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| | issue date = 06/17/1998 | | | issue date = 06/17/1998 |
| | title = Requests That Pse&G Be Released from Requirements of CAL 1-95-009 for Salem Units 1 & 2.Detailed Comparison of Two Unit Startup,Encl | | | title = Requests That Pse&G Be Released from Requirements of CAL 1-95-009 for Salem Units 1 & 2.Detailed Comparison of Two Unit Startup,Encl |
| | author name = KEISER H W | | | author name = Keiser H |
| | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY | | | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY |
| | addressee name = MILLER H J | | | addressee name = Miller H |
| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | | | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | docket = 05000272, 05000311 | | | docket = 05000272, 05000311 |
Similar Documents at Salem |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5421999-09-22022 September 1999 Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. 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[Table view] Category:INCOMING CORRESPONDENCE
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[Table view] |
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. f. *:* .. I Public Service Electric and Gas Company Harold W. Keiser Chief Nuclear Officer & President Nuclear Business Unit Public Service Electric and Gas Company PO. Box 236, Hancocks Bridge, NJ 08038 609-339-11 oo . . Mr. H. J. Miller Regional Administrator
-Region I U.S. Nuclear Regulatory Commission 475 Allendale Rd. King of Prussia, PA 19406
Dear Mr. Miller:
JUN 171999 LR-N980287 REQUEST TO RELEASE PUBLIC SERVICE ELECTRIC AND GAS FROM THE REQUIREMENTS OF CONFIRMATOR;f ACTION LETTER (CAL-1-95-009)
FOR SALEM GENERATING STATION NOs 1and2 FACILITY OPERATING LICENSES DPR-70 and DPR-75 . DOCKET NOS. 50-272 and 50-311 On June 9, 1995, the Nuclear Regulatory Commission (NRG) issued a Confirmatory Action Letter (CAL) for Salem Units 1 and 2. Since this date, Public Service Electric & Gas (PSE&G) has taken the required actions and provid_ed information concerning these actions via letters dated June 27, 1997 and March 23, 1998, for Units 2 and 1 respectively.
Accordingly, NRG responded by modifying the CAL via letters dated August 6, 1997 (Unit 2 restart) and April 1, 1998 (Unit 1 restart).
With the April 1, 1998 letter, the NRC modified CAL 1-95-009 to permit the restart of Salem Unit 1. NRC also requested PSE&G to provide a summary of our operating and testing experience, and an evaluation of our overall restart plan, including any lessons learned. PSE&G hereby provides the requested information and respectfully requests that it be released from the requirements of CAL 1-95-009 for Salem Units 1 and 2. Following the May/June 1995 shutdown of both Salem Units and the issuance of the CAL, PSE&G conducted a comprehensive review (self-assessment) of our operational readiness.
This review led to the development of the Salem Restart Plan (SRP). The SRP consisted ofa comprehensive and systematic approach for the identification, review, approval, assessment and affirmation of the activities needed to support the restart and reliable operation of the Salem Units. The SRP contained three major sections; (1) Plant, People and Process Improvements, (2) Restart Readiness Review and Affirmation, and (3) Startup and Power Ascension Testing. /l / / .) IQ ----------
9806290129 980617 PDR ADOCK 05000272 p P.DR /f \: /
. " Mr. H. J. Miller LR-N980287 2 JUN 171998 As part of this overall SRP, PSE&G established the Management Review Committee. (MRC). The MRC was established as an oversight committee to review amongst other things the restart action plans (RAPs), and the System Readiness Review Program (SRRP). The RAPs were developed to address the major areas described above and the identified root and contributing causes for their deficiencies.
The root and contributing causes identified and addressed by the RAP were the causes, which led to the decline in performance and eventual shutdown of the Salem Units. The SRRP provided PSE&G with reasonable assurance that equipment operability and reliability issues had been identified, and that effective corrective actions had been taken. This* was accomplished by a methodical review of selected systems. These systems were selected on the basis of a combination of attributes such as safe shutdown risk, risk significance, and historical power reduction and high incidence of corrective maintenance.
The SRP and its associated RAPs and SRRP were considered living documents/programs.
As PSE&G moved forward with the restart process, the SRP was revised (e.g., the Operations and Maintenance interventions) to ensure that PSE&G accomplished the goals necessary to allow for a safe and event free restart of . the Salem Units. In summary, the successful implementation of the Salem Restart Plan in conjunction with other activities, such as the closure of all NRC restart items, led PSE&G to request the NRC to begin its Readiness Assessment Team Inspections (RATI). These inspections independently concluded that PSE&G was ready to proceed with the restart of the Salem Units and embarked on the last portion of the SRP; the Startup and Power Ascension Testing. Modifying the CAL via letters dated August 6, 1997 (Unit 2 restart) and April 1, 1998 (Unit 1 restart) provided this concurrence.
- At the MRC of June 15, 1998, departmental affirmations were completed establishing the readiness of the Salem management team to support the safe and reliable operation on the Salem Units. In essence, this affirmation signaled the completion of the startup and testing of the Salem Units 1 and 2. The Startup and Power Ascension Program for the Salem units was originally developed as a part of the PSE&G Restart Plan. The successful restart of both Units demonstrated that the SRP was successful in improving our plant, process and people. The lessons learned from the Unit 2 startup were captured and used to improve the startup and testing for Unit 1. For example, Unit 2 problem equipment was fixed on Unit 1 and the scheduled was adjusted to do complex tasks first. As a result of better test planning, coordination between departments no major test delays were encountered during the Unit 1 startup. 95-4933
. *' Mr. H. J. Miller LR-NS80287 3 JUN 1 7 1998 In addition, test procedures were improved, test set-ups and sequencing of activities were better controlled, planning was more complete and experienced test engineers applied their knowledge, which resulted in fewer tests and test procedures to test the same functions.
This outcome, in itself, was very positive.
Another way to measure the success of the Unit 1 startup is to the efficient use of time and resources during the two restarts.
The following table provides such a comparison:
UNIT2 UNIT 1 Unit 1 STARTUP STARTUP vs. Unit2 Day of Activity Event . Day of Activity Days Startup Days Startup Davs 1 Entered Mode 6 1 5 Fuel Load Complete 4 11 Entered Mode 5 11 175 Entered Mode 4 60 194 45 Entered Mode 3 87 21 -24 239 8 Entered Mode 2 108 5 -3 247 5 Entered Mode 1 113 3 -2 252 3 Reactor Power at 116 4 1 25% 255 9 Reactor Power at 120 4 -5 47% 264 8 ADFCS 10% Load 124 6 -2 Swing Performed 272 3 Reactor Power at 13.0 3 0 90% 275 -Reactor Power at 133 --100% 81 Total Mode 3 to 1 46 -35 However, since the Unit 2 startup was delayed by several unscheduled activities (e.g., installation of the containment fan coil unit (CFCU) modification), the comparison can best be measured by evaluating the timeframe from Mode 3 to 100 percent power (i.e., below the heavy black line). As the table shows for this period, the Unit 2 startup took 81 days, while the Unit 1 startup took only 46 days. This difference represents a 43% reduction in the startup time for Unit 1, an accomplishment even more significant since it also included testing of the new steam generators.
95-4933
- if Mr. H. J. Mil.ler 4 JUN 171998 Again, this comparison demonstrates how better teamwork has resulted in greater schedule adherence and more efficient use of organizational resources.
In summary, the Unit 1 startup demonstrated that the Nuclear Business Unit (NBU) has successfully integrated plant, people and process to assure safe, and reliable operation of our nuclear plants. Attachment 1 to this letter contains a detailed comparison of the two unit startups.
As we move into the future, PSE&G acknowledges that there are a number of areas requiring further management attention.
Reducing the Maintenance and Engineering Backlogs, and fully implementing the Workweek Management process are areas where additional management focus is needed. Currently, plans are in place to . implement the same model to reduce the maintenance backlog that was used for Hope Creek. The engineering backlog will be reduced utilizing both internal and external resources.
The plans to reduce the backlogs are either in place or being developed and will be initiated during the remainder of 1998. PSE&G expects that several
- operating cycles will be needed to achieve their full effect. In conclusion, PSE&G is committed to operating its nuclear plants safely and reliably.
Our goal is to become a top quartile performer.
A strong foundation has.been established to achieve this goal; however, we must continue to improve our . performance to maintain pace with today's increasing industry standards and competitive challenges.
In particular, we need to continue to improve our quality of work and ensure that our operational decisions are conservative.
We recognize that the nuclear environment requires people to work to increasingly higher standards.
PSE&G leadership strives not only to meet these standards but exceed them in our daily work practices.
Based on the discussion above and the information contained in Attachment 1, PSE&G firmly believes that it has demonstrated its ability to safely and reliably operate all of its nuclear units. Therefore, PSE&G respectfully requests that it be released from the requirements of CAL 1-95-009 for Salem Units 1 and 2. If you have any concerns regarding this submittal, please contact us. Sincerely, 95.4933
' i Mr. H. J. Miller LR-N9Bo2a1 5 C U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Mr. P. Milano, Licensing Project Manager-Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. S. Morris (X24) USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 e JUN 1 7 1998 95-4933