Similar Documents at Salem |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18107A5291999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9 ML20211Q8771999-08-27027 August 1999 Rev 0 to Inservice Testing Manual for Pumps & Valves Program ML18107A5171999-08-25025 August 1999 Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2 ML18107A5121999-08-23023 August 1999 Procedure 71151, Performance Indicator Verification. ML18107A5091999-08-23023 August 1999 Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability. ML18107A4961999-08-23023 August 1999 Proposed Tech Specs,Modifying 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. ML18107A4671999-07-29029 July 1999 Proposed Tech Specs Replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements ML18107A4601999-07-23023 July 1999 Proposed Tech Specs Pages Changing TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown ML18107A4241999-07-0202 July 1999 Proposed Tech Specs,Relocating TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to UFSAR ML18107A3811999-06-10010 June 1999 Proposed Tech Specs 3/4.6.1, Containment Integrity, Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML18107A2961999-05-12012 May 1999 Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9 ML18107A2131999-04-14014 April 1999 Proposed Tech Specs 3/4.9.12, Fhavs, Revised to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,As Well Better Alignment to Bases Provided in NUREG-1431 ML18106B1591999-03-31031 March 1999 Proposed Tech Specs Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918 ML18106B0801999-02-22022 February 1999 Proposed Tech Specs Re CR Emergency Air Conditioning Sys ML18106B0641999-02-0808 February 1999 Proposed Tech Spec Pages,Modifying ECCS Subsystems Surveillance 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing ML18106B0611999-02-0808 February 1999 Proposed Tech Specs SR 4.8.1.1.2.f Re Hot Restart & Definition of Standby Conditions. ML18106B0531999-02-0202 February 1999 Proposed Tech Specs 5.6.1.1,revising Max Permissible Enrichment of Stored New Fuel ML18106B0431999-01-19019 January 1999 Proposed Tech Specs Bases Section 3/4.1.2 Re Boration Sys ML18106B0241999-01-15015 January 1999 Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1 ML18106A9231998-10-12012 October 1998 Proposed Tech Specs Re Inserts & Marked Up Pages for LCR S98-03 ML18106A9181998-10-12012 October 1998 Proposed Tech Specs Re one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10 ML18106A8941998-09-29029 September 1998 Proposed Tech Specs Section 3/4.9.2,modified to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch ML18106A8781998-09-17017 September 1998 Proposed Tech Specs Modifying 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity ML18106A8371998-08-12012 August 1998 Proposed Tech Specs Modifying Allowed Continued Operation W/Inoperable Air Lock Door Provided That Operable Door Is Closed & Unlocked & Making Requirements for Inoperable Air Lock Door ML18106A7931998-07-30030 July 1998 Proposed Tech Specs,Revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Stated Phrase ML18106A6961998-07-0707 July 1998 Proposed Tech Specs Section 4.2.1 Re Aquatic Monitoring of App B for Environ Protection Plan ML18106A6631998-06-17017 June 1998 Proposed Revised Tech Specs Bases Pages 3/4.1.3,3/4.1.2, 3/4.5.5 & 3/4.9.1,ensuring Acceptable Power Distribution Limits Are Maintained,Providing Operational Flexibility & Clarifying Statements ML20216B0641998-05-0101 May 1998 Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page ML18106A5571998-04-16016 April 1998 Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents ML20239A1251998-03-31031 March 1998 Rev 11 to Salem Nuclear Generating Station Odcm ML18106A4241998-03-26026 March 1998 Proposed Tech Specs Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters. ML18106A4291998-03-26026 March 1998 Proposed Tech Specs,Changing Applicability Statement from Mode 3 to Modes 1 & 2 ML18106A3921998-03-13013 March 1998 Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency. ML18106A8281998-03-0404 March 1998 Rev 1 to Reactivity Manipulations Documentation Guide. ML18106A3221998-02-18018 February 1998 Marked-up TS Pages for Section 4.2.1 of App B ML18106A3091998-02-0202 February 1998 Revised TS Bases Pages for Specs 3/4.3.3.1,radiation Monitoring instrumentation,3/4.3.3.8,radioactive Liquid Effluent Monitoring Instrumentation & 3/4.3.3.9,radioactive Gaseous Effluent Monitoring Instrumentation ML18106A2541998-01-0808 January 1998 Proposed Tech Specs Pages,Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page ML18106A2141997-12-15015 December 1997 Proposed Tech Specs Pages,Revising TS to Adopt Option B to 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing ML18106A1961997-12-11011 December 1997 Proposed Tech Specs Re one-time Exemption to Allow Containment Purging in Modes 3 & 4 ML18102B6791997-11-14014 November 1997 Proposed Tech Specs Providing Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels ML18102B6751997-11-14014 November 1997 Proposed Tech Specs Re Administrative & Editorial Corrections ML18102B6591997-11-0404 November 1997 Proposed Tech Specs,Revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid ML18102B6631997-11-0404 November 1997 Proposed Tech Specs,Deleting 4.8.1.1.2.d.1,which Calls for Diesels to Be Subjected to Insp Based on Vendor Recommendations at Least Once Per 18 Months During Shutdown ML18102B6431997-10-29029 October 1997 Proposed Tech Specs Revising SR 4.8.1.1.2.d.2 Proposed in 960925 Request to Change EDG Voltage & Frequency Limits as Result of Updated EDG Load Calculations & Ambiguity in Testing Methodology for EDG Start Timing ML18102B6391997-10-29029 October 1997 Proposed Tech Specs Changing SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10 ML18102B6491997-10-24024 October 1997 Proposed Tech Specs Pages,Modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases ML18102B6461997-10-24024 October 1997 Proposed Tech Specs Revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1 ML18102B6321997-10-21021 October 1997 Proposed Tech Specs,Extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers Are in Closed Position ML18102B6201997-10-14014 October 1997 Proposed Tech Specs Modifying Pressure Isolation Valves LCO, LCO Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2 1999-09-10
[Table view] Category:TEST REPORT
MONTHYEARML18102B3491997-05-28028 May 1997 Readiness for Restart,Overview of Key Initiatives. ML18096B0061992-09-0303 September 1992 Test Rept A28173 for Project, Fuel Oil Spills,Crane & Filter. ML18096B0051992-09-0303 September 1992 Test Rept A28173 for Project, Fuel Oil Spills,Crane & Filter. ML18096A9091992-06-28028 June 1992 Suppl to Test Rept A27611, Well House 5 Spill. ML18096A7991992-06-23023 June 1992 Reactor Containment Bldg Integrated Leak Rate Test. ML18096A9081992-06-12012 June 1992 Test Rept A27611, Well House 5 Spill. ML18096A1231991-07-0303 July 1991 Ninety-Day Containment Integrated Leak Rate Test Rept Ninth Refueling Outage Salem Generating Station Unit 1. W/910703 Ltr ML20059E7901990-01-22022 January 1990 ASTM E-72 Load Testing of 2-h Solid Stud Wall ML18093A7671987-12-31031 December 1987 Reactor Containment Bldg Third/Final Inservice Integrated Leak Rate Test,First 10-Yr Insp Interval & Type B & C Surveillance Tests. ML18092B4611987-03-13013 March 1987 Second Inservice Integrated Leak Rate Test & Type B & C Surveillance Test, Rept for Nov 1986 ML20215E4621986-11-30030 November 1986 Voltage Study for Split Group Bus Configuration ML18092A3701984-08-31031 August 1984 Reactor Containment Bldg Second Inservice Integrated Leak Rate Test & Types B & C Surveillance Test. ML20094G5731984-07-30030 July 1984 Revised Pages 6 & 7 to Salem,Unit 2 Cycle 2 Startup Test Rept ML18092A2101984-05-15015 May 1984 Cycle 2 Startup Test Rept. W/840613 Ltr ML18094A4091984-04-13013 April 1984 Simulated 40-Yr Svc Life Test for PSA-3 Shock Arrestor W/2 to 3% Friction. ML20081C3751983-09-15015 September 1983 Rept of Exams,Insps & Tests Conducted During 1983 First Refueling of Salem 2 ML18089A3291983-08-22022 August 1983 Cycle 5,Startup Test Rept. W/830822 Ltr ML18089A1791983-06-0303 June 1983 Analysis of Valve/Operator Interface Hardware for Containment Pressure & Vacuum Relief Valves 1 & 2 VC 5. ML18089A4221983-05-31031 May 1983 Reactor Containment Bldg First Inservice Integrated Leak Rate Test & Type B & C Surveillance Test. ML18086B6141982-08-0303 August 1982 Cycle 4 Startup Test Rept. ML18086B3431982-01-31031 January 1982 X 17 Fuel Assembly Guide Thimble Tube Wear Exam Rept. ML20040E7921982-01-29029 January 1982 Startup Test Rept,Part 2. ML18086B1381981-12-0303 December 1981 Feedwater Hammer Test,Number 21 Feedwater Piping,Salem Generating Station. ML18086A9971981-08-14014 August 1981 Steam Driven Auxiliary Feed Pump Endurance Test, Special Tests 21,22 & 23 ML18086A8381981-07-31031 July 1981 Tech Specs 3/4.6.3 for Containment Sys ML18086A3571981-04-28028 April 1981 Startup Test Rept. ML18086A2671981-04-0909 April 1981 Cycle 3,Startup Test Rept. ML18086B2731981-01-31031 January 1981 Experimental Evaluation of Flow Patterns in RHR Sump W/ Simulation of Screen Blockage Salem Nuclear Generating Station. ML18082B1711980-09-0808 September 1980 Natural Circulation Tests. ML19329F9951980-07-0808 July 1980 Addendum to Rept for Reactor Containment Integrated Leak Rate Test First Retest - Aug 1979. ML18082A2951980-05-0101 May 1980 Cycle 2 Startup Test Rept. ML18082A1491980-04-0303 April 1980 Refueling Water Storage Tank Vortex Test. ML18082A1221979-08-31031 August 1979 Reactor Containment Integrated Leak Rate Test,First Retest - Aug 1979. ML18079A7931979-08-0808 August 1979 Corrected Startup Test Power Coefficients for Cycle 2 Reload Originally Submitted 790803 ML20114E8611979-05-17017 May 1979 Qualification of Electrical Connection Terminal Blocks/Junction Boxes in Containment Environ of LOCA or Steam Line Break Accident ML18078B1611979-02-26026 February 1979 Structural Integrity Test of Containment. ML18078A9801979-02-0808 February 1979 Qualification Tests of Solenoid Valves by Environ Exposure to Elevated Temp,Radiation,Seismic Simulation,Vibration Endurance,Accident Radiation & LOCA Simulation ML18078A9811978-09-0505 September 1978 Namco EA-180 Limit Switch Qualification Rept. ML20210T4841977-09-29029 September 1977 Startup Test Rept ML18086A8371975-10-24024 October 1975 Seismic Vibration of (1)10 Inch,(1)20 Inch & (1)36 Inch Butterfly Valves for Masoneilan Intl,Inc. 1997-05-28
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AttCchment 1 to
. NFU 84-210 ATTACIDEENT 1 REVISIONS TO THE
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- SALEN 2, CYCLE 2 STARTUP REPORT i
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Z3ro Power Test Results The zero powsr test schedule for Cycle 2 was essentially identical to that done for Unit 1 Cycle S. The rod exchange technique was used for measuring the bank rodworth rather than the traditional boron dilution method. Comparisons of swap mode rodworth measurements and design values along with review criteria are shown in Table 2. Comparisons of dilution mode measurements and design values along with acceptance criteria are shown in Table 3.
As shown in Table 3, the dilution mode worth for bank C fails the acceptance criteria by 23 pcm. This failure was pre-dicted prior to the' test based on comparisons of PSEEG and Westinghouse rodworth calculations. The cause of the predicted deviations was a difference in the flux distributions as cal-culated by PSEEG and Westinghouse.' Relative to PSE&G, the .
Westinghouse power distribution was radially tilted, with higher flux levels at the center. According to PSE&G analyses per-formed prior to the test, this tilt would cause some of the Westinghouse test predictions to deviate from measurements.
PSE&G calculations predicted that the measurements of bank C and A would be 20% and 96 pcm lower than the 1[ predictions.
The observed deviations were 16% and 67 pcm lower respectively.
Additional confirmation of the presence of a radial flux tilt in the 1[ models was obtained from the HZP flux map measurement, and a special dilution measurement of the bank C worth. Com-parisons of the measured and predicted HZP flux distributions are shown in Figure 3 for Map #2200. The results confirm that the
- Westinghouse predictions were approximately 10% too high at the core center.
.The special dilution measurement of the bank C worth was performed using the boron dilution technique. The measured value
. was 736 pcm, which confirms the exchange mode measurement shown in Table 3.
Page 6
s The deviation of the bank C measurement from vendor design predictions was reviewed by the Station operations Review Com-mittee. Based on the composite of test results, and the PSE&G calculations. performed prior to the test, it was concluded that the deviation did not significantly effect the conclusions of the Salem 2, Cycle 2 Reload Safety Evaluation.
A Boron end point measurement was conducted with all rods out and was witnin the + 50 ppm acceptance criteria. The measured value of 1364 ppm was 44 ppm lower than predicted.
An Isothermal temperature coefficient measurement was per-formed with all rods out. The value obtained was very close to the predicted value and well within tolerances.
Results of the zero power flux map (#2200) are shown in Table
- 4. A tilt ini het power distribution of 2.3% was discov.ered'in ,
the N. W., quadrant and the resulting peaking factor Fxy exceeded the full power Technical Specification limits, but was below the zero power limits. The observed tilt was within the range pre-dicted by the Fuel Vendor (Westinghouse).
Map 2200 was taken to evaluate the potential that the quantity FAH may violate the Technical Specification for low power, rodded operation at BOC. The vendor's evaluation of this potential violation on the appropriate accident analysis showed that there would be no adverse effects. NFG analyzed that the cause fcr the potential violation would be a radial, in-out flux tilt.
The results of Map 2200 (Figure 3) confirmed the existence of the radial tilt. Administrative limits on rod insertion were imposed to ensure that FAH would not be violated for low power rodded operation (See Figure 13).
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7 NFU 84-210
' O PSEG Public Service Electnc and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department July 30, 1984 Dr. Thomas E. Murley Regional Administrator, Region 1 631 Park Avenue King of Prussia, PA 19406
Dear Dr. Murley:
STARTUP TEST REPORT SALEM NO. 2 CYCLE 2 LICENSE NO. DPR-75 DOCKET NO. 50-311 Attached please find two (2) copies of revised pages to the Salem No. 2 Cycle 2 Startup Test Report.
Sincerely, E. A. Liden Manager - Nuclear Licensing and Regulation RAB:dgh Attachment 0
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The Energy People Il 95-21 M 160M11182
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. '. O Dr.LThomas E..Murley 7/30/84 C Director, office of Inspection att.(36) and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 lur. Donald C. Fischer att.
Licensing Project -Manager-Mr. James Linville att.
Senior _ Resident Inspector
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