm 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 2 Relay Rm 100.00 Yes BS GRS Yes Yes Yes Yes Yes 2 Relay Rm 100.00 NIA ABS CRS Yes Yes Yes Yes Yes Cert1ficat1on:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability "Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date*
Print or Type Name Signature Date
04120195 08.111 Eq.
Eq. ID Rev Cl No 14 2DDE 0
14 2SWGR2ADE 0
14 2SWGR2BDE 0
20 103-2 0
20 131-2 0
20 132-2 0
20 205-2 0
20 206-2 0
20 207-2 0
20 2CC1 0
20 2CC2 0
20 2CC3 0
20 2PNL11828 0
20 2PNL11829 0
20 2PNL11830 0
20 2PNL11831 0
20 2PNL11832 0
20 2PNL11833 0
Certification:
SyslEq. Desc I NO 2D 28VDC CONTROL BUS EP I NO 2A 28VDC BUS EP I NO 2B 28VDC BUS EP 12 RAD WASTE LQUID AUX SUPM TNK LVLPANEL EP 12 REACTOR PROT SOLID STATE PROT TRAIN A OUTPUT TEST PANEL 131 EP 12 REACTOR PROT SOLID STATE PROT OUTPUT TEST CAB NO. 132 EP 121 AUX FEEDWATER PANEL 205 EP 122 AUX FEEDWATER PANEL 206 AF 123 AUX FEEDWATER PANEL 12 REACTOR PROT CONTROL ROOM CONSOLE PANEL 12 REACTOR PROT CONTROL ROOM CONSOLE PANEL I 2 MN STM & TRB BYPASS CONTROL ROOM CONSOLE PANEL EP I 2A DIG GENERATOR CONTROL PANEL EP I 2A DIG ENGINE CONTROL PANEL EP I 2B DIG GENERATOR CONTROL PANEL EP I 2B DIG ENGINE CONTROL PANEL EP I 2C DIG GENERA TOR CONTROL PANEL EP I 2C DIG ENGINE CONTROL PANEL SALEM NUCLEAR GE **
G STATION* UNIT 2 SCREENING VERIFICATION DATA SHEET (SVCS)
Bldg.
FIEI.
Rm orRwlCI Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 122.00 2 Control Rm Aux2 122.00 2 Control Rm Aux2 122.00 2 Control Rm Aux2 84.00 22 Aux Fd Pmp Rm Aux2 84.00 22 Aux Fd Pmp Rm Aux2 84.00 22 Aux Fd Pmp Rm Aux2 122.00 2 Control Rm Aux2 122.00 2 Control Rm Aux2 122.00 2 Control Rm Aux2 100.00 2A DIG Control Area Aux2 100.00 2A DIG Control Area Aux2 100.00 2B DIG Control Area Aux2 100.00 2B DIG Control Area Aux2 100.00 2C DIG Control Area Aux2 100.00 2C DIG Control Area Certification:
rage# 4125 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes No Yes No No 122.00 Yes BS GRS Yes No Yes No No 122.00 Yes BS GRS Yes No Yes No No 84.00 NIA ABS CRS Yes No Yes No No 84.00 NIA ABS CRS Yes No Yes No No 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes No Yes No No 100.00 Yes BS GRS Yes No Yes No No 100.00 Yes BS GRS Yes No Yes No No 100.00 Yes BS GRS Yes No Yes No No 100.00 Yes BS GRS Yes No Yes No No 100.00 Yes BS GRS Yes No Yes No No All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Aziz Saber I~~-
I 04120195 Print or Type Name
£'"""""'"
Date Print or Type Name Signature Date Steve Anagnostis
)
~ Cj/' c:;:: I 04120195 Print or Type Name Signature Date Print or Type Name Signature Date*
Print or Type Name Signature Date Print or Type Name Signature Date
- I
04120195 O.M Eq.
Eq. ID Rev Cl No 20 2PNL11834 0
20 2PNL11835 0
20 2PNL11836 0
20 2RP2 0
20 2TRCC 0
20 2TRDD 0
20 32-2 0
20 37-2 0
20 378-2 0
20 379-2 0
20 38-2 0
20 401-2 0
20 58-2 0
20 59-2 0
20 SEC-2A 0
Certification:
SyslEq. Desc EP I 2A DIG 230V CONTORL CENTER AUX PANEL EP I 2B DIG 230V CONTORL CENTER AUX PANEL EP I 2C DIG 230V CONTORL CENTER AUX PANEL EP I 2 AUX BLDG VENT CONT RM RECORDER PNL EP 12 CABINET RELAY ROOM TERMINAL RACK2TRCC EP 121-24 MN STM & TRB BY PASS STY V HYD PMP OVRD RL Y TERM RACK EP 12 REACT PROT SOLID STATE PROT INTERFACE CAB NO. 32 EP 12 REACT PROT SOLID STATE PROT TRAIN B OUTPUT CAB NO. 37 SJ I 2 SAFETY INJ RWST 230V AC, 1 KW PANEL SJ I 2 SAFETY INJ RWST 230V AC, 1 KW PANEL EP 12 REACT PROT SOLID STATE PROT TRAIN B INTERFACE CAB NO. 38 CC 12 CC SURGE TNK LVL INST PNL EP 12 CABINET AUX RELAY RACK EP 12 CABINET AUX RELAY RACK EP I SAFEGUARDS EMERGENCY CABINET
-2A SALEM NUCLEAR GEN."'G STATION - UNIT 2 SCREENIN~ VERIFICATION DATA SHEET {SVCS)
Bldg.
Fl El.
Rm orRwlCI Aux2 100.00 2A DIG Control Area Aux2 100.00 2B DIG Control Area Aux2 100.00 2C DIG Control Area Aux2 122.00 2 West Elevator Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 122.00 2 Control Rm Aux2 122.00 2 Control Rm Yard 100.00 Fire PmplFresh Water House Yard 100.00 2 RWSTArea Aux2 122.00 2 Control Rm Aux2 122.00 2 CC Surge Tk Area Aux2 122.00 2 Control Rm Aux2 122.00 2 Control Rm Aux2 100.00 2 Relay Rm Certification:
.Page#5/25 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes No Yes No No 122.00 Yes BS GRS Yes No Yes No No 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes No Yes No No 122.00 Yes BS GRS Yes Yes Yes Yes Yes 122.00 Yes BS GRS Yes No Yes No No 122.00 Yes BS GRS Yes No Yes No No 100.00 Yes BS GRS Yes No Yes No No All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professional engineer.)
Aziz Saber
~
04120195 Steve Anagnostis Signature
&~z:::y~*
7 Signature Date Print or Type Name E 04120/95 Print or Type Name Date Print or Type Name Signature Date Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability Engineers deem it necessary.)
- Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
Eq.
Eq. ID Rev Sys/Eq. Desc Cl No 20 SEC-2B 0 EP I SAFEGUARDS EMERGENCY CABINET
-2B 20 SEC-2C 0 EP I SAFEGUARDS EMERGENCY CABINET
-2C Certification:
SALEM NUCLEAR GE.1NG STATION - UNIT 2 SCREENING VERIFIC~DATA SHEET (SVDS)
Bldg.
FIEI.
Rm orRw/CI Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Certification:
Base El.
100.00 100.00 Page#6125
<40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
Yes BS GRS Yes No Yes No No Yes BS GRS Yes No Yes No No All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professional engineer.)
Aziz Saber
~=
04/20/95 Print or Type Name Signature Date Steve Anagnostis
- i 4.f ?S2" <"
- ;
- :;::: I 04120195 Print or Type Name Print or Type Name -
Signature Date Approved: (One signature of Systems or Operations Engineer Is required if the Seismic Capability
,Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Print or Type Name Signature Date
04/20/95 08.
Eq.
Eq. ID Rev Cl No 0
2DAE14 0
0 2DAE15 0
0 2DAE24 0
0 2DAE33 0
0 2DAE47 0
0 2DAE48 0
0 2DFE3 0
0 2DFE4 0
0 2DFE5 0
5 2CHE20 0
5 2CHE21 0
5 2CHE22 0
5 2CHE6 0
5 2CHE7 0
7 21MS10 0
7 21MS11 0
7 21MS12 0
7 21MS13 0
7 21MS14 0
7 21MS15 0
7 21MS167 0
7 21MS169 0
Certification:
Sys/Eq. Desc DA I EXHAUST SILENCER - 2A DIESEL DA I EXPANSION TANK - 2A DIESEL DA I EXHAUST SILENCER - 2B DIESEL DA I EXPANSION TANK-2B DIESEL DA I EXHAUST SILENCER - 2C DIESEL DA I EXPANSION TANK - 2C DIESEL OF I NO. 2A DIESEL FUEL OIL DAY TANK DF I NO. 2B DIESEL FUEL OIL DAY TANK OF I NO. 2C DIESEL FUEL OIL DAY TANK SW/ 21 CH CNDSR RECIRC PUMP SW/ 22 CH CNDSR RECIRC PUMP SW I 23 CH CNDSR RECIRC PUMP CH I 21 CH WTR PMP CH I 22 CH WTR PMP MS I MS POWER RELIEF VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS/MS ISOLV MS I MS ISO V STEAM ASSIST SALEM NUCLEAR GEN.G STATION - UNIT 1 SCREENING VERIFICATION DATA SHEET (SVDS)
Bldg.
FIEI.
Rm orRw/CI Aux2 122.00 2AD/G Rm Aux2 122.00 2AD/G Rm Aux2 122.00 22 DIG Exhst Fan Rm/2B Day Tnk Aux2 122.00 2B D/G Rm Aux2 122.00 23 D/G Exhst Fan Rm/2C Day Tnk Aux2 122.00 23 D/G Exhst Fan Rm/2C Day Tnk Aux2 122.00 21 D/G Exhst Fan Rm/2C Day Tnk Aux2 122.00 23 D/G Exhst Fan Rm/2C Day Tnk Aux2 122.00 23 D/G Exhst Fan Rm/2C Day Tnk IPA2 100.00 CH Wtr Pmp Area IPA2 100.00 CH Wtr Pmp Area IPA2 100.00 CH Wtr Pmp Area IPA2 100.00 CH Wtr Pmp Area IPA2 100.00 CH Wtr Pmp Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area Cert1ficat1on:
.Page#7/25 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
122.00 N/A DOC RRS Yes Yes Yes Yes Yes 122.00 N/A DOC RRS Yes Yes Yes Yes Yes 122.00 NIA DOC RRS Yes Yes Yes Yes Yes 122.00 N/A DOC RRS Yes Yes Yes Yes Yes 122.00 N/A DOC RRS Yes Yes Yes Yes Yes 122.00 N/A DOC RRS Yes Yes Yes Yes Yes 122.00 N/A DOC RRS Yes Yes Yes Yes Yes 122.00 N/A DOC RRS Yes Yes Yes Yes Yes 122.00 N/A DOC RRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes N/A Yes Yes 100.00 Yes BS.
GRS Yes Yes N/A Yes Yes 100.00 Yes BS GRS Yes Yes N/A Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes N/A Yes Yes 100.00 Yes BS GRS Yes Yes N/A Yes Yes 100.00 N/A DOC RRS Yes Yes N/A Yes Yes 100.00 Yes BS GRS Yes Yes N/A Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All Information" includes each entry and of the equipment c<>ntained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRD are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude I ~ /h.j96u. ~~
I 04120195 Steve Anagnostis 4~
I(
Signature Date Print or Type Name Signature 04/20/95 Print or Type Name Date Print or Type Name Signature Date Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
..Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04120195 o *.
v1 Eq.
Eq. ID Rev Cl No 7
21MS171 o
7 21SW92 o
7 21SW93 o
7 22MS10 o
7 22MS11 0
7 22MS12 0
7 22MS13 o
7 22MS14 o
7 22MS15 0
7 22MS167 o
7 22MS169 o
7 22MS171 0
7 22SW92 o
7 22SW93 o
7 23MS10 o
7 23MS11 0
7 23MS12 o
7 23MS13 o
7 23MS14 o
7 23MS15 0
7 23MS167 o
7 23MS169 0
7 23MS171 0
7 23SW92 o
7 24MS10 o
7 24MS11 0
7 24MS12 o
Certification:
SyslEq. Desc MS I MS ISO V STEAM ASSIST SW I CH CNDSR SW CONT V SW I 21 CH CNDSR SW RECIRC V MS I MS POWER RELIEF VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS/MS ISOLV MS I MS ISO V STEAM ASSIST MS I MS ISO V STEAM ASSIST SW I CH CNDSR SW CONT V SW I 22 CH CNDSR SW RECIRC V MS I MS POWER RELIEF VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS/MS ISOLV MS I MS ISO V STEAM ASSIST MS I MS ISO V STEAM ASSIST SW I CH CNDSR SW CONT V MS I MS POWER RELIEF VLV MS I MS SAFETY VLV MS I MS SAFETY VL V SALEM NUCLEAR GE...
G STATION - UNIT 1.
SCREENING VERIFICATION DATA SHEET (SVDS)
Bldg.
FIEI.
Rm or RwlCI IPA2 100.00 MS Pen Area IPA2 100.00 CH Wtr Pmp Area IPA2 100.00 CH Wtr Pmp Area OPA2 100.00 MS Pen Area OPA2 100.00 MS Pen Area OPA2 100.00 MS Pen Area OPA2 100.00 MS Pen Area OPA2 100.00 MS Pen Area OPA2 100.00 MS Pen Area OPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 CH Wtr Pmp Area IPA2 100.00 CH Wtr Pmp Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 CH Wtr Pmp Area OPA2 100.00 MS Pen Area OPA2 100.00 MS Pen Area OPA2 100.00 MS Pen Area Certification:
Page#B/25 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 NIA ABS CRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes*
Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 N/A DOC RRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 NIA ABS CRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 NIA DOC RRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes
.BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All Information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRn are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude I c. /YI. /)6w.-~.4J.-
04/20/95 Print or Type Name Date Steve Anagnostis Print or Type Name Print or Type Name Signature Date Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
-Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04/20/95 OS **
Eq.
Eq. ID Rev Cl No 7
24MS13 0
7 24MS14 0
7 24MS15 0
7 24MS167 0
7 24MS169 0
7 24MS171 0
7 2CH168 0
9 2VHE25 0
9 2VHE26 0
9 2VHE27 0
10 2VHE315 0
10 2VHE811 0
11 2CHE17 0
11 2CHE18 0
11 2CHE19 0
12 2CAE5 0
17 2DAE23 0
17 2DAE38 0
17 2DAE4 0
18 684-2A 0
18 684-2B 0
18 684-2C 0
Certification:
Sys/Eq. Desc MS I MS SAFETY VLV MS I MS SAFETY VLV MS I MS SAFETY VLV MS/MS ISOLV MS I MS ISO V STEAM ASSIST MS I MS ISO V STEAM ASSIST CH I EMER NC COIL RET CONT V VH I 2A D/G AREA SUPPLY FAN VH I 2B D/G AREA SUPPLY FAN VH I 2C D/G AREA SUPPLY FAN VH / 2 CONTRL AREA VENT EMER AIR FL TR COOLING COIL VH I 2 CONTRL AREA VENT SWGR RM SUP FAN FILTER ENCLOSURE CH I 21 CHILLER CH I 22 CHILLER CH I 23 CHILLER CH / 2 ECAC LP & HP CYL COOLING EP I NO. 2B DIESEL GENERATOR EP I NO. 2C DIESEL GENERATOR EP I NO. 2A DIESEL GENERATOR MS 121 MN STM & TRB BY PASS STM GEN PRESS CONTRL PNL MS 122 MN STM & TRB BY PASS STM GEN PRESS CONTRL PNL MS I 23 MN STM & TRB BY PASS STM GEN PRESS CONTRL PNL SALEM NUCLEAR GEN *
.; STATION - UNIT 1 SCREENING VERIFICATIO ATA SHEET (SVOS)
Bldg.
FIEI.
RmorRw/CI OPA2 100.00 MS Pen Area OPA2 100.00 MS Pen Area OPA2 100.00 MS Pen Area OPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area Aux2 122.00 CRNCRm Aux2 122.00 2AD/G Rm Aux2 122.00 2B D/G Rm Aux2 122.00 2C DIG Rm Aux2 122.00 CRNCRm IPA2 100.00 CH Wtr Pmp Area IPA2 100.00 CH Wtr Pmp Area IPA2 100.00 CH Wtr Pmp Area IPA2 100.00 CH Wtr Pmp Area IPA2 100.00 CH Wtr Pmp Area Aux2 100.00 2BDIG Rm Aux2 100.00 2C DIG Rm Aux2 100.00 2ADIGRm IPA2 100.00 MS Pen Area OPA2 100.00 MS Pen Area IPA2 100.00 MS Pen Area Certification:
age#9/25 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes N/A Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 NIA DOC RRS Yes Yes N/A Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes N/A Yes Yes 122.00 Yes BS GRS Yes Yes NIA Yes Yes 122.00 NIA ABS CRS Yes Yes Yes Yes Yes 122.00 N/A ABS CRS Yes Yes Yes Yes Yes 122.00 N/A ABS CRS Yes Yes Yes Yes Yes 140.00 N/A ABS CRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 N/A ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 N/A ABS CRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 N/A ABS CRS Yes No Yes Yes No 100.00 NIA ABS CRS Yes No Yes Yes No 100.00 NIA ABS CRS Yes No Yes Yes No 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the-Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude c,
04/20/95 Print or Type Name Date Print or Type Name Signature Date Steve Anagnostis 04120195 Print or Type Name Date Print or Type Name Signature Date*
Print or Type Name Signature Date Print or Type Name Signature Date
04/20/95 08.
SALEM NUCLEAR GEN.G STATION* UNIT 1 SCREENINC VERIFICATION DATA SHEET (SVDS)
.age#10/25 Eq.
Eq. ID Rev Sys/Eq. Desc Bldg.
FIEI.
Cl No 18 684-2D 0 MS I 24 MN STM & TRB BY PASS STM GEN OPA2 100.00 PRESS CONTRL PNL 18 685-2A 0 MS/ 21 MN STM & TRB BY PASS STM GEN IPA2 100.00 OUTLET HEAD PRESS CONTRL PNL 18 685-2B 0
MS I 22 MN STM & TRB BY PASS STM GEN OPA2 100.00 OUTLET HEAD PRESS CONTRL PNL 18 685-2C 0
MS I 23 MN STM & TRB BY PASS STM GEN IPA2 100.00 OUTLET HEAD PRESS CONTRL PNL 18 685-2D 0
MS I 24 MN STM & TRB BY PASS STM GEN OPA2 100.00 OUTLET HEAD PRESS CONTRL PNL 18 686-2A 0
MS I 21 MN STM & TRB BY PASS STM GEN IPA2 100.00 STM OUTLET HEAD PRESS CONTRL PNL 18 686-2B 0
MS I 22 MN STM & TRB BY PASS STM GEN OPA2 100.00 STM OUTLET HEAD PRESS CONTRL PNL 18 686-2C 0
MS I 23 MN STM & TRB BY PASS STM GEN IPA2 100.00 STM OUTLET HEAD PRESS CONTRL PNL 18 686-2D 0
MS I 24 MN STM & TRB BY PASS STM GEN OPA2 100.00 STM OUTLET HEAD PRESS CONTRL PNL 20 2R11 0
EP I 2 4KV 2CDD, 21 CSD & 22CSD BKR Aux2 100.00 FAIL PROT RELAY RACK 2R11 PANEL 20 2R24 0
EP / 2 4KV VITAL BUS 2800, 21 BSD &
Aux2 100.00 22BSD BKR FAIL PROT RELAY RACK 20 2R8 0
EP I 2 4KV 2ADD, 21ASD & 22ASD BKR Aux2 100.00 FAIL PROT RELAY RACK 2R8 (PANEL) 20 407-2 0 VH I 2 CONTRL AREA VEN CONT RM AC Aux2 122.00 CONTPNL 20 RC21-3 0
EP I 21 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC21-3 Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
RmorRw/CI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
MS Pen Area 100.00 Yes BS GRS
. Yes Yes Yes Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes Yes Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes Yes Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes Yes Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes Yes Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes Yes Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes Yes Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes Yes Yes Yes MS Pen Area 100.00 Yes BS GRS Yes Yes Yes Yes Yes 2 Relay Rm 100.00 N/A ABS CRS Yes Yes Yes Yes Yes 2 Relay Rm 100.00 N/A ABS CRS Yes Yes Yes*
Yes Yes 2 Relay Rm 100.00 NIA ABS CRS Yes Yes Yes Yes Yes CRNCRm 122.00 N/A ABS CRS Yes Yes Yes Yes Yes 2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the
-Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude 04/20/95 Print or Type Name Date Print or Type Name Signature Date Steve Anagnostis 04/20/95 Print or Type Name Date Print or Type Name Signature Date*
Print or Type Name Signature Date Print or Type Name Signature Date
SALEM NUCLEAR GE.ING STATION - UNIT 1 SCREENIN'G VERIFICATION DATA SHEET (SVDS)
Page# 11125 Eq.
Eq. ID Rev Sys/Eq. Desc Bldg.
FIEI.
Cl No 20 RC21-4 0
EP / 21 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC21-4 20 RC21-5 0
EP / 21 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC21-5 20 RC21-6 0
EP / 21 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC21-6 20 RC21-7 0
EP / 21 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC21-7 20 RC22-3 0
EP / 22 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC22-3 20 RC22-4 0
EP I 22 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC22-4 20 RC22-5 0
EP I 22 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC22-5 20 RC22-6 0
EP I 22 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC22-6 20 RC22-7
- o. EP I 22 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC22-7 20 RC23-3 0
EP I 23 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC23-3 20 RC23-4 0
EP I 23 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC23-4 20 RC23-5 0
EP / 23 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC23-5 20 RC23-6 0
EP I 23 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC23-6 20 RC23-7 0
EP / 23 AUX CONTROL SYSTEM RELAY Aux2 100.00 CABINET RC23-7 Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Rm orRw/CI Base EL <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No 2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No 2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No 2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No 2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No 2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No 2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No 2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No 2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No 2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No 2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No 2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No 2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No 2 Relay Rm 100.00 Yes BS GRS Yes No Yes No No Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the
-Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude I a, /J?.;Q&k~ I 04/20/95 Print or Type Name
~
'S~natu"'
Date Print or Type Name Signature Date Steve Anagnostis
~
04/20/95 7
~~
Print or Type Name Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04/20/95 08.
Eq.
Eq. ID Rev Cl No 20 RC24-3 0
20 RC24-5 0
20 RC24-6 0
20 RC24-7 0
20 RC25-3 0
20 RC25-4 0
20 RC25-6 0
20 RC25-7 0
20 RC26-5 0
20 RC26-6 0
20 RC26-7 0
20 RC28-4 0
20 RC28-5 0
20 RC28-6 0
Certification:
Sys/Eq. Desc EP I 24 AUX CONTROL SYSTEM RELAY CABINET RC24-3 EP I 24 AUX CONTROL SYSTEM RELAY CABINET RC24-5 EP I 24 AUX CONTROL SYSTEM RELAY CABINET RC24-6 EP / 24 AUX CONTROL SYSTEM RELAY CABINET RC24-7 EP / 25 AUX CONTROL SYSTEM RELAY CABINET RC25-3 EP I 25 AUX CONTROL SYSTEM RELAY CABINET RC25-4 EP I 25 AUX CONTROL SYSTEM RELAY CABINET RC25-6 EP / 25 AUX CONTROL SYSTEM RELAY CABINET RC25-7 EP I 26 AUX CONTROL SYSTEM RELAY CABINET RC26-5 EP I 26 AUX CONTROL SYSTEM RELAY CABINET RC26-6 EP I 26 AUX CONTROL SYSTEM RELAY CABINET RC26-7 EP I 28 AUX CONTROL SYSTEM RELAY CABINET RC28-4 EP / 28 AUX CONTROL SYSTEM RELAY CABINET RC28-5 EP / 28 AUX CONTROL SYSTEM RELAY CABINET RC28-6 SALEM NUCLEAR GE-~G STATION - UNIT 1 SCREENING VERIFICATION DATA SHEET {SVDS)
Bldg.
FIEI.
Rm orRw/CI Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Certification:
Page# 12125 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
100.00 Yes BS GRS Yes Yes Yes No No 100.00 Yes BS GRS Yes Yes Yes No No 100.00 Yes BS GRS Yes Yes Yes No No 100.00 Yes BS GRS Yes Yes Yes No No 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes Yes Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude I c. /rJ.;f)~ J~
04/20/95 Print or Type Name Steve Anagnostis Print or Type Name Print or Type Name Signature Date Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
-Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Print or Type Name Signature Date
04120195 0 *.
.11 SALEM NUCLEAR GE *
. 4G STATION* UNIT 1 SCREENING VERIFICATION DATA SHEET (SVDS)
'age# 13/25 Eq.
Cl Eq. ID Rev No Sys/Eq. Desc Bldg.
Fl El.
Rm orRw/CI Base El. <40'? Cap.
Demd. Cap > Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
(This page is intentionally left blank)
Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the
-Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude I c. ff7.;{)&-JL.-..t--....
04/20/95 Print or Type Name rsignature Date Print or Type Name Signature Date Steve Anagnostis
~z:;::=a 04/20/95 Print or Type Name
~Signature Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
Eq.
Eq. ID Rev Cl No 0
2DAE25 0
0 2DAE26 0
0 2DAE39 0
0 2DAE40 0
0 2DAE5 0
0 2DAE6 0
7 21SW39 0
7 21SW42 0
7 22SW39 0
7 22SW42 0
7 23SW39 0
7 23SW42 0
20 EC-2A 0
20 EC-2B 0
20 EC-2C 0
Certification:
Sys/Eq. Desc DA I 22A DIESEL START AIR RCVR DA I 22B DIESEL START AIR RCVR DA/ 23A DIESEL START AIR RCVR DA/ 23B DIESEL START AIR RCVR DA I 21A DIESEL START AIR RCVR DA 121 B DIESEL START AIR RCVR SW 12 A DIESEL CLG SW SW I 2,.A DIESEL CLG SW TH ROT V SW I 2B DIESEL CLG SW SW I 2B DIESEL CLG SW THROT V SW I 2C DIESEL CLG SW SW I 2C DIESEL CLG SW EP I EXCITER CABINET - 2A EP I EXCITER CABINET* 2B EP I EXCITER CABINET* 2C SALEM NUCLEAR GE *.*
G STATION* UNIT 1 SCREENIN(; VERIFICATION DATA SHEET (SVDS)
Bldg.
Fl El.
Rm orRw/CI Aux2 100.00 2B D/G Rm Aux2 100.00 2B D/G Rm Aux2 100.00 2C DIG Rm Aux2 100.00 2C DIG Rm Aux2 100.00 2AD/G Rm Aux2 100.00 2ADIG Rm Aux2 100.00 2AD/G Rm Aux2 100.00 2AD/G Rm Aux2 100.00 2B DIG Rm Aux2 100.00 2B DIG Rm Aux2 100.00 2C D/G Rm Aux2 100.00 2C DIG Rm Aux2 100.00 2AD/G Rm Aux2 100.00 2B D/G Rm Aux2 100.00 2C DIG Rm Certification:
age#14/25 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
100.00 NIA DOC RRS Yes Yes Yes Yes Yes 100.00 N/A DOC RRS Yes Yes Yes Yes Yes 100.00 NIA DOC RRS Yes Yes Yes Yes Yes 100.00 NIA DOC RRS Yes Yes Yes Yes Yes 100.00 NIA DOC RRS Yes Yes Yes Yes Yes 100.00 NIA DOC RRS Yes Yes Yes Yes Yes 100.00 Yes BS GRS Yes Yes N/A Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 Yes BS GRS Yes Yes N/A Yes Yes 100.00 Yes BS GRS Yes Yes NIA Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes All the information contained on this Screening Verification Data Sheef.(SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS Is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the
-Engineers deem it necessary.)
entries and conclusions. One signatory sh Id be a licensed professio al engineer.)
Jim Flaherty 04120195 Print or Type Name Date Print or Type Name Signature Date Steve Anagnostis 04120195 Print or Type Name Date Print or Type Name Signature Date*
Print or Type Name Signature Date Print or Type Name Signature Date
04120195 08.
Eq.
Eq. ID Rev Cl No 2
2SWGR2ADC 0
2 2SWGR2BDC 0
2 2SWGR2C9X 0
2 2SWGR2CDC 0
5 2AFE6 0
7 23AF21 0
7 2MS132 0
7 2MS53 0
14 2ADE 0
14 2CDE 0
14 2DDC 0
15 2BTRY2CDC 0
16 2BTRY2A10Y 0
16 2BTRY2B10Y 0
16 2BTRY2C12Y 0
20 230-2 0
Certification:
SyslEq. Desc EP I NO 2A 125VDC BUS EP I NO 2B 125VDC BUS EP I NO 2C 460V VITAL BUS EXTENSION EP I NO 2C 125VDC BUS AF I 23 AUX FEED PMP AF I AUX FEED - SIG LEVEL CONTROL V MS/ 23 AF PMP TURB START/STOP V MS / 23 AF PMP TURB GOV EP I NO 2A 28VDC CONTROL BUS EP I NO 2C 28VDC CONTROL BUS EP / 125VDC DISTRIBUTION CABINET EP I NO 2C 125VDC BATTERY EP I NO 2A1125VDC BATTERY CHARGER EP I NO 2B1125VDC BATTERY CHARGER EP I NO 2C1 125VDC BATTERY CHARGER VH I 2 AUX BLDG VENT SWGR RM INST PANEL SALEM NUCLEAR GE.G STATION - UNIT 1 SCREENIN~ VERIFICATION DATA SHEET (SVDS)
Bldg.
Fl El.
Rm orRwlCI Aux2 84.00 4601230V Vital 1251250DC Bat Aux2 84.00 4601230V Vital 1251250DC Bat Aux2 84.00 4601230V Vital 1251250DC Bat Aux2 84.00 4601230V Vital 1251250DC Bat Aux2 84.00 23 Aux Fd Pmp Rm Aux2 84.00 23 Aux Fd Pmp Rm Aux2 84.00 23 Aux Fd Pmp Rm Aux2 84.00 23 Aux Fd Pmp Rm Aux2 84.00 4601230V Vital 125/250DC Bat Aux2 84.00 4601230V Vital 125/250DC Bat Aux2 84.00 460/230V Vital 125/250DC Bat Aux2 64.00 C Bat Rm; Vital Bus Area Aux2 84.00 4601230V Vital 1251250DC Bat Aux2 84.00 4601230V Vital 1251250DC Bat Aux2 84.00 4601230V Vital 125/250DC Bat Aux2 84.00 460/230V Vital 125/250DC Bat Certification:
.r'age # 15125 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 64.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 84.00 N/A ABS CRS Yes Yes N/A Yes Yes 84.00 N/A ABS CRS Yes Yes N/A Yes Yes 84.00 N/A ABS CRS Yes No Yes Yes No 84.00 NIA ABS CRS Yes No Yes Yes No 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 64.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All Information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the Engineers deem it necessary.)
entries and conclusions. One signatory should be a lie ed p fessional engineer.)
Walter Djordjevic 04120195 Print or Type Name Date Print or Type Name Signature Date Aziz Saber 04/20195 Print or Type Name Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04/20/95 O.M SALEM NUCLEAR GE.ING STATION* UNIT 1 SCREENIN'G VERIFICATION DATA SHEET (SVDS)
~age# 16125 Eq.
Cl Eq. ID Rev No Sys/Eq. Desc Bldg.
Fl El.
Rm orRw~CI Base El. <40'? Cap.
Demd. Cap > Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
(This page is intentionally left blank)
Certification:
Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT.
II si natories should agree with all the entries and conclusions. One signatory should be a )ic;n7 ofess*
engineer.)
Walter Djordjevic N /1 04/20/95 Aziz Saber.
04/20/95 Print or Type Name Signature Date Print or Type Name Signature Date Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
-Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
041201950.
Eq.
Eq. ID Rev Cl No 2
2SWGR2AX 0
2 2SWGR2AY 0
2 2SWGR2BX 0
2 2SWGR2BY 0
2 2SWGR2CX 0
2 2SWGR2CY 0
3 2SWGR2AD 0
3 2SWGR2BD 0
3 2SWGR2CD 0
4 2XFR2A4DAX 0
4 2XFR2A4DBY 0
4 2XFR2B4DAX 0
4 2XFR2B4DBY 0
4 2XFR2C4DA 0
x Certification:
SyslEq. Desc EP I NO 2A 460V VITAL BUS EP I NO 2A 230V VITAL BUS EP I NO 2B 460V VITAL BUS EP I NO 2B 230V VITAL BUS EP I NO 2C 460V VITAL BUS EP I NO 2C 230V VITAL BUS EP I NO 2A 4160V VITAL BUS EP I NO 2B 4160VVITAL BUS EP I NO 2C 4160V VITAL BUS EP I TRANSFORMER TO NO. 2A 460V VITAL BUS 2SWGR2AX EP I TRANSFORMER TO NO. 2A 230V VITAL BUS 2SWGR2AY EP I TRANSFORMER TO NO. 2B 460V VITAL BUS 2SWGR2BX EP I TRANSFORMER TO NO. 2B 230V VITAL BUS 2SWGR2BY EP I TRANSFORMER TO NO. 2C 460V VITAL BUS 2SWGR2CX SALEM NUCLEAR GE.lllG STATION* UNIT 1 SCREENING VERIFICAT DATA SHEET (SVDS)
Bldg.
Fl El.
Rm orRwlCI Aux2 84.00 460/230V Vital 125/250DC Bat Aux2 84.00 460/230V Vital 125/250DC Bat Aux2 84.00 460/230V Vital 125/250DC Bat Aux2 84.00 460/230V Vital 125/250DC Bat Aux2 84.00 460/230V Vital 125/250DC Bat Aux2 84.00 460/230V Vital 125/250DC Bat Aux2 64.00 4 KV Vital Bus & Bat Rm Aux2 64.00 4 KV Vital Bus & Bat Rm Aux2 64.00 4 KV Vital Bus & Bat Rm Aux2 84.00 460/230V Vital 125/250DC Bat Aux2 84.00 460/230V Vital 125/250DC Bat Aux2 84.00 460/230V Vital 125/250DC Bat Aux2 84.00 460/230V Vital 125/250DC Bat Aux2 84.00 4601230V Vital 125/250DC Bat Certification:
-~age# 17/25 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 N/A ABS CRS Yes Yes Yes Yes Yes 84.00 N/A ABS CRS Yes Yes Yes Yes Yes 84.00 N/A ABS CRS Yes Yes Yes Yes Yes 64.00 N/A ABS CRS Yes Yes Yes Yes Yes 64.00 N/A ABS CRS Yes Yes Yes Yes Yes 64.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 N/A ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 84.00 NIA ABS CRS Yes Yes Yes Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the, Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude 04/20/95 Print or Type Name Date Print or Type Name Signature Date Jim Flaherty 04/20/95 Print or Type Name Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
041201950 *
.il Eq.
Eq. ID Rev Cl No 4
2XFR2C4DB 0
y 7
2CV114 0
7 2CV2 0
7 2CV277 0
7 2PR1 0
7 2PR2 0
7 2PR3 0
7 2PR4 0
7 2PR5 0
8 21SJ54 0
8 22SJ54 0
8 23SJ54 0
8 24SJ54 0
8 2PR6 0
8 2PR7 0
8 2RH2 0
8 2SV1198 0
8 2SV1199 0
9 2VHE15 0
9 2VHE16 0
9 2VHE17 0
9 2VHE18 0
9 2VHE19 0
10 2SWE24 0
10 2SWE25 0
10 2SWE26 0
Certification:
SyslEq. Desc EP I TRANSFORMER TO NO. 2C 230V VITAL BUS 2SWGR2CY RC I RCP SEAL BYPASS STOP V CV I LETDOWN LINE ISOL VLV CV I L TOWN LINE ISOL V PR I PZR PWR OP RELIEF V PR I PZR PWR OP RELIEF V PR I PRESSURIZER RELIEF VALVE PR I PRESSURIZER RELIEF VALVE PR I PRESSURIZER RELIEF VALVE SJ I ACCUM OUTLET VALVE SJ I ACCUM OUTLET VALVE SJ I ACCUM OUTLET VALVE SJ I ACCUM OUTLET VALVE PR I PZR PWR OP RELIEF STOP V PR I PZR PWR OP RELIEF STOP V RH I RHR COMMON SUCT V PR I PORV ACCUM OUTLET SOL VLV PR I PORV ACCUM OUTLET SOL VLV VH I 21 CFCU FAN VH I 22 CFCU FAN VH 123 CFCU FAN VH I 24 CFCU FAN VH I 25 CFCU FAN SWl21 FCU SWl22 FCU SWl23FCU SALEM NUCLEAR GE *.
lG STATION - UNIT 1 SCREENING VERIFICATION DATA SHEET (SVDS)
Bldg.
FIEI.
Rm orRwlCI Aux2 64.00 4 KV Vital Bus & Bat Rm Cntmnt 2 78.00 Cor at Elevator Cntmnt2 78.00 Regen Hx Rm Cntmnt 2 78.00 Regen Hx Rm Cntmnt 2 130.00 2 PzrArea Cntmnt 2 130.00 2 PzrArea Cntmnt 2 130.00 2 PzrArea Cntmnt 2 130.00 2 PzrArea Cntmnt2 130.00 2 PzrArea Cntmnt2 78.00 21 Accumulator Cntmnt2 78.00 22 Accumulator Cntmnt 2 78.00 23 Accumulator Cntmnt 2 78.00 24 Accumulator Cntmnt 2 130.00 2 PzrArea Cntmnt2 130.00 2 PzrArea Cntmnt2 78.00 Cor at Elevator Cntmnt 2 130.00 2 PzrArea Cntmnt 2 130.00 2 PzrArea Cntmnt 2 130.00 21 CFCU Cntmnt2 130.00 22 CFCU Cntmnt2 130.00 23 CFCU Cntmnt2 130.00 24 CFCU Cntmnt 2 130.00 25 CFCU Cntmnt 2 130.00 21 CFCU Cntmnt 2 130.00 22CFCU Cntmnt 2 130.00 23CFCU Certification:
- age#18/25 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
64.00 NIA ABS CRS Yes Yes Yes Yes Yes 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 130.00 NIA ABS CRS Yes Yes NIA Yes Yes 130.00 NIA ABS CRS Yes Yes NIA Yes Yes 130.00 NIA ABS CRS Yes Yes NIA Yes Yes 130.00 NIA ABS CRS Yes Yes NIA Yes Yes 130.00 NIA ABS CRS Yes Yes NIA Yes Yes 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 130.00 NIA ABS CRS Yes Yes NIA Yes Yes 130.00 NIA ABS CRS Yes Yes NIA Yes Yes 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 130.00 NIA ABS CRS Yes Yes NIA Yes Yes 130.00 NIA ABS CRS Yes Yes NIA Yes Yes 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 130.00 NIA ABS CRS Yes Yes Yes Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the, Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude 04120195 Print or Type Name 1
Signature Date Print or Type Name Signature Date Jim Flaherty 04120195 Print or Type Name Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
041201950 *.
.A Eq.
Eq.10 Rev Cl No 10 2SWE27 0
10 2SWE28 0
14 2DIS2A5YA 0
14 2DIS2B11YA 0
14 2DIS2B5YA 0
14 2DIS2C5YA 0
15 2BTRY2ADC 0
15 2BTRY2ADE 0
15 2BTRY2BDC 0
15 2BTRY2BDE 0
16 2BTRY2A12Y 0
16 2BTRY2B14Y 0
16 21NV2A5YB 0
16 21NV2B11YB 0
16 21NV2B5YB 0
16 21NV2C5YB 0
16 21NV2C6YC 0
18 2PD9859 0
18 2PD9860 0
18 440-2A 0
Certification:
SyslEq. Desc SWl24 FCU SWl25 FCU EP I NO 2A VITAL INSTRUMENT BUS (115V)
EP I NO 2D VITAL INSTRUMENT BUS (115V)
EP I NO 2B VITAL INSTRUMENT BUS (115V)
EP I NO 2C VITAL INSTRUMENT BUS (115V)
EP I NO 2A 125VDC BATTERY EP I NO 2A 28VDC BATTERY EP I NO 2B 125VDC BATTERY EP I NO 2B 28VDC BATTERY EP I NO 2A1 28VDC BATTERY CHARGER EP I NO 2B1 28VDC BATTERY CHARGER EP I NO 2A VITAL INSTRUMENT INVERTER EP I NO 20 VITAL INSTRUMENT INVERTER EP I NO 2B VITAL INSTRUMENT INVERTER EP I NO 2C VITAL INSTRUMENT INVERTER EP I NO 21 & 22 STATION ESSENTIAL CONTROL INVERTER PR I PRESSURE SWITCH FOR 2SV1198 PR I PRESSURE SWITCH FOR 2SV1199 VH I 21 CNTMNT VENT FCU DAMPER CONTRLPNL SALEM NUCLEAR GE *.*
G STATION - UNIT 1 SCREENING VERIFICATION DATA SHEET (SVDS)
Bldg.
FIEI.
Rm orRwlCI Cntmnt2 130.00 24CFCU Cntmnt 2 130.00 25CFCU Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 125 VDC Bat Rm Aux2 100.00 125 voe Bat Rm Aux2 100.00 2B 125V Bat Rm (South)
Aux2 100.00 28 125V Bat Rm (South)
Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Aux2 100.00 2 Relay Rm Cntmnt 2 130.00 2 Pzr Area Cntmnt 2 130.00 2 Pzr Area Cntmnt 2 130.00 21 CFCU Certification:
- age# 19125 Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
130.00 NIA ABS CRS Yes Yes Yes Yes Yes 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes No Yes No No 100.00 NIA ABS CRS Yes No Yes No No 100.00 NIA ABS CRS Yes No Yes No No 100.00 NIA ABS CRS Yes No Yes No No 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes Yes Yes 100.00 NIA ABS CRS Yes Yes Yes No No 100.00 NIA ABS CRS Yes Yes Yes No No 100.00 NIA ABS CRS Yes Yes Yes No No 100.00 NIA ABS CRS Yes Yes Yes No No 100.00 NIA ABS CRS Yes Yes Yes No No 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 130.00 NIA ABS CRS Yes Yes Yes Yes Yes All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of The information provided to the Seismic Capability Engineers regarding systems and operations our knowledge and belief, correct and accurate. "All information" includes each entry and of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and conclusion (whether verified to be seismically adequate or not).
accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professional engineer.)
I e. I??. ~
.Jl-..(..L..._ I 04120195 Charbel Abou-Jaoude Print or Type Name Jim Flaherty 04120195 Print or Type Name Date Print or Type Name Signature Date Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
-Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04120195 O.M SALEM NUCLEAR GE.ING STATION* UNIT 1 SCREENl~G VERIFICATION DATA SHEET (SVDS)
Page# 20125 Eq.
Eq. ID Rev SyslEq. Desc Bldg.
Fl El.
Cl No 18 440-2B 0 VH I 22 CNTMNT VENT FCU DAMPER Cntmnt 2 130.00 CONTRLPNL 18 440-2C 0 VH I 23 CNTMNT VENT FCU DAMPER Cntmnt 2 130.00 CONTRL PNL 18 440-2D 0 VH I 24 CNTMNT VENT FCU DAMPER Cntmnt 2 130.00 CONTRL PNL 18 440-2E 0 VH 125 CNTMNT VENT FCU DAMPER Cntmnt 2 130.00 CONTRLPNL 18 444-2A 0 AF I 21 SIG FEED & COND PNL NARROW Cntmnt 2 130.00 RANGE 1 18 444-2B 0 AF 121 SIG FEED & COND PNL NARROW Cntmnt 2 130.00 RANGE2 18 444-2C 0 AF 121 SIG FEED & COND PNL NARROW Cntmnt 2 130.00 RANGE3 18 444-2D 0 AF 122 SIG FEED & COND PNL NARROW Cntmnt 2 130.00 RANGE 1 18 444-2E 0 AF 122 SIG FEED & COND PNL NARROW Cntmnt 2 130.00 RANGE2 18 444-2F 0 AF I 22 SIG FEED & COND PNL NARROW Cntmnt2 130.00 RANGE3 18 444-2G 0 AF I 23 SIG FEED & COND PNL NARROW Cntmnt 2 130.00 RANGE 1 18 444-2H 0 AF I 23 SIG FEED & COND PNL NARROW Cntmnt2 130.00 RANGE2 18 444-2J 0 AF I 23 SIG FEED & COND PNL NARROW Cntmnt 2 130.00 RANGE3 18 444-2K 0 AF 124 SIG FEED & COND PNL NARROW Cntmnt2 130.00 RANGE 1 Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Rm orRwlCI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
22 CFCU 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 23CFCU 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 24CFCU 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 25 CFCU 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 21 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 21 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 21 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 22 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 22 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 22 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 23 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 23 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 23 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 24 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the, Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude 04120195 Print or Type Name Date Print or Type Name Signature Date Jim Flaherty 04120195 Print or Type Name Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04120195.M SALEM NUCLEAR G.nNG STATION - UNIT 1 SCREENl~G VERIFICATION DATA SHEET (SVDS)
Page#21125 Eq.
Eq. ID Rev SyslEq. Desc Bldg.
FIEI.
Cl No 18 444-2L 0 AF I 24 SIG FEED & COND PNL NARROW Cntmnt 2 130.00 RANGE 2 18 444-2M 0 AF I 24 SIG FEED & COND PNL NARROW Cntmnt 2 130.00 RANGE 3 19 2TE413A 0
RC I TEMPERATURE ELEMENT, RCS LOOP Cntmnt 2 78.00 21 HOT LEG 19 2TE413B 0
RC I TEMPERATURE ELEMENT, RCS LOOP Cntmnt 2 78.00 21 COLD LEG 19 2TE423A 0
RC I TEMPERATURE ELEMENT, RCS LOOP Cntmnt 2 78.00 22 HOT LEG 19 2TE423B 0
RC I TEMPERATURE ELEMENT, RCS LOOP Cntmnt 2 78.00 22 COLD LEG 19 2TE433A 0
RC I TEMPERATURE ELEMENT, RCS LOOP Cntmnt 2 78.00 23 HOT LEG 19 2TE4338 0
RC I TEMPERATURE ELEMENT, RCS LOOP Cntmnt2 78.00 23COLD LEG 19 2TE443A 0 RC /TEMPERATURE ELEMENT, RCS LOOP Cntmnt 2 78.00 24 HOT LEG 19 2TE443B 0 RC I TEMPERATURE ELEMENT, RCS LOOP Cntmnt 2 78.00 24COLD LEG 20 335-2 0 PR I 2 REACT COOL PZR PROTECTION Cntmnt 2 100.00 PANEL Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude I c
- h.;QDz-..J""2c.-~ I 04120195 Print or Type Name Signature Date Jim Flaherty
~Q,'Cf,~
04120195 Print or Type Name Date Print or Type Name Signature Date Rm orRwlCI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
24 SIG Area 130.00 NIA ABS CRS Yes Yes Yes Yes Yes 24 SIG Area 130.00 N/A ABS CRS Yes Yes Yes Yes Yes 21 S/G & RCP Supports 78.00 NIA ABS CRS Yes Yes NIA Yes Yes Area 21 SIG & RCP Supports 78.00 NIA ABS CRS Yes Yes NIA Yes Yes Area 22 SIG & RCP Supports 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 22 SIG & RCP Supports 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 23 SIG & RCP Supports 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 23 SIG & RCP Supports 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 24 SIG & RCP Supports 78.00 NIA ABS CRS Yes Yes NIA Yes Yes 24 SIG & RCP Supports 78.00 NIA ABS CRS Yes Yes NIA Yes Yes Elevator Passage Area 100.00 NIA ABS CRS Yes Yes Yes Yes Yes Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability
, Engineers deem it necessary.)
Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04/20/95 O.M SALEM NUCLEAR GE.ING STATION* UNIT 1 SCREENING VERIFICATION DATA SHEET (SVDS)
Page# 22125 Eq.
Eq. ID Rev Sys/Eq. Desc Bldg.
Fl El.
Cl No 2
2SWGR2EPX 0
EP I NO. 2EP 480V PRESSURIZER HTR Aux2 84.00 BUS (BACK-UP GROUP 2) 2 2SWGR2GPX 0
EP I NO. 2GP 480V PRESSURIZER HTR IPA2 78.00 BUS (BACK-UP GROUP 1)
Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Rm orRw/CI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
460/230V Vital 84.00 N/A ABS CRS Yes Yes Yes Yes Yes 125/250DC Bat A, B, C East Valves CC 78.00 N/A ABS CRS Yes Yes Yes Yes Yes Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the
- Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Charbel Abou-Jaoude
- c. °'. /()t>z.,_,JL..c.,.-_ I 04/20/95 I,
Print or Type Name
' Signature Date Print or Type Name Signature Date Aziz Saber
~A -
04/20/95 Print or Type Name Signature Date Print.or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04120195
- 11.A SALEM NUCLEAR G *.
~G STATION - UNIT 1 SCREENING VERIFICA N DATA SHEET {SVDS)
~age# 23125 Eq.
Eq. ID Rev SyslEq. Desc Bldg.
FIEI.
Cl No 5
2AFE4 0 AF I 21 AUX FEED PMP Aux2 84.00 5
2AFE5 0
AF I 22 AUX FEED PMP Aux2 84.00 5
2CCE2 0
CC I CC PMP NO. 21 Aux2 84.00 5
2CCE3 0
CC I CC PMP NO. 23 Aux2 84.00 5
2CCE4 0 CC I CC PMP NO. 22 Aux2 84.00 5
2CSE1 0 CV I CONTAINMENT SPRAY PUMP, NO. 21 Aux2 84.00 5
2CSE2 0 CV I CONTAINMENT SPRAY PUMP, NO. 22 Aux2 84.00 5
2CVE20 0
121 CHG PMP Aux2 84.00 5
2CVE21 0
CV 122 CHG PMP, CENTRIFUGAL Aux2 84.00 5
2CVE22 0
CV 123 CHARGING PUMP, Aux2 84.00 RECIPROCATING 5
2DFE10 0
DF I NO. 21 DIESEL FUEL OIL TRANSFER Aux2 84.00 PUMP 5
2DFE9 0
DF I N0.22 DIESEL FUEL OIL TRANSFER Aux2 84.00 PUMP 5
2RHE1 0
2RHE2 0
2SJE101 0 SW I 22 SJ PMP LUBE OIL CLR Aux2 84.00 5
2WGE2 0 CC I NO. 21 WASTE GAS COMPRESSOR Aux2 64.00 HX 5
2WGE3 0 CC I NO. 22 WASTE GAS COMPRESSOR Aux2 64.00 HX 7
21AF21 0 AF I AUX FEED - SIG LEVEL CONTROL V Aux2 84.00 7
21RH18 0
RH I 21 RHR HX FLOW CONT V Aux2 45.00 7
21SW122 0 SW I CC HX SW INLET V Aux2 84.00 7
21SW127 0 SW 121 CC HX SW REG VLV Aux2 84.00 7
21SW129 0 SW I 21 CC PMP RM CLR SW CONT V Aux2
- 54_00 7
21SW153 0 SW I 21 RH PMP RM CLR SW CONT V Aux2 45.00 Cert1ficat1on:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
RmorRwlCI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
21 Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 22 Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 21 CC Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 22 CC Hx Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 22 & 23 CC Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 21 Cont Spray Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 21 Cont Spray Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 21 Chrg Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 22 Chrg Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 23 Chrg Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 21 DIF X Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 22 DIF X Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 21 RHRVlv Rm 45.00 NIA ABS CRS Yes Yes Yes Yes Yes 22 RHRVlv Rm 45.00 NIA ABS CRS Yes Yes Yes Yes Yes 22 SI Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 21 Waste Gas Cmpsr 64.00 NIA ABS CRS Yes Yes Yes Yes Yes Rm 22 Waste Gas Cmpsr 64.00 NIA ABS CRS Yes Yes Yes Yes Yes Rm 21 Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 21 RHRPmp Rm 45.00 NIA ABS CRS Yes Yes NIA Yes Yes 21 CCPmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 21 CC Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 21 CC Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 21 RHR Pmp Rm 45.00 NIA ABS CRS Yes Yes NIA Yes Yes Cert1ficat1on.
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the, Engineers deem it necessary.)
entries and conclusions. One signatory should be*a licensed professional engineer.)
Jim Flaherty 04120195 Print or Type Name Signature Date Print or Type Name Signature Date Aziz Saber Af?a~
04120195 Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
04120195 O.vl SALEM NUCLEAR GE **
- G STATION - UNIT 1 SCREENING VERIFICATION DATA SHEET (SVDS)
Eq.
Eq. ID Rev SyslEq. Desc Bldg.
Fl El.
Cl No 7
22AF21 0 AF I AUX FEED - SIG LEVEL CONTROL V Aux2 84.00 7
22RH18 0
RH I 22 RHR HX FLOW CONT V Aux2 45.00 7
22SW122 0 SW 122 CC HX INLET VALVE Aux2 84.00 7
22SW127 0
SW 122 CC HX OUTLET VALVE Aux2 84.00 7
22SW129 0
SW I 22 & 23 CC PMP RM CLR SW CONT V Aux2 84.00 7
22SW153 0
SW I 22 RH PMP RM CLR SW CONT V Aux2 45.00 7
24AF21 0 AF I AUX FEED - SIG LEVEL CONTROL V Aux2 84.00 7
2CV55 0 CV I CENT CHG PMP FCV Aux2 84.00 7
2SW137 0
SW 121 AF PMP RM CLR SW CLR CONT V Aux2 84.00 7
2SW191 0 SW I CHG PMP RM CLR SW CONT V Aux2 84.00 7
2SW205 0
SW I 22CHG PMP LO CLR SW INLET V Aux2 84.00 7
2SW213 0
SW I 21CHG PMP RM CLR SW CONT V Aux2 84.00 8
21CC16 0
CC 121 RHR HEAT EXCHANGER Aux2 55.00 COMPONENT COOLING OUTLET VAVLE (MOV) 8 21CC3 0
CC 121-23 HEADER X-OVER VLV Aux2 84.00 8
22CC16 0
CC 122 RHR HEAT EXCHANGER Aux2 55.00 COMPONENT COOLING OUTLET VAVLE (MOV) 8 22CC3 0
CC 122-23 HEADER X-OVER VLV Aux2 84.00 8
2CC17 0 CC I CC PMP SUCT X-OVER V Aux2 84.00 8
2CC18 0
CC I CC PUMP SUCTION X-OVER VLV Aux2 84.00 8
2SJ1 0
CV I RWST TO CHG PMPS STOP V Aux2 84.00 8
2SJ2 0
CV I RWST TO CHG PMPS STOP V Aux2 84.00 9
2VHE33 0
VH I 21 & 22 CC PMP RM CLR FAN UNIT Aux2 84.00 9
2VHE34 0
VH I 22 & 23 CC PMP RM CLR FAN UNIT Aux2 84.00 9
2VHE36 0
VH I 21 & 22 AUX FEED WTR PMP RM CLR Aux2 84.00 FAN UNIT Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
RmorRwlCI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
22 Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 22RHRPmpRm 45.00 NIA ABS CRS Yes Yes NIA Yes Yes 22 & 23 CC Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 22 & 23 CC Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 21 Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 22 RHRPmp Rm 45.00 NIA ABS CRS Yes Yes NIA Yes Yes 21 Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes Chrg Pmp Viv Alley 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 22 Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes Chrg Pmp Viv Alley 84.00 NIA ABS CRS Yes Yes NIA Yes Yes Chrg Pmp Viv Alley 84.00 NIA ABS CRS.
Yes Yes NIA Yes Yes Chrg Pmp Viv Alley 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 22 RHRVlv Rm 55.00 NIA ABS CRS Yes Yes NIA Yes Yes 21 CC Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 21 RHRVlv Rm 55.00 NIA ABS CRS Yes Yes NIA Yes Yes 22 CC Hx Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 21 CC Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 22 & 23 CC Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes WIM Tk & Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes WIM Tk & Pmp Rm 84.00 NIA ABS CRS Yes Yes NIA Yes Yes 23 Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 22 Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes 22 Aux Fd Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes Cert1ficat1on:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (Signatures of all Seismic Capability E11gineers on the Seismic Review Team (SRT)
Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the*
Engineers deem it necessary.)
entries and conclusions. One signatory should be a* licensed professional engineer.)
Jim Flahert 04120195 Print or Type Name Signature Date Print or Type Name Signature Date Aziz Saber
~
04120195 Print or Type Name Date Print or Type Name Signature Date*
Print or Type Name Signature Date Print or Type Name Signature Date
04/20/95 08.
SALEM NUCLEAR GEN.G STATION - UNIT 1 SCREENING'VERIFICATION DATA SHEET (SVDS)
.age#25/25 Eq.
Eq. ID Rev Sys/Eq. Desc Bldg.
Fl El.
Cl No 9
2VHE37 0 VH I 21 CHRG PMP RM CLR FAN UNIT Aux 2 84.00 9
2VHE38 0 VH I 22 CHRG PMP RM CLR FAN UNIT Aux 2 84.00 9
2VHE39 0 VH / 23 CHRG PMP RM CLR FAN UNIT Aux 2 84.00 10 2VHE31 0 VH / 21 RHR PMP RM CLR Aux2 45.00 18 203-2 0
I PANEL Aux2 84.00 20 216-2 0 CV I 2 eve CHG PMPS FL & PR INST Aux2 84.00 PANEL 20 229-2A 0
I PANEL Aux2 84.00 20 229-2B 0
/PANEL Aux2 84.00 Certification:
All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our knowledge and belief, correct and accurate. "All information" includes each entry and conclusion (whether verified to be seismically adequate or not).
Rm or Rw/CI Base El. <40'? Cap.
Demd. Cap> Caveats Anchor Interact Equip Spec.
Spec Demd?
OK?
OK?
OK OK?
21 Chrg Pmp Rm 84.00 N/A ABS CRS Yes Yes Yes Yes Yes 22 Chrg Pmp Rm 84.00 N/A ABS CRS Yes Yes Yes Yes Yes 23 Chrg Pmp Rm 84.00 N/A ABS CRS Yes Yes Yes Yes Yes 21 RHR Pmp Rm 45.00 NIA ABS CRS Yes Yes Yes Yes Yes 21 CC Pmp Rm 84.00 NIA ABS CRS Yes Yes Yes Yes Yes Chrg Pmp Viv Alley 100.00 NIA ABS CRS Yes Yes Yes Yes Yes Chrg Pmp Viv Alley 84.00 N/A ABS CRS Yes Yes Yes Yes Yes Chrg Pmp Viv Alley 84.00 NIA ABS CRS Yes Yes Yes Yes Yes Certification:
The information provided to the Seismic Capability Engineers regarding systems and operations of the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and accurate.
Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRn Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability are required; there should be at least two on the SRT. All signatories should agree with all the*
Engineers deem it necessary.)
entries and conclusions. One signatory should be a licensed professional engineer.)
Jim Flaherty 04/20/95 Print or Type Name Date Print or Type Name Signature Date Aziz Saber
~
04/20/95 Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date Print or Type Name Signature Date
SEISMIC EVALUATION REPORT FOR SALEM GENERA TING STATION ATTACHMENT G osvs SALEM UNIT 1 (25 Pages)
PSE&G SALEM UNIT 2 GIP Rev 2, Corrected 2114/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet 1 of2 ID : 1 CA-EC-0398A (Rev. 0)
I Class: 21. Tanks and Heat Exchangers
==
Description:==
AIR ACCUMULATOR FOR 1PR2 Building : Cntmnt 1 I Floor El.: 130.00 Room, Row/Col : 1 Pzr Area
- 1. OUTLIER ISSUE DEFINITION - Tanks and Heat Exchangers
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Shell Buckling Anchor Bolts and Embedment Anchorage Connections Flexibility of Attached Piping Other x
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
1CA-EC-0398A,_ Band 1CA-ED-0148A, B are 4 horizontal air tanks attached to a sustantial, well braced welded steel frame atop the pressurizer cubicle at El 170. The tanks rely on U-bolt friction to prevent longitudinal motion. The small (1" diameter) aii" lines attached to the tank could be damaged if the tanks shift longitudinally. Adequate lognitildinal restraint needs to be demonstrated.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
The tanks should either be postively restrained longitudinally (welded to the saddles or have lugs welded to the tanks) or it should be demonstrated that the U-bolts have adeq\\}ate tension to provide the necessary friction.
PSE&G has an existing program to verify the adequacy of safety-related U-bolt anchors on piping systems (Technical Standard SC-DE-TS/\\.ZZ-3068(Q)). This program could be applied to these tanks.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 3. COMMENTS This OSVS applies to 1CA-EC-0398A, Band 1CA-ED-0148A, B.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirments for this item of equipment to be verified for seismic adequacy:
PSE&G SALEM UNIT 2 GIP Rev 2, Corrected 2/14/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet2 of2 ID: 1CA-EC-0398A (Rev. 0)
I Class: 21. Tanks and Heat Exchangers
==
Description:==
AIR ACCUMULATOR FOR 1PR2 Building : Cntmnt 1 I Floor El.: 130.00 Approved by:
Room, Row/Col : 1 Pzr Area Date:
't/t -r / '1S--
~ (t 1 / '1;
I OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
I GIP Rev 2, Corrected 2114/92 Sheet 1of1 ID: 1SJE5 (Rev. 0)
I Class : 21. Tanks and Heat Exchangers Description : RWST TEST CONN Building : Yard I Floor El.: 100.00 I Room, Row/Col : 1 RWST Area
- 1. OUTLIER ISSUE DEFINITION - Tanks and Heat Exchangers
- a. Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Shell Buckling x
Anchor Bolts and Embedment x
Anchorage Connections Flexibility of Attached Piping Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
I Per the analysis in Section 7 of the GIP, the tank's base moment demand exceeds the base moment capacity.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
Do a more refined analysis per EPRI NP-6041 Appendix H.
In particular, consider:
- 1.
Fluid hold-down force.
- 2. A higher stress allowable for the tank material.
- 3. Using the actual Housner design basis SSE, rather than the enveloping El Centro Spectrum used in this analysis.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
PSE&G SALEM UNIT 1 GIP Rev 2, Corrected 2114/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID: 103-1 (Rev. 0)
I Class: 20. Instrumentation and Control Panels and Cabinets Description : 1 RAD WASTE LQUID AUX SUPM TNK LVL PANEL Building : Aux 1 I Floor El.: 122.00 Room, Row/Col : 1 Control Rm.
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a. Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand x
Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
. The following control room cabinets contain essential relays and are not bolted to adjacent cabinets:
103-1, 131-1, 32-1, 58-1, 59-1
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the listed cabinets to their adjacent cabinets.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 3. COMMENTS This OSVS applies to: 103-1, 131-1, 32-1, 58-1, 59-1.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirments for this item of equipment to be verified for seismic adequacy:
Approved by:
Date:
-=
/
r1
I PSE&G SALEM UNIT 1 GIP Rev 2, Corrected 2114/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID : SEC-1A (Rev. 0)
I Class : 20. Instrumentation and Control Panels and Cabinets Description : SAFEGUARDS EMERGENCY CABINET - 1A i*,
Building : Aux 1 I Floor El. : 100.00 Room, Row/Col : 1 Relay Rm.
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand x
Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
The following relay room cabinets contain essential relays and are are not bolted to adjacent terminal cabinets:
SEC-lA, SEC-lB, SEC-lC.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the listed cabinets to the adjacent terminal cabinets.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
None.
- 3. COMMENTS This OSVS applies to: SEC-1A, SEC-18, SEC-1C.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirments for this item of equipment to be verified for seismic adequacy:
Approved by:
Date:
PSE&G SALEM UNIT 1 OUTLIER SESIMIC VERIFICATION SHEET (OSV GIP Rev 2, Corrected 2114/92 Sheet 1of1 S)
ID : 1WGE17 (Rev. 0)
I Class : 0. Ot her Description : WASTE EVAP VENT GAS CLR Building : Aux 1 I Floor El.: 100.00 Room, Row/Col : 1 Cone Fltr Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electric al Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could
- b.
not be satisfied.)
Capacity vs. Demand x
Caveats Anchorage Seismic Interaction Other Describe all the reasons for the outlier (i.e., if all the list ed outlier issues were resolved, then the signatories seismic adequacy).
would consider this item of equipment to be verified for IWGE17 is a small (apprx 200 lb) passive piping compon ent rigidly mounted to an r/c wall on a substantial anchors. The frame and anchorage are adequate by are rusty - the SRT judged that component needs to be ent's integrity.
welded steel frame anchored with four (4) 5/8" expansion inspection. The component itself and the attached piping inspected to determine if the rust has affected the compon
- anal)
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Opt1
- a.
Defined proposed method(s) for resolving outlier.
I Inspect the component to determine if the rust has affected the component's integrity.
- b.
- Provide information needed to implement proposed me thod(s) for resolving outlier (e.g., estimate of fundamental frequency).
None.
- 3. COMMENTS
~
I
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledg e and belief, correct and accurate, and resolution of equirments for this item of equipment to be verified for the outlier issues listed on the previous page will satisfy the r seismic adequacy:
Approved by: 7¥= '92 Date:
/\\;-6cak/l.
.c
'i/i'flts I
I
~--
PSE&G SALEM UNIT 1 GIP Rev 2, Corrected 2/14/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet 1of2 ID: 1PNL 11828 (Rev. 0)
I Class: 20. Instrumentation and Control Panels and Cabinets Description : 1A D/G GENERATOR CONTROL PANEL Building : Aux 1 I
Floor El. : 1 oo.oo_
Room, Row/Col: 1A DIG Control Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand x
Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier {i.e., if all. the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
The pairs of panels listed below are the A, B, and C diesel engine I diesel generator control panels. Each pair is adjacent to each other and an MCC. They contain essential relays and are not bolted either to each other nor to the adjacent MCC.
A: 1PNL11828, 1PNL11829 B: 1PNL11830, 1PNL11831 C: 1PNL11832, 1PNL11833
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the panels and the MCCs together.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g.., estimate of fundamental frequency).
- 3. COMMENTS This OSVS applies to: 1PNL11828, 1PNL11829, 1PNL11830, 1PNL11831, 1PNL11832, 1PNL11833.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirments for this item of equipment to be verified for seismic adequacy:
PSE&G SALEM UNIT 1 GIP Rev 2, Corrected 2/14/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet2 of2 ID: 1PNL 11828 {Rev. 0)
I Class : 20. Instrumentation and Control Panels and Cabinets
~-
==
Description:==
1A D/G GENERATOR CONTROL PANEL Building : Aux 1 I Floor El. : 1_00.00 Room, Row/Col: 1A D/G Control Rm Approved by:
Date:
/~??'
~~
I I
OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
I GIP Rev 2, Corrected 2/14/92 Sheet 1 of.g l ID : 205-1 (Rev. 0)
I Class : 20. Instrumentation and Control Panels and Cabinets
==
Description:==
11 AUXFEEDWATERPANEL205 Building : Aux 1 I
Floor El. : 84.00 I
Room, Row/Col : 12 Aux Fd Pmp **
Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
I 205-1 and 206-1 are adjacent, not bolted together; and contain essential relays.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the cabinets together to prevent them from striking each other *
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e;g., estimate of fundamental frequency).
- 3. COMMENTS
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
7'"-4L---1-*_,t.7::__4{..::::===--~~;L------- Date:
~ek~
PSE&G SALEM UNIT 1 GIP Rev 2, Corrected 2114/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID: 11105 (Rev. 0)
I Class : 1. Motor Control Centers
==
Description:==
NO 18 DIESEL GENERATOR 230VVITAL CONTROL CENTER Building : Aux 1 I Floor El. : 100.00 Room, Row/Col : 1 B DIG Control Area
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage x
Seismic Interaction Other
- --~
- b.
Describe all the reasons for the outlier (i.e., if all'the. listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
One of the 114" bolts connecting the MCC to its base channel is missing, and a 2nd bolt is not fully engaged.
As the bolts are the primary load path for the anchorage, they need to be repaired.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Replace the missing 1/4" bolt and tighten the 1/4" bolt that is not fully engaged.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
None.
- 3. COMMENTS
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirments for this item of equipment to be verified for seismic adequacy:
Approved by:
Date:
T I
PSE&G SALEM UNIT 1 GIP Rev 2, Corrected 2/14/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID: 11107 (Rev. 0)
I Class : 1. Motor Control Centers Description : NO 1A EAST VALVES & MISC. 230V VITAL CONTROL CENTER
~-*
Building: IPA 1 I Floor El. : 78.00 Room, Row/Col : A, B, C East Valves
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
*~-*
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
Both MCCs 11107 and 11137 abut fire barrier framing - this is an interaction issue as the MCCs contain essential relays.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Modify the fire barrier so that it does contact the MCCs during a seismic event.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
None.
- 3. COMMENTS This OSVS applies to both 11107 and 11137.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy.the requirments for this item of equipment to be verified for seismic adequacy:
- .,.. -~-*
Approved by:
Date:
/
PSE&G SALEM UNIT 1 GIP Rev 2, Corrected 2/14/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet 1 of 1 ID: 11133 (Rev. 0)
I Class : 1. Motor Control Centers
==
Description:==
NO 1C VENTILATION 230VVITAL CONTROL CENTER Building: IPA 1 I Floor El. : 100.00 Room, Row/Col : CH Wtr Pmp Area
- 1. OUTLIER ISSUE DEFINITION - Mechanical and.Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.}
Capacity vs. Demand Caveats Anchorage x
Seismic Interaction Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
One of the 1/4" screws (left front comer) connecting the MCC to it's base channel is missing. As this screw is in the primary anchorage load path, it needs to be replaced.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
l Replace the missing 1/4" screw.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
None.
- 3. COMMENTS
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirments for this item of equipment to be verified for seismic adequacy:
Approved by:
Date:
I r
I
OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
I GIP Rev 2, Corrected 2/14/92 Sheet 1of1 ID: 11126 (Rev. 0)
I Class : 1. Motor Control Centers Description : NO IBI SERV WTR INTAKE 230V VITAL CONTROL CENTER Building: Yard I Floor El.: 100.00 I Room, Row/Col : Srvc Wtr Bldg -
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
l,dentify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
11126 ;s not bolted to the adjacent cab;net SSC-2.
As 11126 contains essent;al relays, th;s ;s an interact;on issue.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the cab;nets together *
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g.,* estimate of fundamental frequency).
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
_Az_i_z_S_a_b_er ____ __,k-S_;;:o,.-.-...:aoa... k""-"-....._A........,,-==--"----- Date:
y I 20/1s Steve Anagnostis _.&~~
~
SALEM NUCLEAR GENERATING STATION I GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID : 1 SWE3 (Rev. 0)
I Class : 6. Vertical Pumps
==
Description:==
13 SERVICE WATER PUMP Building : Yard I Floor El.: 100.00 I Room, Row/Col : Srvc Wtr Bldg
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
The glass oil Level indicator at the top of the pump's motor is hard up against an adjacent r/c wall. The glass could strike the wall and break.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION {Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Reposition the indicator to provide about 111 of clearance.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.;Q., estimate of fundamental frequency).
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
_Az._i_z_S_a_be_r ______
~;....=...___;;;;;_..=.~"'-""<<-~.a.::;;..---- Date:
Steve Anagnostis & t:::::::._ o/ ::::::,,,,.
z
SALEM NUCLEAR GENERATING STATION I
GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of2 ID: RC11-3 (Rev. 0)
I Class : 20. Instrumentation and Control Panels and Cabinets
==
Description:==
11 AUX CONTROL SYSTEMRELAYCABINETRCll-3 Building : Aux 1 I Floor El. : 100.00 I Room, Row/Col : 1 Relay Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other x
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
- 1. All the Bailey cabinets are bolted together, but some of the end cabinets in a row are not bolted to adjacent non-Bailey cabinets. This is an issue as the cabinets contain essential relays. Specifically:
RC11 row: TP11-1 is not bolted to SEC-1A RC12 row: TP12-1 is not bolted to SEC-1B RC13 row: TP13-1 is not bolted to SEC-1C RC14 row:
All OK RC15 row: TP15-1 is not bolted to SPDS RC16 row:
All OK RC18 row:
RC18-7 is not bolted to the Hathaway rack.
- 2. There is a potential for "banging" with the ducts and duct supports above the cabinets, particularly above the RC12 row.
Again, this is an issue as the cabinets contain essential relays:
- 3. There are a couple of maintenance items that need to be addressed:
The inside door panel on RC14-6 is loose.
RC15-7 is missing two of the bolts that anchor the cabi"net to the base channels.
RC15-3 is missing one of the bolts that anchor the cabinet to the base channels.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
- 1. Bolt the adjacent cabinets together.
- 2. Reposition or restrain interfering elements so that they cannot strike the Bailey cabinets.
- 3. Repair the maintenance issues.
- b.
Provide information needed to implernent proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 3. COMMENTS This OSVS applies to all the Unit 1 RC cabinets on the SSEL.
SALEM NUCLEAR GENERATING STATION I GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet2 of2 ID: RC11-3 (Rev. 0)
I Class: 20. Instrumentation and Control Panels and Cabinets Description : 11 AUX CONTROL SYSTEM RELA y CABINET RCl 1-3 Building : Aux 1 I Floor El.: 100.00 l Room, Row/Col : 1 Relay Rm
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
_C=.:..::ha:.:.r=..:be:.:..I :..:.A:::.bo=.:u:....-J::..::a::o:.=u=..:de=--....:C'!:::::;....:.~/)?:....:....:._.:.'-'~~~~b~~e.e.A5.::ic!!::-===-- Date:
l Steve Anagnostis
~cf:=.. G?" "'"'""°"'
'f /"L<>/~s
SALEM NUCLEAR GENERATING STATION I
GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID : 1ADE (Rev. 0)
I Class: 14. Distribution Panels Description : NO IA 28VDC CONTROL BUS Building : Ame 1 I
Floor El. : 84.00 I
Room, Row/Col : 460/230V Vital 125/2
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a. Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
There is a gap between this cabinet and the adjacent C1ADC) control bus, The two cabinets are not bolted to each other. This is not an interaction concern for relays since no essential relays are housed in this cabinet; however it is an interaction concern for circuit breakers er EPRI re ort NP-5223, age C36.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION {Optional}
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the adjacent cabinets together.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 4. CERTIFICATION:
The information on this OSVS is, tq.Jhe best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
Walter Djordjevic Date:
Aziz Saber
,.J *-*
SALEM NUCLEAR GENERATING STATION I GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID : 1 COE (Rev. 0)
I Class: 14. Distribution Panels Description : NO 1 c 28VDC CONTROL BUS Building : Aux 1 I
Floor El. : 84.00 1 Room, Row/Col : 460/230V Vital 125/2
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a. Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy}.
There is a gap between this cabinet and the adjacent 1CDC control bus.The two cabinets are not bolted to each other. These cabinets do not contain essential relays, but the SRT judged it an interaction concern for the circuit breakers.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the cabinets together.
- b.
Provide information needed to implement proposed method(s} for resolving outlier (e.g., estimate of fundamental frequency).
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
Aziz Saber 4/ 2o l'f5 r '
SALEM NUCLEAR GENERATING STATION I GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1 of2 ID : 1 INV1A5YB (Rev. 0)
I Class: 16. Battery Chargers and Inverters Description : NO lA VITAL INSTRUMENT INVERTER Building : Aux 1 I Floor El.: 100.00 l Room, Row/Col : 1 Relay Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
Cabinets are installed adjacent to each other with only a wireway on the front connecting adjacent cabinets together; also at the end of each line-up t~e distribution panel is in contact with the end cabinet but not bolted to it. Even though no essential relays are identified, the SRT reconmends that the cabinets be bolted to each other and the adjacent distribution panel to preclude any potential triooing of breakers.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the adjacent cabinets together.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
3.COMMENTS This OSVS applies to the following inverters (the adjacent distribution panels are shown in parentheses):
1 INV1A5YB (1 DIS1A5YA) 11NV1B11YB (1DIS1B11YA) 11NV1B5YB (1DIS1B5YA) 11NV1C5YB (1DIS1C5YA)
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
SALEM NUCLEAR GENERATING STATION GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 2 of 2 ID : 1 INV1A5YB (Rev. 0)
Class: 16. Battery Chargers and Inverters Description : NO IA VITAL INSTRUMENT INVERTER Building : Aux 1 Floor El. : 100.00 Room, Row/Col : 1 Relay Rm Charbel Abou-Jaoude C:. ///. ;()&.,~ Date:
Jim Flaherty if~ tf'.'<J J~
t:lio /9.s-t.J/-u/" r Approved by:
SALEM NUCLEAR GENERATING STATION I GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID: 11NV1C6YC (Rev. 0)
I Class: 16. Battery Chargers and Inverters Description : NO 11 & 12 STATION ESSENTIAL CONTROL INVERTER Building : Aux 1 I Floor El.: 100.00 I Room, Row/Col : 1 Relay Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
1INV1C6YC is not bolted to adjacent cabinets. Although this cabinet does not.contain essential relays, the SRT judged that it should be bolted to the adjacent cabinets to prevent damage to sensitive comoonents.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt adjacent cabinets together.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
Charbel Abou-Jaoude
- c. /7?. £1&.../"lv.. ~ Date:
(
Jim Flaherty ~
!) * ;UalwJ;
SALEM NUCLEAR GENERATING STATION I
GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID : 205-1 (Rev. 0)
I Class : 20. Instrumentation and Control Panels and Cabinets Description : 11 AUX FEEDWATER PANEL 205 Building : Aux 1 I
Floor El. : 84.00 I
Room, Row/Col : 12 Aux Fd Pmp -
Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
I 205-1 and 206-1 are adjacent, not bolted together, and contain essential relays.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the cabinets together to prevent them from striking each other *
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e:g., estimate of fundamental frequency).
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
SteveAnagnostis 41
..... ___ q?
Date:
Aziz Saber
SALEM NUCLEAR GENERATING STATION I
GIP Rev 2, Corrected 2114/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID : 1AFE1 (Rev. 0)
I Class: 21. Tanks and Heat Exchangers Description : I AUX FEED STORAGE TANK Building : Yard I Floor El. : 100.00 I Room, Row/Col : 1 RWST Area
- 1. OUTLIER ISSUE DEFINITION -Tanks and Heat Exchangers
- a. Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Shell Buckling x
Anchor Bolts and Embedment Anchorage Connections Flexibility of Attached Piping Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
I Per the analysis in Section 7 of the GIP, the tank's base moment capacity exceeds the base moment demand.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a. Defined proposed method(s) for resolving outlier.
Do a more refined analysis per EPRI NP-6041 Appendix H.
In particular, consider:
- 1.
Fluid hold-down force.
- 2. A higher stress allowable for the tank material.
- 3. Using the actual Housner design basis SSE, rather than the enveloping EL Centro spectrum used in this analysis.
- b.
Provide information needed to implement proposed method(s) for reso_lving outlier (e.g., estimate of fundamental frequency).
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
Steve Anagnostis.,.4 (...._ __ £"""c:i:;;:::::=::----......:::::...
Date:
Charbel Abou-Jaoude
SALEM NUCLEAR GENERATING STATION I GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID : 1 DAE4 (Rev. 0)
I Class: 17. Engine-Generators Description : NO. IA DIESEL GENERATOR Building : Aux 1 I Floor El. : 100.00 I Room, Row/Col : 1A DIG Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction Other x
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
The intake Line is supported by three bent threaded rods - it appears to be pretty flexible. PSE&G has evaluated the intake Line supports and decided to modify them CDCP 1EC-3321 and DCP 2EC-3286).
The diesels will be designated outliers nding the co Letion of these calculations.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Complete the intake Line support modifications per DCP 1EC-3321 and DCP 2EC-3286 *
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 3. COMMENTS This OSVS applies to all three Unit 1 diesels: 1 DAE4, 1 DAE 23, and 1 DAE 38.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
Charbel Abou-Jaoude C../??. ;(}0u. ~
I Date:
L/j>>/?S-sL/z.o/:r r
SALEM NUCLEAR GENERA TING STATION I GIP Rev 2, Corrected 2114/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID: 1SWGR1AD (Rev. 0)
I Class : 3. Medium Voltage Switchgear Description : NO I.A. 4160V VITAL BUS
- ~.
Building : Aux 1 I Floor El. : 64.00
-, Room, Row/Col : 4 KV Vital Bus &
Bat
- 1. OUTLIER ISSUE DEFINITION -Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
The end switchgear is NOT attached to the terminal cabinet at the end of the row - there is a 114" gap - this is an interaction problem, the switchgear contains essential relays.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the switchgear to the terminal cabinet.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
3.COMMENTS This OSVS applies to the 3 4160V Switchgear 1SWGR1AD, 1SWGR1BD, and 1SWGR1CD.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
Aziz Saber Date:
Charbel Abou-Jaoude C- /?1. JG~ ~~
l
SEISMIC EVALUATION REPORT FOR SALEM GENERATING STATION ATTACHMENT G osvs SALEM UNIT2 (24 Pages)
OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
I GIP Rev 2, Corrected 2/14/92 Sheet 1 of2 ID : 2CA-SC-1245A (Rev. 0)
I Class: 21. Tanks and Heat Exchangers Description : AIR ACCUMULATOR FOR 2PR1 Building : Cntmnt 2 I Floor El.: 130.00 I Room, Row/Col : 2 Pzr Area
- 1. OUTLIER ISSUE DEFINITION - Tanks and Heat Exchangers
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Shell Buckling Anchor Bolts and Embedment Anchorage Connections Flexibility of Attached Piping Other x
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
2CA-SC-1245A, B, C and D.are 4 horizontal air tanks attached to a substantial, well braced welded steel frame atop the pressurizer cubicle at El 170.
The tanks rely on U-bolt friction to prevent longitudinal motion.
The small (1 11 diameter) air lines attached to the tank could be damaged if the tanks shift longitudinally. Adequate longitudinal restraint needs to be demonstrated.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
The tanks should either be positively restrained longitudinally (welded to the saddles or have lugs welded to the tanks) or it should be demonstrated that the U-bolts have adequate tension to provide the necessary friction.
PSE&G has an existing program to verify the adequacy of safety-related U-bolt anchors on piping systems (Technical Standard SC-DE-TS.ZZ-3068(Q)).
This program could be applied to these tanks.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 3. COMMENTS This OSVS applies to _2CA-SC-1245A, B, C and D.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
I GIP Rev 2, Corrected 2114/92 Sheet2 of2 ID: 2CA-SC-1245A (Rev. 0)
I Class: 21. Tanks and Heat Exchangers Description : AIR ACCUMULATOR FOR 2PR1 Building : Cntmnt 2 I Floor El.: 130.00 I Room, Row/Col : 2 Pzr Area Approved by:
a
PSE&G SALEM UNIT 2 I GIP Rev 2, Corrected 2/14/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID: 103-2 (Rev. 0)
I Class : 20. Instrumentation and Control Panels and Cabinets Description : 2 RAD WASTE LQUID AUX SUPM TNK LVL PANEL Building : Aux 2 I Floor El.: 122.00 I Room, Row/Col : 2 Control Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand x
Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
The following control room cabinets contain essential relays and are not bolted to adjacent cabinets:
103-2, 131-2, 132-2, 32-2, 37-2, 38-2, 58-2, 59-2.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the cabinets to the adjacent cabinets.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 3. COMMENTS This OSVS applies to: 103-2, 131-2, 132-2, 32-2, 37~~*- ~8-2, 58-2, 59-2.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirments for this item of equipment to be verified for seismic adequacy:
Approved by:
Date:
/~
'2'.'
0~~/=-"~::==;;:_
~ok r1
PSE&G SALEM UNIT 2 GIP Rev 2, Corrected 2/14/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID : SEC-2A (Rev. 0)
I Class: 20. Instrumentation and Control Panels and Cabinets Description : SAFEGUARDS EMERGENCY CABINET - 2A Building : Aux 2 I Floor El. : 100.00 Room, Row/Col : 2 Relay Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand x
Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be Verified for seismic adequacy).
The following relay room cabinets contain essential relays and are are not bolted to adjacent terminal cabinets:
SEC-2A, SEC-2B, SEC-2C.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the listed cabinets to the adjacent terminal cabinets.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 3. COMMENTS This OSVS applies to: SEC-2A, SEC-2B, SEC-2C.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirments for this item of equipment to be verified for seismic adequacy:
Approved by: /4zL=. {}2'5*
~Q~-
Date:
- J./>c /c;s;--
PSE&G SALEM UNIT 2 GIP Rev 2, Corrected 2/14/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID : 2PNL 11828 {Rev. 0)
I Class : 20. Instrumentation and Control Panels and Cabinets
==
Description:==
2A DIG GENERATOR CONTROL PANEL Building : Aux 2 I
Floor El. : 100.00 Room, Row/Col : 2A DIG Control Area
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one.if several guidelines could not be satisfied.)
Capacity vs. Demand x
Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be veHfied for seismic adequacy).
The pairs of panels listed below are the A,* B, and C diesel engine I diesel generator control panels.
Each pair is adjacent to each other and an**MGG: They contain essential relays and are not bolted either to each other nor to the adjacent MCC.
A: 2PNL11828, 2PNL11829 B: 2PNL 11830, 2PNL 11831 C: 2PNL 11832, 2PNL 11833
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the panels and the MCCs together.
- b.
Provide information needed to implement pr9p.Q§~c;I method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 3. COMMENTS This OSVS applies to: 2PNL 11828, 2PNL 11829, 2PNL 11830, 2PNL 11831, 2PNL 11832, 2PNL 11833.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirments for this item of equipment to be verified for seismic adequacy:
Approved by:
Date:
~-
OUTLIER SEISMIC VERIFICATION SHE~T (OSVS)
I GIP Rev 2, Corrected 2/14/92 Sheet 1of1 ID : 205-2 (Rev. 0)
I Class : 20. Instrumentation and Control Panels and Cabinets
==
Description:==
21 AUXFEEDWATERPANEL205 Building : Aux 2 I Floor El. : 84.00 I Room, Row/Col : 22 Aux Fd Pmp-Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a. Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
I 205-2 and 206-2 are adjacent, not bolted toghether, and contain essential relays.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the cabinets together to prevent them from striking each other.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
Date:
OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
I GIP Rev*2, Corrected 2/14/92 Sheet 1of1 ID: 206-2 (Rev. 0)
I Class : 20. Instrumentation and Control Panels and Cabinets
==
Description:==
22AUXFEEDWATERPANEL206 Building : Aux 2
., Floor El. : 84.00 I
Room, Row/Col : 22 Aux Fd Pmp **
Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand
- Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
I 205-2 and 206-2 are adjacent, not bolted toghether, and contain essential relays.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
~I B~o~L~t~t~he;;....;.;tw~o~c~a~b~in~e~ts~to~g~et~h~er__;,;to;....i;.;pr~e~ve~n~t~t~hem;.;.;;....;f~r~om;;.....;;..;st~r~ik~in~g~e~a~ch~o~th~e~r. ______________________ __,I
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e;g., estimate of fundamental frequency).
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for.this item of equipment to be verified for seismic adequacy:
Approved by:
PSE&G SALEM UNIT 2 GIP Rev 2, Corrected 2/14/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID: 12107 (Rev. 0)
- I Class : 1. Motor Control Centers Description : NO 2A EAST VALVES & MISC. 230V VITAL CONTROL CENTER Building : IPA 2 I
Floor El. : 78.00 Room, Row/Col : A, B, C East Valves CC
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage
- -~--*
Seismic Interaction
- ~-....
x Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
Both MCCs 12107 and 12137 abut fire barrier framing - this is an interaction issue as the MCCs contain essential relays.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Modify the fire barrier so that it does impact the MCCs during a seismic event.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
3.COMMENTS This OSVS applies to 12107 and 12137.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of
- the outlier issues listed on the previous page will satisfy the requirments for this item of equipment to be verified for seismic adequacy:
Approved by:
Date:
7
PSE&G SALEM UNIT 2 GIP Rev 2, Corrected 2114/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet 1 of 1 ID : 12111 (Rev. 0)
I Class : 1. Motor Control Centers Description : NO 2A AIR COND 230V VITAL CONTROL CENTER Building : Aux 2 I Floor El. : 122.00 Room, Row/Col : CR A/C Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a. Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e.,.if all.the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
The top of the MCC is hard up against a pipe support. As this MCC contains essential relays, this an interaction concern.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier...
I Modify the pipe support so that the MCC will not strike it during a seismic event.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 3. COMMENTS
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirments for this item of equipment to be verified for seismic adequacy:
Approved by:
Date:
7
PSE&G SALEM UNIT 2 GIP Rev 2, Corrected 2114/92 OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID: 12132 (Rev. 0)
I Class : 1. Motor Control Centers Description : NO 28 VENTILATION 230V VITAL CONTROL CENTER Building : IPA 2 I Floor El. : 100.00 Room, Row/Col : CH Wtr Pmp-Area
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage x
Seismic Interaction Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
Three (3) of the 114" screws (all are along the front edge) connecting the MCC to it's base channel are missing.
As these screws are in the primary anchorage load path, they need to be replaced.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Replace the missing screws.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 3. COMMENTS
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirments for this item of equipment to be verified for seismic adequacy:
Approved by:
Date:
I I
PSE&G SALEM UNIT 2 GIP Rev 2, Corrected 2/14/92 I
OUTLIER SESIMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 t
t-:-:~:=-:-=-=-~-......,,..,.---------~:-:---"'7--:-=--:--'"-=---:"~-=-'-.....,....------------*
ID: 12133 (Rev. O}
I Class: 1. Motor Control Centers Description : NO 2C VENTILATION 230V VITAL CONTROL CENTER Building: IPA 2 I Floor El.: 100.00 Room, Row/Col : CH Wtr Pmp Area i
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchor:age x
Seismic Interaction Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
Three of the 1/4" screws (all along the back edge) connecting the MCC to it's base channel are missing. As these screws are in the primary anchorage load path, they need to be replaced.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Replace the missing screws.
- b.
Provide information needed to implement proposed method(s) for resolving outlie'r (e.g., estimate of fundamental frequency).
- 3. COMMENTS
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirments for this item of equipment to be verified for seismic adequacy:
Approved by:
Date:
I 7
SALEM NUCLEAR GENERATING STATION I
GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of2 ID: 12109 (Rev. 0)
I Class : 1. Motor Control Centers Description : NO 2B WEST VAL YES & MISC. 230V VITAL CONTROL CENTER Building : Aux 2 I Floor El. : 84.00 I Room, Row/Col : Elec Contr Center
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage x
Seismic Interaction Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
One of the 1/411 bolts connecting section 12109-3 to its base is missing
- As the bolts are the primary Load ath for the anchorage, it needs to be re aired *
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Replace the missing bolt.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.,g.,.estimate of fundamental frequency).
- 3. COMMENTS
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
Steve Anagnostis
- }.-:?7ft-1/'?~~=::_~~~:._,...... ei.~---
Date:
Aziz Saber
SALEM NUCLEAR GENERATING STATION GIP Rev 2, Corrected 2114/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 2 of 2 ID: 12109 (Rev. 0)
Class: 1. Motor Control Centers Description : NO 2B WEST VALVES & MISC. 230V VITAL CONTROL CENTER Building : Aux 2 Floor El. : 84.00 Room, Row/Col : Elec Contr Center
SALEM NUCLEAR GENERATING STATION I
GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID : 2ADE (Rev. 0)
I Class : 14. Distribution Panels Description : NO 2A 28VDC CONTROL BUS Building : Aux 2 I
Floor El. : 84.00
~ Room, Row/Col : 460/230V Vital
\\
125/250DC Bat
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
There is a gap between this cabinet and the adjacent C2ADC) control bus, The two cabinets are not bolted to each other this is an interaction concern.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the cabinets together *
- b.
Provide information needed to implement proposed method{s) for resolving outlier {e.g., estimate of fundamental frequency).
3.COMMENTS This OSVS applies to 2ADE and 2CDE.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
Aziz Saber I
ijioj9s*
SALEM NUCLEAR GENERATING STATION I
GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID: 2DIS2A5YA (Rev. 0)
I Class: 14. Distribution Panels Description : NO 2A VITAL INSTRUMENT BUS {l ISV)
Building : Aux 2 I Floor El.: 100.00 I Room, Row/Col : 2 Relay Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a. Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
All 4 DIS cabinets are adjacent to the Inverter cabinets
- The SRT was concerned with the potential interaction for the circuit breakers.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the adjacent cabinets together *
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
3.COMMENTS This OSVS applies to 2DIS2A5YA, 2DIS2B11YA, 2DIS285YA, 2DIS2C5YA.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
SALEM NUCLEAR GENERATING STATION GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1 of 2 ID: 21NV2A5YB (Rev. 0)
Class: 16. Battery Chargers and Inverters Description : NO 2A VITAL INSTRUMENT INVERTER Building : Aux 2 Floor El. : 100.00 Room, Row/Col: 2 Relay Rm
'-----=---------------~~~~
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
The inverter cabinets are not bolted to each other or to the adjacent distribution cabinets. This is an interaction concern.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the adjacent cabinets together *
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e;g., estimate of fundamental frequency).
3.COMMENTS This OSVS applies to 21NV2A5YB, 21NV2B11YB, 21NV2B5YB, 21NV2C5YB.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
_;;_s;.;..,;.;_,m.;_;_Fla_he~rty-r__,i.....c;~~~Q...._. ~&L..:!ll:g--=~~..;::oiF-- oate:
Charbel Abou-Jaoude
~ /21. M__ ~-kt I
SALEM NUCLEAR GENERATING STATION I
GIP Rev 2, Corrected 2114/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 2 of2 ID : 21NV2A5YB (Rev. 0)
I Class: 16. Battery Chargers and Inverters Description : NO 2A VITAL INSTRUMENT INVERTER Building : Aux 2 I Floor El. : 100.00 I Room, Row/Col : 2 Relay Rm
SALEM NUCLEAR GENERATING STATION I
GIP. Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID : 21NV2C6YC {Rev. 0)
I Class: 16. Battery Chargers and Inverters Description : NO 21 & 22 STATION ESSENTIAL CON1ROL INVERTER Building : Aux 2 I Floor El.: 100.00 I Room, Row/Col : 2 Relay Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
I The adjacent cabinets are not bolted together.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the adjacent cabinets together *
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
_Ji_m F_lah_erty...___~~~*--0_,...,....~""'""""~~'1"'--+-- Date:
Charbel Abou Jaoude c:J., /J'J. N Vt"' ~e;4.L=--
t
SALEM NUCLEAR GENERATING STATION I
GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID : 2DAE4 (Rev. 0)
I Class: 17. Engine-Generators Description : NO. 2A DIESEL GENERA TOR Building : Aux 2 I Floor El. : 100.00 I Room, Row/Col : 2A DIG Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction Other x
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
The intake line is supported by three bent threaded rods - it appears to be pretty flexible. PSE&G has evaluated the intake line supports and decided to modify them CDCP 1EC-3321 and DCP 2EC-3286).
The diesels will be designated outliers ending the com letion of these calculations.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Complete the intake line supeort modifications per DCP 1EC-3321 and DCP 2EC-3286 *
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e:g., estimate of fundamental frequency).
- 3. COMMENTS This OSVS applies to 1 DAE4, 1 DAE23, and 1 DAE38.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
Charbel Abou-Jaoude C. /JJ. t()~ ~e.y....._
Date:
steveAnagnostis 7 4c ~z C
---=;...
SALEM NUCLEAR GENERATING STATION l
GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
.Sheet 1of2 ID : 2AFE3 (Rev. 0)
I Class : 21. Tanks and Heat Exchangers Description : 2 AUX FEED STORAGE TANK Building: Yard I Floor El. : 100.00 I Room, Row/Col : 2 RWST Area
- 1. OUTLIER ISSUE DEFINITION - Tanks and Heat Exchangers
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Shell Buckling x
Anchor Bolts and Embedment Anchorage Connections Flexibility of Attached Piping Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
I Per the analysis in Section 7 of the GIP, the tank's base moment demand exceeds the base moment capacity.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
Do a more refined analysis per EPRI NP-6041 Appendix H.
In particular, consider:
- 1. Fluid hold-down force.
- 2. A higher stress allowable for the tank material.
- 3. Using the actual Housner design basis SSE, rather than the enveloping EL Centro spectrum used in this analysis.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
3.COMMENTS This OSVS applies to 2AFE3 and 2SJE5.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
SALEM NUCLEAR GENERA TING STATION I
GIP Rev 2, Corrected ~14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet2 of2 ID: 2AFE3 (Rev. 0)
I Class : 21. Tanks and Heat Exchangers Description : 2 AUX FEED STORAGE TANK Building : Yard I Floor El.: 100.00 I Room, Row/Col : 2 RWST Area Approved by:
Charbel Abou-Jaoude C'. l?J. ~..£..&...
Date:
I Steve Anagnostis 4r-- ~ "$? ~
SALEM NUCLEAR GENERATING STATION I GIP Rev 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of2 ID : RC21-4 (Rev. 0)
I Class : 20. Instrumentation and Control Panels and Cabinets Description : 21 AUX CONTROL SYSTEM RELAY CABINET RC21-4 Building : Aux 2 I Floor El. : 100.00 I Room, Row/Col : 2 Relay Rm
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier {i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
The RC cabinets contain essential relays. There is an interaction concern between RC24-7 and overhead HVAC ui ent.
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Restrain the HVAC eguipnent so it will not strike the RC cabinets *
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e:g., estimate of fundamental frequency).
3.COMMENTS This OSVS applies to all cabinets in the RC24 row.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
Charbel Abou-Jaoude C,,, rh. Qu~~
Date:
l Steve Anagnostis ~
~
C::
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<r-l"Lo/9r
'1 /:v; /5 y--
SALEM NUCLEAR GENERATING STATION I
GIP Rev 2, Corrected 2114/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet2 of2 ID: RC21-4 (Rev. 0)
I Class : 20. Instrumentation and Control Panels and Cabinets Description : 21 AUX CON1R.OL SYSTEM RELA y CABINET RC21-4 Building : Aux 2 I Floor El. : 100.00 I Room, Row/Col : 2 Relay Rm
~ :.
SALEM NUCLEAR GENERATING STATION I
GIP Rev 2, Corrected 2114/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1of1 ID: RC21-3 (Rev. 0)
- I Class : 20. Instrumentation and Control Panels and Cabinets
==
Description:==
21 AUXCONTROLSYSTEMRELAYCABINETRC21-3 Building : Aux 2 I Floor El.: 100.00 I Room, Row/Col : 2 Relay Rm
'**~
- 1. OUTLIER ISSUE DEFINITION - Mechanical and Electrical Equipment
- a.
Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction x
Other
- b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
The RC cabinets contain essential relays. The following are not bolted to adjacent cabinets:
- The RC21 row is not bolted to SEC-2A
- The RC22 row is not bolted to SEC-2B
- The RC23 row is not bolted to SEC-2C
- 2. PROPOSED METHOD OF OUTLIER RESOLUTION (Optional)
- a.
Defined proposed method(s) for resolving outlier.
I Bolt the cabinets together.
- b.
Provide information needed to implement proposed method(s) for resolving outlier (e.g., estimate of fundamental frequency).
- 3. COMMENTS This OSVS applies to all cabinets in the RC21, RC22, and RC23 rows.
- 4. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
Charbel Abou-Jaoude C'* /?J. ~~.:¥! Date:
I steveAnagnostis 4kr S
7