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Category:Letter type:HNP
MONTHYEARHNP-18-050, Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date2018-09-17017 September 2018 Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date HNP-18-004, License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme2018-08-13013 August 2018 License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme HNP-18-035, Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval2018-06-0404 June 2018 Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval HNP-18-049, Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 192018-05-0303 May 2018 Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 19 HNP-18-023, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes2018-05-0202 May 2018 Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes HNP-18-042, Annual Environmental (Non-radiological) Operating Report2018-04-30030 April 2018 Annual Environmental (Non-radiological) Operating Report HNP-18-032, Annual Radiological Environmental Operating Report2018-04-25025 April 2018 Annual Radiological Environmental Operating Report HNP-18-031, Annual Radioactive Effluent Release Report2018-04-25025 April 2018 Annual Radioactive Effluent Release Report HNP-18-047, Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation2018-04-20020 April 2018 Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation HNP-18-045, Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval2018-04-18018 April 2018 Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval HNP-18-044, Cycle 22 Core Operating Limits Report, Revision O2018-04-16016 April 2018 Cycle 22 Core Operating Limits Report, Revision O HNP-18-039, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2018-04-13013 April 2018 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-18-021, Annual Report in Accordance with Technical Specification 6.9.1.22018-02-19019 February 2018 Annual Report in Accordance with Technical Specification 6.9.1.2 HNP-18-020, Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-02-16016 February 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-019, Cycle 21 Core Operating Limits Report, Revision 12018-02-14014 February 2018 Cycle 21 Core Operating Limits Report, Revision 1 HNP-18-017, CFR 50.54(q) Evaluations2018-02-0505 February 2018 CFR 50.54(q) Evaluations HNP-18-001, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors.2018-02-0101 February 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors. HNP-18-002, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2018-01-22022 January 2018 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-18-003, Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-01-18018 January 2018 Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-007, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations2018-01-11011 January 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations HNP-18-006, Submittal of 14-Day Special Report for Accident Radiation Monitors2018-01-0404 January 2018 Submittal of 14-Day Special Report for Accident Radiation Monitors HNP-17-093, Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 32017-11-29029 November 2017 Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3 HNP-17-078, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-11-27027 November 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-082, Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In..2017-10-30030 October 2017 Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In.. HNP-17-084, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-10-30030 October 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-025, Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan2017-10-23023 October 2017 Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan HNP-17-072, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis2017-10-19019 October 2017 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis HNP-17-077, License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications2017-10-10010 October 2017 License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications HNP-17-076, Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements.2017-10-0202 October 2017 Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements. HNP-17-073, Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-09-14014 September 2017 Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-062, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-09-13013 September 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal HNP-17-061, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-07-20020 July 2017 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-008, License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-06-28028 June 2017 License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-003, License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection2017-06-0505 June 2017 License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection HNP-17-040, Snubber Program Plan2017-06-0101 June 2017 Snubber Program Plan HNP-17-051, 10 CFR 50.54(q) Evaluation2017-05-24024 May 2017 10 CFR 50.54(q) Evaluation HNP-17-050, Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center2017-05-24024 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center HNP-17-041, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete2017-05-22022 May 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Du HNP-17-033, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 112017-05-22022 May 2017 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11 HNP-17-049, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations. HNP-17-047, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-048, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations. HNP-17-046, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-024, Annual Environmental (Nonradiological) Operating Report2017-04-28028 April 2017 Annual Environmental (Nonradiological) Operating Report HNP-17-023, Annual Radioactive Effluent Release Report2017-04-28028 April 2017 Annual Radioactive Effluent Release Report HNP-17-034, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106..2017-04-25025 April 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106.. HNP-17-035, Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator2017-04-12012 April 2017 Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator HNP-17-045, 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation2017-03-30030 March 2017 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation HNP-17-014, Annual Report in Accordance with Technical Specifications, Section 6.9.1.22017-02-16016 February 2017 Annual Report in Accordance with Technical Specifications, Section 6.9.1.2 HNP-17-015, Summary of 10 CFR 50.54(q) Evaluation2017-02-15015 February 2017 Summary of 10 CFR 50.54(q) Evaluation 2018-09-17
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SCP&L James Scarola Vice President AProgress Energy Company Harris Nuclear Plant NOV 2 1 2002 United States Nuclear Regulatory Commission SERIAL: HNP-02-141 ATTENTION: Document Control Desk 10CFR50.90 Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT - RESPONSE TIME TESTING ELIMINATION SUPPLEMENTAL INFORMATION
Dear Sir or Madam:
In a letter dated August 30, 2002 and in accordance with the Code of Federal Regulations, Title 10, Part 50.90, Carolina Power & Light Company (CP&L) requested a revision to the Technical Specifications (TS) for the Harris Nuclear Plant (HNP). The proposed amendment revises Technical Specifications Definitions 1.13, Engineered Safety Features (ESF) Response Time and 1.29, Reactor Trip System (RTS) Response Time. Also proposed in this change request are revisions to Surveillance Requirements 4.3.1.2 and 4.3.2.2 and BASES Sections B 3 /4.3.1 and B 3 /4.3.2. These Ohanges will revise the definition and surveillance requirements for response time testing of the kingineered Safety Feature Actuation System (ESFAS) and the Reactor Trip System. This letter provides additional information to supplement the information provided in the amendment request.
These changes are in conformance with changes approved in WCAP-13632-P-A, Revision 2, and WCAP-14036-P-A Revision 1. These are proprietary documents developed by Westinghouse and approved by the NRC in August 1995, and October 1998, respectively.
The reason for this request is to permit the option of either measuring or verifying the response time for specific components in the above mentioned systems. WCAP-13632-P-A, Revision 2, is for specific pressure sensors and WCAP-14036-P-A, Revision 1, is for instrument loop channels. This option will give HNP an opportunity to eliminate redundant measurement of channel performance without reducing the reliability of these systems. provides additional information that may prove useful as the NRC evaluates the referenced license amendment request.
In accordance with 10 CFR 50.91(b), CP&L is providing the State of North Carolina with a copy of the proposed license amendment.
PO BOX16551L New Hill, NC 27562 f2 Qf )
T> 919362 2502 F> 919362 2095 -,x C)
Please refer any questions regarding this submittal to Mr. J. R. Caves at (919) 362-3137.
Sincerely, RTG
Attachment:
- 1. Supplemental Information in support of the License Amendment request.
James Scarola, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief, and the sources of his information are employees, contractors, and agents of Carolina Power & Light Company.
JBL
....
"Mycommission expires:
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- 1111 8111 Mr. J. B. Brady, NRC Sr. Resident Inspector Ms. Beverly Hall, Section Chief, Radiation Protection Section, N.C. DENR Mr. R. Subbaratnam, NRC Project Manager Mr. L. A. Reyes, NRC Regional Administrator
ATTACHMENT 1 TO SERIAL: HNP-02-141 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT FOR RESPONSE TIME TESTING ELIMINATION FROM TECHNICAL SPECIFICATIONS SUPPLEMENTAL INFORMATION
Background
The following comments provide additional information that may be helpful in the evaluation of the Harris Plant license amendment submittal:
Harris' response to the requirement for confirmation that the generic analysis in WCAP-13632 P-A is applicable to the Harris plant for the following:
- 1. On page El-3 of 13, HNP provides the plant position with respect to performing a hydraulic response time test (RTT) prior to the installation of a new transmitter/switch...
The HNP submittal stated: "...applicable plant procedures include requirements that stipulate that pressure sensor response times must be verified by performance of an appropriate response time test"; for clarification the submittal should say "by the performance of a hydraulic response time test"
- 2. On page El-3 of 13, HNP provides the plant position with respect to transmitters and switches that use capillary tubes and subjecting these transmitters and switches to RTT after initial installation and following any maintenance or modification activity, which could damage the transmitter capillary tubes.
The HNP response included the wording: "...will stipulate that pressure sensors (transmitters and switches) utilizing capillary tubes." This wording should say "that transmitters and switches" and delete the reference to pressure sensors for consistency with the wording in the WCAP.
- 3. On pages El-3 of 13 and El-4 of 13 in items identified as "3" and "4", HNP again uses the terminology "pressure sensors" versus "transmitters and switches." Where the term "pressure sensors" is used it is more consistent with the WCAP to use the terminology "transmitters and switches."
Page 1 of 4
ATTACHMENT 1 TO SERIAL: HNP-02-141
- 4. On page E1-3 of 13 in the item identified as "3", HNP says "HNP has no pressure transmitters..." where it~would be more consistent with the WCAP to say "HNP has no transmitters with variable damping."
- 5. On page El-6 of 13 the HNP submittal stated that WCAP-14620, "7300 Printed Circuit Card Revision History", shows that these components were not affected by any of the changes between artwork level 4 and 6. Also no other changes were identified which could degrade the cards time response." For clarification, a descriptive evaluation of how the Harris Plant reached this conclusion is included as follows:
Per WCAP-14036, actual testing of selected Westinghouse 7300 circuitry with degraded components was conducted to validate the component failure analysis and provide baseline and bounding response times for selected components. Test data for the NSA card is summarized in Table 4-8. The data show that the maximum increase in response time for a 50% increase in capacitance of the most sensitive response time capacitor is 12.5 milliseconds. The response time sensitivity to resistor degradation was minimal (2.5 milliseconds). The response time allocation for this card is 37.5 milliseconds based on the results in Table 4-8. The components degraded for this testing were capacitor C83-1 and R294-1.
A review of the original 7300 card installation records for HNP shows that they were originally all artwork level 4, with the earliest revision level being 12. An inspection of the cards conducted in May of 2002 shows that all of the NSA cards are still artwork level 4 with the exception of certain cards in PIC-01, PIC-02, and PIC-03 that are part of the OTDT (Overtemperature AT) Reactor Trip function. These cards are artwork level 6 type NSA cards.
A review of Westinghouse WCAP-14620, "7300 Printed Circuit Card Revision History", was performed to determine if any changes were made which would adversely affect the card's time response. The conclusion basis that the card's response time is not degraded due to the particular revision is italicized.
A. Revision 13 corrected errors in the bill of material to agree with the assembly and schematics. (No component replacement is documented.)
B. Revision 14 replaced Motorola 741 operational amplifiers (date code 8004) due to oscillation when connected to external test equipment. (The operational amplifier is not a component that was identified in WCAP-14036 as being sensitive to undetectable time response degradation.)
C. Revision 15 corrected typographical error in Bill of Material for item 88 to reflect drawing 4259A57H02. (No component replacementdocumented.)
D. Revision 16 added a verification report number and DEON Control Designation to title page of drawing. (No component replacement documented.)
E. Revision 17 replaced Fairchild 741 operational amplifiers (date codes 8200 through 8252) due to moisture entrapment in can. (The operationalamplifier is Page 2 of 4
ATTACHMENT 1 TO SERIAL: HNP-02-141 not a component that was identified in WCAP-14036 as being sensitive to undetectable time response degradation.)
F. Revision 18 deleted resistor item 37 from the Bill of Material because it was not required. (This component is not listed in WCAP-14036 as being sensitive to undetectable time response degradation.)
G. Revision 19 added ferrite beads to filter out high frequency oscillations in PS17 circuit due to faster transistors. (PSI7 is a power supply circuit on the card and no components on this circuit were identified in WCAP-14036 as sensitive to undetectable time response degradation.)
H. Revision 20 added commercial dedication instruction, test procedure, and shelf life references to drawing. (No component replacementdocumented.)
I. Revision 21 created new artwork level (level 6) that redesigned card to add new group as well as improve reliability, eliminate problems with obsolescence, and improve manufacturability and testability. (Perinspection of this card,there are fewer discrete components that would be subject to time response degradation.
The equivalent component to resistorR294-1 is now R107. Both are 50 K resistors;however, the newer artworklevel 6 card has an improved tolerance of
+0.01% versus the +0.10% of the old card. The equivalent component to capacitorC83-1 is now C38; both capacitorsare the same value of]luF.)
- a. In addition to the above evaluation, it should be noted that the artwork level 6 cards have been successfully response time tested on site per plant procedures MST-10644, MST-10645, and MST-10646 as part of the existing RTT (the latest testing completed during R010 in October, 2001).
This further provides confidence that the changes between artwork level 4 and 6 did not degrade the response time of these cards.
- 6. With respect to Rosemount Model 1154 transmitters as described on page E1-12 of 13, the following describes how a confidence level was obtained for the value of 0.44 seconds that was selected for the bounding response time.
The response time data of Rosemount transmitters from the past eight refueling outages was obtained from the completed HNP Response Time Tests. A total of 35 data points were analyzed to obtain an enveloping value. The worst case value of Rosemount transmitters other than the pressurizer pressure transmitters was 0.13 seconds. A 95/95 statistical analysis was performed on the group of Rosemount transmitters exclusive of the pressurizer pressure transmitter noise analysis data. This resulted in an upper limit of 0.194 seconds. This correlates well with the vendor manual specification of 0.2 seconds for the range codes used at HNP. However, for conservatism, a 95/95 analysis was performed on the range group of Rosemount transmitters with the highest response times (pressurizer pressure transmitters) using the noise analysis data. This resulted in an upper limit time of 0.542 seconds.
However, HNP elected to use a more realistic time of 0.44 seconds for the Rosemount Page 3 of 4
I 4_'.
ATTACHMENT 1 TO SERIAL: HNP-02-141 transmitter time response based upon the most conservative test data obtained during this period. It should be.noted that the noise analysis technique used by HNP is conservative compared to the hydraulic ramp method. For example, the pressurizer pressure transmitter response times ranged from 0.013 seconds to 0.020 seconds using the hydraulic ramp method; however, the noise analysis method results in times from 0.32 seconds to 0.44 seconds. In summary, the 0.44 second value for Rosemount transmitters is based upon the following:
"* The 0.440 seconds is the worst case test result using a conservative test method.
"* The noise analysis testing method used on the pressurizer pressure transmitters produce very conservative results because the process noise is minimal.
"* Hydraulic ramp tests on the pressurizer pressure transmitters produced response times significantly less than the 0.44'seconds.
"* Rosemount supplied information indicates the response time of these transmitters is significantly lower than 0.44 seconds.
"* NUREG/CR-5383 documents response times for these transmitters that are significantly lower than 0.44 seconds Per section 9 of WCAP-13632, Rev.2, allocations for sensor response times may be obtained from: (1) historical records based on acceptable response time tests (hydraulic, noise, or power interrupt tests), (2) in place, onsite, or offsite (e.g. vendor) test measurements, or (3) utilizing vendor engineering specifications. The time allocated by HNP for the Rosemount transmitters envelopes all of these methods.
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