ML20211M726
| ML20211M726 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/30/1999 |
| From: | Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20211M732 | List: |
| References | |
| NUDOCS 9909090192 | |
| Download: ML20211M726 (18) | |
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- 4 Teressee Valle y A#ctity Post Oft:ce Box 2000. Soddy-Daisy. Tennessee 37379 August 30, 1999 l
TVA-SON-TS-99-08 10 CFR 50.90 l l
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U.S. Nuclear Regulatory Commission ATTN: Document Control Desk l Washington, D. C. 20555 Gentlemen: i l
Docket Nos. 50-327 I In the Matter of )
Tennessee Valley Authority ) 50-328 i
SEQUOYAH NUCLEAR PLANT (SQN) - UNITS 1 AND 2 - TECHNICAL SPECIFICATION (TS) CHANGE NO. 99-08, " RESPONSE TIME TEST (RTT) ELIMINATION" l In accordance with the provisions of 10 CFR 50.4 and 50.90, TVA is submitting a request for an amendment to SON's Licenses DPR-77 and 79 to change the TSs for Units 1 and 2.
SON's current TSs require periodic measurement of response times of reactor trip and engineering safety features 3 instrumentation channels. The proposed change would provide an alternative to the requirement of actually measuring the response times. Instead; the respor se times would be verified by summing allocated times for sensors, the process f protection system, the nuclear instrumentation system, and the logic system. These allocated values will be added to the measured times for the actuated devices to initiate their safety function and compared to the overall analysis limits.
The proposed change requires revising the TS definition for
" Engineered Safety Features (ESF) Response Time" and " Reactor hh o' Trip System (RTS) Response Time" to provide for verification {2'7 of response time for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC in accordance with Westinghouse Owner Group Topical Report WCAP-13632-PA, Revision 2. 001.
9909090192 990830 PDR ADOCK 05000327 P PDR
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, o RU.S. . Nuclear Regulatory Commission LPage 2
.. August 30, 1999-TVA has determinedLthat there.are no significant' hazards
. considerations associated.with the proposed change and that the change is' exempt'from environmental' review pursuant to the provisions of 10 CFR 51.22 (c) (9) . The SON Plant Operations Review Committee and the SON Nuclear' Safety Review Board have reviewed'this proposed change and determined that ,
operation of SQN. Units 1 and 2, in accordance with the !
proposed: change, wil1~not endanger the health and safety of the public. Additionally, in accordance with 10 CFR
- 50. 91 (b) (1) , _ TVA is sending.a copy of this letter to the Tennessee State Department of-Public Health.
' Enclosure-1 to this letter provides the description and
. evaluation of the proposed change. This includes TVA's determination that the proposed change does not. involve a
- significant hazards consideration, and is exempt from environmental revie6 Enclosure 2'contains copies of the appropriate TS pages from Units 1 and 2 marked up to show the proposed change. . Enclosure 3 forwards the revised TS pages for Units 1 and 2 which incorporate the proposed change.
L TVA requests that~ approval be provided to support the Unit 1 l Cycle'10 refueling outage scheduled for February 2000. TVA also requests that the-revised TS be made effective within 45 days ~of NRC approval. If you have any questions about this change, please telephone me at (423) '843-7170 or J. D. Smith
'at (423) 843-6672.
Sin ely, k
S as
. Licensing and Industry Affairs Manager Subscribed aqd sworn to efore m o is dote day of //M e 1/n'1 h ~
a bN' 1> J' Notar/ t6blic l' (s
My Commission Expires _pctober 9, 2002 Enclosures cc: Seefpage 3 l
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U.S. Nuclear Regulatory Commission Page 3
. . Augpst 30, 1999 cc (Enclosures):
Mr. R. W. Hernan, Project Manager Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Michael H. Mobley, Director 1(w/o Enclosures)
Division of' Radiological Health Third Floor L&C Annex 401 Church-Street
. Nashville, Tennessee 37243-1532 NRC Resident Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy,. Tennessee 37379-3624 Regional Administrator U.S.. Nuclear Regulatory Commission Region II Atlanta-Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303-3415 L ..i .
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ENCLOSURE 1
, , TENNESSEE VALLEY AUTHORITY SEQUOYAH. NUCLEAR PLANT (SQN)
, UNITS 1 AND 2.
DOCKET NOS. 327 AND 328 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS 99-08 DESCRIPTION AND EVALUATION OF THE PROPOSED CHANGE I. DESCRIPTION OF THE PROPOSED CHANGE TVA proposes to modify the Sequoyah Nuclear Plant (SON)
Units 1 and 2 TSs by revising the TS definition for
" Engineered Safety Features (ESF) Response Time" and
" Reactor Trip System.(RTS) Response Time" to provide for verification of response time for selected components provided that the c.omponents and methodology for verification have been reviously reviewed and approved by the NRC. In addition, the terminology in Surveillance Requirements (SRs) 3.3.1.1 and 3.3.2.1 is being revised from demonstrated, test, and tested, to verified, verification, and verified, respectively. The bases are being revised to indicate where NRC approved the components and methodology for verification.
These changes are described as follows:
- Definition 1.13, ESF Response Time - add "The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC."
- Definition 1.27, RTS Response Time - add "The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC."
- SR 4.3.1.1.3 - Revise the terminology from demanstrated, test, and tested, to verified, verification, and verified.
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SR 4.3.2.1.3 - Revise the terminology from demonstrated, test, and tested to verified, verification, and
. . verified.
- Bases 3/4.3.1 and 3/4.3.2 - Delete the paragraph beginning with " Response time may be demonstrated . . .
and replace with two paragraphs that reference the methodology and bases for NRC approval.
II. REASON FOR THE PROPOSED CHANGE The current SON TSs require periodic measurement of f response times of reactor trip and ESF instrumentation
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channels. The proposed change would provide an I alternative to the requirement of actually measuring the l response times. Instead, the response times would be verified by summing allocated times for sensors, the process protection system, the nuclear instrumentation system, and the logic system. These allocated values will be added to the measured times for the actuated devices to l initiate their safety function and compared to the overall l analysis limits. Elimination of periodic response time j testing (RTT) will result in reduced maintenance testing hours and a reduction in radiation exposure. Since testing is performed during preoutage or outage periods, it will also reduce the number of activities to be performed during the time of complex high activity maintenance schedules that accompany these periods.
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III. SAFETY ANALYSIS
Background
Instrument channel response time is generally the time span from when a monitored variable exceeds a predetermined setpoint at the channel sensor, until the actuated device begins its safety function. The RTT has been an integral part of the TS instrument surveillance program to assure the proper functioning of the sensors and instrumentation loop for ESF and RTS. It verifies that the individual channel / train actuation response times are less than or equal to the maximum values assumed in the accident analysis.
The Westinghouse Owners Group (WOG) performed two analyses to assess the impact of elimination of RTT for instruments and instrument loops. These analyses also discussed alternate test methodologies that would show that the instrumentation was functioning correctly. The first of these analyses was WOG Topical Report WCAP-13632-P-A Revision (Rev.) 2, " Elimination of Pressure Sensor Response Time Testing Requirements," dated August 1995, which was approved by an NRC Safety Evaluation (SE) dated El-2
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September 5, 1995. The second analysis, WCAP-14036-P-A, Rev. 1, " Elimination of Periodic Protection Channel
, , Response Time Tests," dated December 1995 was approved by !
an NRC SE dated October 6, 1998. The NRC SEs approving WCAP-13632-P-A, Rev. 2 and WCAP-14036-P-A, Rev. 1 stipulated certain conditions that individual plant licensees must meet when implementing the guidelines in WCAP-13632-P-A, Rev. 2 and WCAP-14036-P-A, Rev. 1 on a plant specific basis. These WCAPs and the analyses supporting the plant specific requirements form the basis l
for these proposed changes.
l Two tables have been. prepared to identify the equipment affected by this request. Table 1 identifies the equipment that is part of the reactor trip system and Table 2 identifies the equipment that is part of the engineered safety features actuation system (ESFAS).
This request mirrors the request made by Vogtle Electric Generating Plant, the lead plant for the WOG RTT elimination effort. That request was granted by NRC on February 8, 1999. It is also similar to the generic industry request being processed as TSTF-111, Rev. 6.
Basis for Proposed Change for Sensors WCAP-13632-P-A contains the technical basis and methodology for eliminating RTT requirements on sensors l identified in the WCAP. The NRC SE for WCAP-13632-P-A requires. confirmation by the licensee that the generic analysis in the WCAP is applicable to their plant and that licensees take the following actions:
l 1. Perform a hydraulic RTT prior to installation of a new transmitter / switch or following refurbishment of the transmitter / switch (e.g., sensor cell or variable damping components) to determine an initial sensor-specific response time value.
- 2. For transmitters and switches that use capillary tubes, perform an RTT after initial installation, and after any maintenance or modification activity that could damage the capillary tubes.
- 3. If variable damping is used, implement a method to assure that the potentiometer is at the required setting and cannot be inadvertently changed or perform a hydraulic RTT of the sensor following each calibration.
- 4. Perform periodic drift monitoring of all Model 1151, 1152, 1153, and 1154 Rosemount pressure and differential pressure transmitters, for which RTT El-3
elimination is proposed, in accordance with the guidance contained in Rosemount Technical Bulletin
,. , No. 4 and continue to remain in full compliance with any prior ~ commitments to Bulletin 90-01, Supplement 1, t " Loss of Fill-Oil in Transmitters Manufactured by Rosemount." l I
TVA has reviewed the plant data for SON Units 1 and 2. The sensors bounded by the generic analysis contained in WCAP-13632-P-A that are installed in the units are those 4 listed in attached Tables 1 and 2 identified by Note 5. '
To comply with the required actions of WCAP-13632-P-A, TVA will take the following actions:
Response to Item 11 Consistent with the proposed TS changes (including the l
associated bases) and Electric Power Research Institute Report NP-7243, Revision 1, the applicable plant procedures will include revisions which stipulate that pressure sensor response times must be verified by performance of an appropriate response time test prior to placing a sensor into operational service and reverified following maintenance that may adversely affect sensor response time.
Response to Item 2:
Plant procedure revisions (and/or other appropriate administrative controls) will stipulate that pressure sensors (transmitters) utilizing capillary tubes, that can be tested must be subjected to RTT after initial installation and following any activity which could damage i
the transmitter capillary tubes.
Response to Item 3:
SON has no pressure transmitters with variable damping installed in RTS or ESEAS applications for which RTT is required. No SON procedure changes or enhanced administrative controls are required.
l Response to Item 4:
l SON does not have any Rosemount transmitters installed in RTS or ESEAS applications for which RTT is required as shown in Tables 1 and 2. SON provided responses to NRC Bulletins 90-01 and 90-01, Supplement 1, by letters dated July 13, 1990 and March 4, 1993, respectively. These responses define actions SQN would take, should in the future, any of the existing transmitters in RTS or ESEAS l
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l . l applications requiring RTT be replaced with Rosemount transmitters.
Basis for Proposed Changes for Protection Channels WCAP-14036-P-A, Revision 1, contains the technical basis and methodology for elimination of RTT requirements on protection channels identified in the WCAP. The NRC safety evaluation for WCAP-14036-P-A requires confirmation by the licensee that generic analysis in the WCAP is applicable to their plant.
Two tables have been prepared to identify the equipment affected by this request. Table 1 identifies the equipment that is part of the RTS and Table 2 identifies the equipment that is part of the ESFAS. The equipment listed in Tables 1 and 2 is the equipment actually installed at SON. TVA has reviewed the FMEAs in WCAP 14036-P-A Rev. 1 to ensure that they are applicable to this equipment, and the analysis is valid for the versions l of the boards utilized. These tables also identify the l assumed response time being used and how the number was i derived.
IV. NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION TVA has concluded that operation of SON Units 1 and 2, I in accordance with the proposed change to the technical !
specifications (TSs), does not involve a significant hazards consideration. TVA's conclusion is based on its evaluation, in accordance with 10 CFR 50. 91 (a) (1) , of ,
the three standards set forth in 10 CFR 50.92(c). I i
The proposed amendment revises Section 1.0 definitions for
" Engineered Safety Feature (ESF) Response Time" and
" Reactor Trip System (RTS) Response Time" to provide for verification of response time for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC.
In addition, the bases for Surveillance Requirements (SRs) 4.3.1.1.3 and 4.3.2.1.3 are being revised to clarify that
! response time may be verified by actual response time tests l
in any series of sequential, overlapping or total channel measurements, or by the summation of allocated sensor, signal processing and actuation logic response times with actual response time tests on the remainder of the channel.
Allocations for sensor responses times may be derived 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.
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WCAP-13632-P-A, Rev. 2, " Elimination of Pressure Sensor Response Time Testing Requirements," provides the basis and
, ,methodology for using allocated sensor response times in the overall verification of the channel response time for specific sensors identified in the WCAP. Response time verifications for other sensor types must be demonstrated by test. WCAP-14036-P-A Revision 1, " Elimination of Periodic Protection Channel Response Time Tests," provides the basis and methodology for using allocated signal processing and actuation logic response times in the overall verification of the protection system channel response time. The allocations for sensor, signal conditioning, and actuation logic response times must be verified prior to placing the component into operational service and reverified following maintenance that may adversely affect the response time. Periodically sensors, signal conditioning, and logic components are functionally tested. TVA has verified that the selected components installed at Sequoyah are the same manufacturer and model numbers as those components evaluated in WCAPs 13632-P-A and 14036-P-A.
A. The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
This change to the TS does not result in a condition where the design, material, and construction standards that were applicable prior to the change are altered.
The same RTS and engineered safety feature actuation system (ES EAS ) instrumentation is being used, the time response allocations /modeling assumptions in the Chapter 15 analyses are still the same, only the method of verifying time response is changed. The proposed change will not modify any system interface and could not increase the likelihood of an accident since these events are independent of this change.
The proposed activity will not change, degrade or prevent actions, or alter any assumptions previously made in evaluating the radiological consequences of an accident described in the Final Safety Analysis Report. Therefore, the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
! B. The proposed amendment does not create the possibility of a new or different kind of accident from any i accident previously evaluated. l This change does not alter the performance of pressure differential pressure transmitters, solid state protection system racks, nuclear instrumentation, or input and output master / slave relays used in the plant El-6 t
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l 4 L protection systems. Applicable sensors, solid state protection system (SSPS) racks, nuclear
, , instrumentation, and relays will still have response time verified by test prior to placing the equipment in operational service and after any maintenance that could affect the response time of that equipment.
Changing the method of periodically verifying instrument response time for certain instruments from RTT to calibration and channel checks or functional test.will not create any new accident initiators or scenarios. Therefore, the proposed amendment does not involve a significant increase in the probability or consequencesoof an accident previously evaluated.
C. The proposed amendment does'not involve a significant reduction in a margin of safety.
This change does not affect the total system response time assumed in the safety analysis. The periodic l system response time verification method for selected L pressure and pressure differential sensors and SSPS l
racks, nuclear instrumentation, or logic systems is modified to allow use of actual test data or engineering data (various Westinghouse WCAPs). The method of verification still provides assurance that the total system response time is within that assumed in the safety analysis, since calibration checks and functional tests will detect any degradation which might significantly affect equipment response time.
Therefore, the proposed license amendment request does not result in a significant reduction in margin of safety. '
V. ENVIRONMENTAL IMPACT CONSIDERATION The proposed change does not involve a significant hazards consideration, a significant change in the types of or significant increase in the amounts of any effluents that may be released offsite, or a significant increase in individual or cumulative ]
occupational radiation exposure. Therefore, the i proposed change meets the eligibility criteria for i categorical exclusion set forth in 10 CFR 51.22 (c) (9) . l
.Therefore, pursuant to 10 CFR 51.22 (b) , an :
environmental assessment of the proposed change is not j required. I t
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FUNCTION / REACTOR-TRIP SYSTEM / ALLOCATION TIME-/ TABLE 1 NOTES:
T 1. WCAP-14036 R1 evaluated Eagle ~ Cards for response time eliminationLare-P/Ns ERI, EAI, DFP, LCP, .DDC and EPT. All
'these P/Ns.are' applicable for SON (reference. drawings 1-45N-1661-5 through.-8 R0, 1-45N1662-5 through -8 R0, 1-45N1663-4 through -6'RO, 1-45N1664-3 through -4 R0; 2-45N2661-5 through -8 RO, 2-45N2662-5 through --7 R0, j 2-45N2662-8 R1, 2-45N2663-4.through -6 R0, 2-45N2664-3 i
.through~-4 R0, 1,2-47W610-68 series, 1,2-47W610-3 series,
'1,2-47W610-63 seri'es)..
'2. WCAP-13877'R1.and WCAP-13878 R1 evaluated the reliability based onLthe relay environment for Westinghouse Type AR
-relays and Potter & Brumfield MDR series relays, respectively. WCAP-14036 R1 was evaluated for response time.
elimination-and SQN' installed relays are: The solid' state
-protection system (SSPS) slave relays used are either
-Westinghouse Type AR relays or Potter & Brumfield MDR relays, the SSPS input and master relays are G. P. Clare GP1 series, Midtex/AEMCO 156 or Potter & Brumfield KH series type relays (reference drawing 1 & 2-1057E57 Sheets 1 & 2, Contract No. 75380A).
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- 3. . Allocated response time for sensors in this column is from
-SON-SI-IRT-099-400.0 except as noted. For Eagle and relays WCAP-14036 R1 allocated response time is used.
- 4. Sensors for'these transmitters / resistance' temp d9tectors
, (RTDs) were not included in Westinghouse evalb.clon fer l Elimination of Response Time Testing. Therefore, allocated
. sensor time is not used for these variables. These components will continue to be tested as required.
- 5. The sensors installed at SON in this column are evaluated )
for response time elimination and are included in WCAP-13632 !
R1.except those with Note 4. l 6.
~
l -This response time is based on actual onsite test measurements (reference: Evaluation to determine reactor coolant system (RCS) flow transmitter response time for TS Change 99-08, RIMS No. B37990628001).
1 i
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s l' FUNCTION / ENGINEERED SAFETY FEATURE / ALLOCATION TIME / TABLE 2 )
I NOSTS r
- 1. WCAP-14036 R1 evaluated Eagle Cards-for response time elimination are P/Ns ERI, EAI, DFP, LCP, DDC and EPT. All these P/Ns are l
. applicable for SON (Reference Drawings 1-45N-1661-5 through -8 RO , 1-45N1662-5 through -8 R0,-1-45N1663-4 through -6 R0, 1-45N1664-3 through -4 R0; 2-45N2661-5 through -8 R0, 2-45N2662-5 through -7 ROl 2-45N2662-8 R1, 2-45N2663-4 through -6 R0, {
r 2-45N2664-3 through -4 R0, 1,2-47W610-63 series, 1,2-47W610-3 l series, 1,2-47W610-68 series).
- 2. WCAP-13877 R1 and WCAP-13878 R1 evaluated the reliability based on the relay environment for Westinghouse Type Im relays and
. Potter & Brumfield MDR series relays, respectively. WCAP-14036 R1 evaluated for response time elimination and SON installed relays are: The SSPS slave relays used are either Westinghouse I Type AR relays or Potter & Brumfield MDR relays, the SSPS Input- j and Master Relays are G. P. Clare GP1 series, Midtex/AEMCO 156 or Potter.& Brumfield KH. series type _ relays (reference drawing 1 and l i
2-1057E57 Sheets 1 & 2, Contract No. 75380A).
- 3. Allocated response time for sensors in this column is from SON-SI-IRT-099-400.0 except as noted. .For Eagle and relays WCAP-14036 R1 allocated response time is used.
- 4. Sensors for.these transmitters /RTDs were not included in 1 Westinghouse evaluation for elimination of response time testing.
Therefore, allocated sensor time is not used for these variables.
These' components will continue to be tested as required.
~ 5.= The sensors installed at SON in this column are evaluated for response time elimination and are included in WCAP-13632 R1 except those with Note 4.
- 6. The bounding response time allocation for ESF functions is the combination of the longest pick-up or drop-out time for each j relay in the total circuit. signal path for ESF component actuation. Therefore, an additional 36 milliseconds must be
' allocated for each MDR or AR type separation relay (if installed) between the slave relay and end device.
i 4
)
El-14 i
6 i_ .. +
ENCLOSURE 2
, , TENNESSEE VALLEY AUTHORITY
'SEQUOYAH PLANT (SQN)
UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS 99-08 MARKED PAGES I. AFFECTED PAGE LIST ,
Unit 1 1-3 1-5
- 3/4 3-1 3/4 3-14 B 3/4 3-2 Unit 2 1-3 1-6 3/4 3-1 3/4 3-14 B 3/4 3-2 II. MARKED PAGES See attached.
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