SER Re Setpoint Methodology for Rosemont Replacement Transmitters.Licensee Proposed Methodology Not Adequate to Allow Approval to Be Used in Application of UnitsML20235G965 |
Person / Time |
---|
Site: |
Seabrook |
---|
Issue date: |
09/24/1987 |
---|
From: |
Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
Shared Package |
---|
ML20235G961 |
List: |
---|
References |
---|
NUDOCS 8709300314 |
Download: ML20235G965 (3) |
|
|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212D1461999-09-17017 September 1999 SER Accepting Request to Use Proposed Alternative to Certain Weld Repair Requirements in ASME Boiling & Pressure Vessel Code ML20210Q7581999-08-11011 August 1999 SER Approving Proposed Merger of CES & Bec,Which Will Create New Parent Company of Canal ML20210J8681999-08-0303 August 1999 SER Approving License Transfer from Montaup Electric Co to Little Bay Power Corp & Approval of Conforming Amend for Seabrook Station Unit 1 ML20205C1981999-03-24024 March 1999 Safety Evaluation Concluding That Proposed Relief Request IR-8,Rev 1,provides Acceptable Alternative to ASME Code Requirements.Recommends Authorization of Proposed Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20196F5741998-12-0202 December 1998 Safety Evaluation Concluding That Licensee Has Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Seabrook ML20197A7531998-02-27027 February 1998 Safety Evaluation Accepting License Request for Relief from ASME Code,Section IX Requirements Re Inservice Insp of RHR Heat Exchanger Nozzle Welds & Reactor Vessel Closure Head Nuts ML20137T9941997-04-0909 April 1997 Safety Evaluation Accepting Proposed Use of ASME Code Case N-524 for North Atlantic Energy Service Corp,Seabrook Station,Unit 1 ML20133P9121997-01-22022 January 1997 Safety Evaluation Accepting Corporate Restructuring of Great Bay Power Corp & Formation of Holding Company,North Atlantic Energy Svc Corp ML20059J2381993-11-0505 November 1993 Safety Evaluation Accepting 921125 TS Changes,Augmented by 930702 Response to NRC Rai,Allowing Use of Fixed Incore Detector Sys at Facility ML20247N5901989-07-28028 July 1989 Safety Evaluation Concluding That Overall State of Onsite & Offsite Emergency Preparedness Provides Reasonable Assurance That Adequate Protective Measures Can & Will Be Taken in Event of Radiological Emergency at Plant ML20245A9091989-06-15015 June 1989 SER Supporting Util Actions to Comply W/Atws Rule (10CFR50.62),pending Resolution of Tech Spec Issue.Licensee Should Continue W/Scheduled Installation & Implementation of ATWS Design Using Administrative Controlled Procedures ML20246H5711989-05-0303 May 1989 Safety Evaluation Supporting Util Decommissioning Funding Assurance Plan for Facility Per Commission Decision 88-10 ML20246N8731989-03-21021 March 1989 Safety Evaluation Accepting Util 881118 Submittal on Isolation Devices ML20154Q9881988-09-27027 September 1988 Safety Evaluation Supporting Amend 1 to License NPF-56 ML20153D2321988-08-24024 August 1988 Safety Evaluation Accepting Licenseee Proposed Mod to Control Room Habitability Sys ML20235G9651987-09-24024 September 1987 SER Re Setpoint Methodology for Rosemont Replacement Transmitters.Licensee Proposed Methodology Not Adequate to Allow Approval to Be Used in Application of Units ML20235U6021986-06-17017 June 1986 Sser Supporting Util 860528 Request for Relief from Impractical Preservice Insp Requirements of ASME Code Section XI IA-87-213, SER Finding Facility Design Acceptable W/Respect to Conformance to Reg Guide 1.97,Rev 3,except for Accumulator Tank Level & Pressure Instrumentation,Containment Sump Water Temp Instrumentation & Quench Tank Temp Instrumentation1986-06-11011 June 1986 SER Finding Facility Design Acceptable W/Respect to Conformance to Reg Guide 1.97,Rev 3,except for Accumulator Tank Level & Pressure Instrumentation,Containment Sump Water Temp Instrumentation & Quench Tank Temp Instrumentation ML20215G1691986-06-11011 June 1986 SER Finding Facility Design Acceptable W/Respect to Conformance to Reg Guide 1.97,Rev 3,except for Accumulator Tank Level & Pressure Instrumentation,Containment Sump Water Temp Instrumentation & Quench Tank Temp Instrumentation ML20136D6751985-04-30030 April 1985 Safety Evaluation Re Elimination of Arbitrary Intermediate Pipe Breaks in High Energy Piping Sys.Pipe Rupture Postulation & Associated Effects Are Adequately Considered in Design.Deviation from SRP Acceptable ML20235U0031985-03-31031 March 1985 Safety Evaluation Supporting Util 850207 Request to Eliminate Arbitrary Intermediate Pipe Breaks in All High Energy Piping Sys Except Main Feedwater Sys at Facility ML20235T6911985-02-22022 February 1985 Safety Evaluation Supporting Util Request for Exemption from GDC-4 for Facility.Util Occupational Dose Saving Estimate for Plant Personnel of Approx 1,400 Person Rem Is Reasonable ML20235T6631985-01-18018 January 1985 Safety Evaluation Supporting Util Technical Justification for Not Providing Protective Devices Against Dynamic Effects of Postulated Pipe Breaks 1999-09-17
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H2841999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Seabrook Station. with ML20212D1461999-09-17017 September 1999 SER Accepting Request to Use Proposed Alternative to Certain Weld Repair Requirements in ASME Boiling & Pressure Vessel Code ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 ML20212B8671999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Seabrook Station. with ML20210Q7581999-08-11011 August 1999 SER Approving Proposed Merger of CES & Bec,Which Will Create New Parent Company of Canal ML20210R9781999-08-0606 August 1999 ISI Exam Rept of Seabrook Station, for RFO 6,period 3 ML20210J8681999-08-0303 August 1999 SER Approving License Transfer from Montaup Electric Co to Little Bay Power Corp & Approval of Conforming Amend for Seabrook Station Unit 1 ML20210R6001999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Seabrook Station, Unit 1.With ML20210H1151999-06-30030 June 1999 Naesc Semi-Annual Fitness-for-Duty Rept for 990101-0630 ML20209H1371999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Seabrook Station, Unit 1.With ML20195G5391999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Seabrook Station, Unit 1.With ML20195C0491999-05-25025 May 1999 Offshore Intake Seal Deterrent Barrier Design ML20206E4761999-04-30030 April 1999 LER 99-S01-00:on 990408,contractor Employee Was Granted Temporary Unescorted Access to Seabrook Station Protected Area.Caused by Failure of Contractor Employee to Provide Accurate Info.Individual Access Revoked.With ML20206N1751999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Seabrook Station, Unit 1.With ML20196L2081999-04-19019 April 1999 Rev 01-07-00 to RE-21, Cycle 7 Colr ML20205K5441999-03-31031 March 1999 Decommissioning Update ML20205L8141999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Seabrook Station. with ML20205C1981999-03-24024 March 1999 Safety Evaluation Concluding That Proposed Relief Request IR-8,Rev 1,provides Acceptable Alternative to ASME Code Requirements.Recommends Authorization of Proposed Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20207F4941999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Seabrook Station. with ML20199E6731998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Seabrook Station, Unit 1.With ML20198P1831998-12-31031 December 1998 LER 98-S01-00:on 981214,incomplete pre-employment Screening Records Was Noted.Caused by Failure of Contractor Employee to Provide Accurate Info.Subject Contractor Employees Employment Was Terminated.With ML20202E8241998-12-31031 December 1998 Naesc Semi-Annual Fitness-for-Duty Rept for 980701-981231 ML20196F5741998-12-0202 December 1998 Safety Evaluation Concluding That Licensee Has Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Seabrook ML20198B8661998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Seabrook Station, Unit 1.With ML20195D0311998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Seabrook Station, Unit 1.With ML20154H5291998-10-0808 October 1998 Special Rept:On 980928,meteorological Monitoring Instrumentation Channel Inoperable for Period Greater than 7 Days.Caused by Vendor to Follow Std Industry Practice for Calibr of Instrumentation.Instruments Installed ML20154M8421998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Seabrook Generating Station,Unit 1.With ML20151V5951998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Seabrook Station, Unit 1.With ML20237B4501998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Seabrook Station ML20236R1781998-06-30030 June 1998 Naesc Semi-Annual Fitness-for-Duty Rept for 980101-0630 ML20236M3591998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Seabrook Station, Unit 1 ML20237A4871998-06-0303 June 1998 North Atlantic Seabrook Station 1998 Exercise on 980603 ML20248M2951998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Seabrook Station, Unit 1 ML20247G2641998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Seabrook Station ML20247H3171998-04-27027 April 1998 Rev 1 to Seabrook Station SGs B & C Isi,May/June 1997 ML20216F8891998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Seabrook Station 05000443/LER-1998-002, Re Potential Safety Injection Pump Runout Conditions Identified on 980113.LER 98-002-00 Retracted1998-03-20020 March 1998 Re Potential Safety Injection Pump Runout Conditions Identified on 980113.LER 98-002-00 Retracted ML20216H9211998-03-13013 March 1998 Fitness for Duty Program Performance Data Personnel Subject to 10CFR26 ML20248L2811998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Seabrook Station, Unit 1 ML20197A7531998-02-27027 February 1998 Safety Evaluation Accepting License Request for Relief from ASME Code,Section IX Requirements Re Inservice Insp of RHR Heat Exchanger Nozzle Welds & Reactor Vessel Closure Head Nuts ML20202G3701998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Seabrook Station ML20198G0271997-12-31031 December 1997 Commonwealth Energy Sys 1997 Annual Rept ML20248L7711997-12-31031 December 1997 Western Massachusetts Electric 1997 Annual Rept. Supporting Info,Encl ML20198G1021997-12-31031 December 1997 Baycorp Holdings 1997 Annual Rept ML20198N7021997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Seabrook Station, Unit 1 ML20198G0351997-12-31031 December 1997 Eastern Edison Co 1997 Annual Rept ML20198G0681997-12-31031 December 1997 Taunton Municipal Lighting Plant 1997 Annual Rept ML20248L7671997-12-31031 December 1997 North Atlantic 1997 Annual Rept ML20198F9511997-12-31031 December 1997 United Illuminating Co 1997 Annual Rept ML20236M9561997-12-31031 December 1997 Amended Public Service of New Hampshire 1997 Annual Rept 1999-09-30
[Table view] |
Text
,
ENCLOSURE 1 8" kg UNITED STATES NUCLEAR REGULATORY COMMISSION g
n .g ,j WASHINGTON. D. C. 20555 y
4*****$ SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON PUBLIC SERVICE OF NEW HAMPSHIRE SEABROOK NUCLEAR GENERATING PLANT, UNIT NO. 1 DOCKET N0. 50-443 SETPOINT METHODOLOGY FOR ROSEMOUNT REPLACEMENT TRANSMITTERS
1.0 INTRODUCTION
By letter dated February 14, 1986 Public Service of New Hampshire (PSNH) responding to the staff's RAI 420.8, verified that the existing safety-related l instrument channel setpoints as specified in their technical specifications were developed by utilizing the Westinghouse (W) setpoint methodology that had been approved by the staff. According to the licensee this methodology provides two methods of combining error contributors in an instrument measuring I loop. One method is by statistically combining independent (not interactive) errors using the Root Sum Squares (RSS), and the other method is by adding the dependent error components arithmetical 11y. ;
In a later letter dated December 23, 1986, PSNH responded to a request from the !
staff for additional information concerning the proposed setpoint methodology that they intended to use for recently purchased Rosemount transmitters and described a methodology which differed from the W methodology discussed above.
Specifically, PSNH states that based on test results in Rosemount Report 08300076 (" Accuracy of Pressure Transmitters") Revision A dated June 6,1973 they now consider transmitter error from LOCA/HELB conditions to be statistically independent and as such will be combined with other statistically independent channel error in a measuring loop by placing this error contributor under the radical (RSS method). This method of combining the error contributor from LOCA/HELB conditions is considered nonconservative with respect to the W method that combines the same error contributor by adding the error value arithmetical 11y.
8709300314 870924 DR ADOCK 0500 3
l Additionally, the licensee states that their intent is to use this same methodology for all future setpoint calculations at Seabrook Station when applied to Rosemount transmitters. ICSB has reviewed this latter methodology proposed by PSNH and finds that there is not an adequate basis to allow staff approval for it to be used for the replacement Rosemount transmitter at this time. ICSB's evaluation of this issue is discussed below.
2.0 EVALUATION The setpoint methodology that the licensee is proposing for the replacement transmitters from Rosemount is based on data obtained from LOCA/HELB tests of six transmitters tnd described in Rosemount reports D8300040 and 08600010.
Our review of the test results indicate that the drift error of the units during the run of the LOCA/HELB test is not independent but random in nature.
However, the staff believes that the data submitted thus far are insufficient to support this randomness classification, and, therefore find the setpoint methodology proposed by the licensee to be unacceptable at this time. In this regard the licensee may want to conduct additional tests to obtain more supporting data for future Rosemount applications at the Seabrook Station.
One additional concern the staff has considered in determining the acceptability of the proposed setpoint methodology is that the licensee has stated that if the proposed methodology was found to be acceptable by the staff then they intend to use this less conservative approach for all future applications of Rosemount transmitters. The staff does not concur in this generalistic approach. The staff believes that since the proposed setpoint methodology is less conservative than the current method, the licensee, as a minimum to satisfy the concern for
, the health and safety of the public, should study each application of the Rosemount transmitters on a case-by-case basis.
i .
[ -$
.;- , .3-L
3.0 CONCLUSION
l In summary, the ' staff finds the licensee's proposed methodology for establishing setpoint values for the. replacement transmitters from Rosemount not to have an
. adequate basis, at this time, to allow approval for it to be used in the application of these' units to measure pressurizer pressure and steam generator water level at the Seabrook Station.
-. Principal ~ Contributor . Vincent D. Thomas
. Dated:-
SE 241987
^. a. f s
__- __c_____.-_._______._____'__