ML20245A909
| ML20245A909 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/15/1989 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20245A907 | List: |
| References | |
| NUDOCS 8906220259 | |
| Download: ML20245A909 (13) | |
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ENCLOSURE 1 SAFETY EVALUATION REPORT SEABROOK NUCLEAR STATION, UNIT 1 COMPLIANCE WITH ATWS RULE 10 CFR 50.62 DOCKET NO: 50-443 l
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I.0 INTRODUCTION On July 26, 1984, the Code of Federal Regulations (CFR) was amended to include Section 10 CFR 50.62, " Requirements for Reduction of Risk from
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Anticipated Transients Without Scram (ATWS) Events for Light-Water-Cooled
' I Nuclear Power Plants" (known as the ATWS Rule). The requirements of Section 10 CFR 50.62 apply to all comercial light-water-cooled nuclear i
power plants.
An ATWS is an anticipated operational occurrence (such as loss of I
feedwater, loss of condenser vacuum, or loss of offsite power) that is accompanied by a failure of the Reactor Trip System (RTS) to shut down the j
reactor. The ATWS Rule requires specific improvements in the design and 4
operation of comercial nuclear power facilities to reduce the probability j
of failure to shut down the reactor following anticipated transients and l
to mitigate the consequences of an ATWS event.
Paragraph (c)(1)of10CFR50.62specifiesthebasicATWSmitigation system requirements for Westinghouse plants. Equipment, diverse from the i
RTS, is required to initiate the auxiliary feedwater (AFW) system and a turbine trip for ATWS events.
Inresponsetoparagraph(c)(1),the Westinghouse Owners Group (WOG) developed a set of conceptual ATWS mitigating system actuation circuitry (AMSAC) designs generic to Westinghouse plants. WOG issued Westinghouse Topical Report WCAP-10858, l
"AMSAC Generic Design Package," which provided information on the various Westinghouse designs.
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The staff reviewed WCAP-10858 and issued a safety evaluation of the subject topical report on July 7, 1986 (Ref. 1).
In this safety evaluation, the staff concluded that the generic designs presented in WCAP-10858 adequately meet the requirements of 10 CFR 50.62. The approved version of the WCAP is labeled WCAP-10858-P-A.
During the course of the staff's review of the proposed AMSAC design, the
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WOG issued Addendum 1 to WCAP-10858-P-A by letter dated February 26, 1987 (Ref. 2). This Addendum changed the setpoint of the C-20 AMSAC permissive signal from 70% reactor power to 40% power. On August 3, 1987, the WOG issued Revision 1 to WCAP-10858-P-A (Ref. 3) which incorporated
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Addendum 1 changes and provided details on changes associated with a new variable timer and the C-20 time delay.
For those plants selecting either the feedwater flow or the feedwater pump / valve status logic option, a
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variable delay timer is to be incorporated into the AMSAC actuation logics. The variable time delay will be inverse to reactor power and will j
approximate the time that the steam generator takes to boil cown to the low-low level setpoint upon a loss of main feedwater (MFW) from any given reactor power level between 40% and 100% power. The time delay on the C-20 permissive signal for all logics will be lengthened to incorporate the maximum time that the steam generator takes to boil down to the low-low level setpoint upon a loss of MFW with the reactor operating at 40% power. The staff considers the Revision 1 changes to be acceptable.
Paragraph (c)(6) of the ATWS Rule requires that detailed information to
'l demonstrate compliance with the requirements be submitted to the Director, Office of Nuclear Reactor Regulation (NRR).
In accordance with paragraph (c)(6) of the ATWS Rule Public Service of New Hampshire (PSNH) (licensee) i provided infonnation by letter dated December 15,1988(Ref.4). The letter forwarded the detailed design description of the ATWS mitigating system actuation circuitry proposed for installation at the Seabrook Nuclear Station, Unit 1.
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. i The staff held a conference call with the licensee on February 16, 1989 to discuss the AMSAC design. As a result of the conference call, the i
staff's concerns were resolved and the licensee responded to the action items by letter dated March 15, 1989 (Ref. 5).
l 2.0.
REVIEW CRITERIA The systems and equipment required by 10 CFR 50.62 do not have to meet all of the stringent requirements normally applied to safety-related equipment. However, the equipment required by the ATWS Rule should be of sufficient quality and reliability to perform its intended function while minimizing the potential for transients that may challenge the safety systems, e.g., inadvertent scrams.
The following review criteria were used to evaluate the licensee's submittals:
1.
The ATWS Rule, 10 CFR 50.62.
2.
" Considerations Regarding Systems and Equipment Criteria,"
published in the Federal Register, Volume 49, No. 124, dated June 26, 1984.
3.
Generic Letter 85-06, " Quality Assurance Guidance for ATWS Equipment That Is Not Safety Related."
4.
Safety Evaluation of WCAP-10858 (Ref.1).
5.
WCAP-10858-P-A, Revision 1 (Ref. 3).
3.0 DISCUSSION AND EVALUATION To determine that conditions indicative of an ATWS event are present, the licensee has elected to implement the WCAP-10858-P-A AMSAC design associated with monitoring the steam generator water level and activating I
l 1 l the AMSAC when the water level is below the low-low setpoint established 1
for the reactor protection system (RPS). Also, the licensee will implement the new time delay (described in the introduction section) associated with the C-20 permissive consistent with the requirements of 1
Revision 1 to the WCAP.
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Many details and interfaces associated with the implementation of the I
final AMSAC design are of a plant-specific nature.
In its safety evaluation of WCAP-10858, the staff identified 14 key elements that
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require resolution for each plant design.
The following paragraphs l
provide a discussion on the licensee's compliance with respect to each of the plant-specific elements.
1.
Diversity The plant design should include adequate diversity between the AMSAC equipmentandtheexistingReactorProtectionSystem(RPS) equipment. Reasonable equipment diversity, to the extent practicable, is required to minimize the potential for common-cause failures.
The licensee has provided information to confinn that the AMSAC logic circuits will be diverse from the logic circuits of the RPS in the areas of design, equipment, and manufacturing. Where similar types components are used, such as output relays, the AMSAC will utilize a relay of a different irake and manufacturer.
2.
Logic Power Supplies Logic power supplies need not be Class IE, but must be capable of performing the required design function upon a inss of offsite power. The logic power must come from a power source that is independent from the RPS power supplies.
I The licensee has provided information verifying that the logic power l
supplies selected for the Seabrook Station 1 AMSAC logic circuits will provide the maximum available independence from the RPS power supplies.
The AMSAC will be powered from nonsafety-related power supplies which will be independent of the RPS and capable of operating upon a loss of offsite power.
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Safety-Related In,terface i
The implementation of the ATWS Rule shall be such that the existing l
RPS continues to meet all applicable safety criteria.
l The proposed AMSAC design interfaces at its input with the existing Class 1E circuits of the steam generator level instrumentation and the turbine first-stage pressure instrumentation. At its output, the AMSAC will interface with the Class IE circuits of the station's Emergency Feedwater System (EFW). Connections to these Class IE circuits will be made through the use of approved Cless 1E isolation devices. The licensee has confirmed to the staff that the existing safety-related criteria, as described in Section 7.0 of the Seabrook j
Station FSAR will continue to be met after the implementation of AMSAC (i.e., the RPS will continue to perform its safety functions without interference from AMSAC). Refer to Item 9 for further discussion on this issue.
4.
Quality Assurance The licensee is required to provide information regarding compliance with Generic Letter (GL) 85-06, " Quality Assurance for ATWS Equipment That Is Not Safety Related."
The criteria of the NRC quality assurance guidance (GL 85-06) were reviewed by the licensee. The licensee stated that the quality
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- assurance practices at the Seabrook Station, as applicable to nonsafety-related AMSAC equipment, comply with the guidance of GL 85-06.
5.
Maintenance Bypasses Information showing how maintenance at power is accomplished should i
be provided.
In addition, maintenance bypass indications should be incorporated into the continuous indication of bypass status in the control room.
The licensee provided infomation showing how maintenance will be accomplished at power. The staff was informed that maintenance at power will be performed by inhibiting (through a test bypass switch) the operation of AMSAC's output relays which will block the output signal.and, thus, prevent it from reaching the final actuation devices.-
The continuous indication of bypass status will be provided in the main control room through the use of status lights and annunciation as provided by the Video Alann System.
It is the staff's understanding l
that the licensee will conduct a human-factors review of the subject indication consistent with the station's control room design process.
l 6.
Operating Bypasses The operating bypasses should be indicated continuously in the control room. The independence of the C-20 permissive signal should be addressed.
The licensee has provided information stating that an AMSAC operating bypass (C-20) will be used to enable the operators to bring the station up in power during startup and to avoid spurious AMSAC actuations at power levels below 40% reactor power (the C-20 setpoint). Above 40% reactor power, the C-20 will automatically arm the AMSAC logics. The C-20 permissive signal will be maintained for a period of 360 seconds upon a decrease in power below 40% reactor
.. power. This is consistent with that' stated'in Revision.1 to WCAP 10858-P-A.- The licensee has determined that the time delay.
will be sufficient to ensure that AMSAC will perform its function in the event of a turbine trip (loss of. load ATWS). The C-20 pemissive signal will originate from existing Class IE first-stage turbine impulse chamber pressure sensors. This signal, taken downstream from qualified isolators, will not interfere with the RPS and will be processed by the AMSAC logic which will be diverse from the reactor protection system. The C-20 bypass status will be continuously indicated in the control room when the reactor is above the 40% power level. This indication will be consistent with the human-factors-guidelines in effect at the plant.
7.
Means for Bypasses The means for bypassing shall be accomplished by using a permanently installed, human-factored, bypass switch or similar device. Disallowed methods for bypassing mentioned in the guidance should not be used.
The licensee's response stated that a permanently installed control switch located in the control room will be used for the bypass function.
The disallowed methods for bypassing such as lifting leads, pulling fuses, blocking relays, or tripping breakers will not be used. It is the staff's understanding that the licensee will conduct a human-factors review of the bypass controls and annunciation consistent with the station's detailed control room design process.
8.
Manual Initiation Manual initiation capability of the AMSAC function must be provided.
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The licensee discussed how manual turbine trip and EFW actuation are accomplished by the operator.
In summary, the operator can use existing manual controls located in the control room to perform a turbine trip and to initiate EFW chould it be necessary. Thus, no additional manual initiation capability is required as a result of installing the AMSAC equipment.
i 9.
Electrical Independence From Existing Reactor Protection System l
Independence is required from the sensor output to the final l
actuation device, at which point nonsafety-related circuits must be isolated from safety-related circuits by qualified Class IE l
1solators.
The licensee discussed how electrical independence is to be achieved. The proposed design requires isolation between the non-Class IE AMSAC and the Class IE circuits associated with the steam generator (SG) level, the turbine first-stage impulse chamber pressure, and the EFW pumps.
The licensee has informed the staff that the required isolation will be achieved using electrical isolation devices that have been qualified and tested to Class 1E electrical equipment requirements.
In addition, the isolators were tested as described in Appendix A to the safety l
evaluation (Ref.1) and thus, are acceptable for use at Seabrook Station i
as qualified isolators for this application. The implementation of the AMSAC design will be consistent with the electrical separation criteria
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established for the Seabrook Station during original plant licensing.
- 10. Physical Separation From Existing Reactor Protection System J
The implementation of the ATWS mitigating system must be such that the separation criteria applied to the existing RPS are not violated.
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The licensee stated that the AMSAC circuitry will be physically separated from the RPS circuitry. The licensee has further stated that the AMSAC cable routing will be independent of protection system cable routing and that the ATWS equipment cabinets.will be located so that there will be no interaction with the protection system cabinets. The licensee also stated ~that the RPS-design will continue (subsequenttotheimplementationofAMSAC)tomeetthe separation criteria originally established for.the Seabrook Station during initial plant licensing, as discussed in Section 7.1.2.2 and Section 8.3.1.4 of the Seabrook Station FSAR.
- 11. Environmental Qualification The plant-specific submittal should address the environmental qualification of ATWS equipment for anticipated operational occurrences.
The licensee stated that AMSAC mitigation equipment will be located in areas of the station that are considered to be a mild environment.
The licensee also stated that the equipment will be designed to' operate in the environent for anticipated operational occurrences that might occur associated with the respective equipment locations.
- 12. Testability at Power Measures to test the ATWS mitigating system before initial operation as well'as periodically, are to be established. Testing of the system may be perfonned with the system in the_ bypass mode.. Testing from the input sensor through'to the final actuation device should be perfonned with the plant shut down.
The licensee stated that a complete end-to-end test of the AMSAC-system, including the AMSAC outputs through the final
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l actuation devices, will be performed during each refueling outage.
With the plant at power, the system can be tested with the AMSAC outputs bypassed. This bypass will be accomplished through a permanently installed bypass switch which will negate the need to lift leads, pull fuses, trip t~eakers, or physically block relays.
The testing capability will consist of a series of overlapping tests.
These tests will verify analog channel accuracy, setpoint (bistable trip) accuracy, and coincidence logic operation including operation and accuracy of all timers.
Status outputs to the Video Alarm System and main control board; indicating that a general warning condition exists with AMSAC w111 be initiated when the system's outputs are bypassed. The 3
station procedures will be used when testing the AMSAC circuitry and the AMSAC outputs. These procedures will ensure that AMSAC is returned to service when testing is complete.
It is the staff's understanding that the licensee will conduct a human-factors review of the controls and indications used for testing purposes consistent with the station's detailed control room design process.
- 13. Completion of Mitigative Action
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The licensee is required to verify that (1) the protective action, j
once initiated, goes to completion and (2) the subsequent return to l
operation requires deliberate operator action.
The licensee responded that the AMAC system design will be such that AMSAC oction will be consistent with the circuitry of the emergency l
feedwater and turbine trip control systems. Once initiated, the i
design will ensure that protective action goes to completion. Following l
completion of the mitigative action, deliberate operator action will then be required to return the actuated systems to normal operation.
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. 14. Technical Specifications The plant specific submittals should address technical specification requirements for AMSAC.
The licensee responded that no technical specification action is proposed with respect to the AMSAC and that nonnal administrative controls are sufficient to control AMSAC.
The equipment required by the ATWS Rule to reduce the risk associated with an ATWS event must be designed to perform its functions in a reliable manner. A method acceptable to the staff for demonstrating that the equipment satisfies the reliability requirements of the ATWS Rule is to provide limiting conditions for operation and surveillance requirements in the technical specifications.
In its Interim Commission Policy Statement of Technical Specification j
Improvements for Nuclear Power Plants [52 Federal Register 3788, l
February 6,1987], the Commission established a specific set of objective criteria for determining which regulatory requirements and operating i
restrictions should be included in technical specifications. The staff is l
presently reviewing ATWS requirements to criteria in this Policy Statement to determine whether and to what extent technical specifications are appropriate. Accordingly, this aspect of the staff review remains open I
pending completion of, and subject to the results of, the staff's further review. The staff will provide guidance regarding the technical specification requirements for AMSAC at a later date.
4.0 CONCLUSION
The staff concludes, based on the above discussion and pending resolution of the technical specification issue, that the AMSAC design proposed by
. Public Service of New Hampshire for the Seabrook Nuclear Station, Unit 1 is acceptable and is in compliance with the ATWS Rule, 10 CFR 50.62, paragraph (c)(1). The staff's conclusion is further subject to the successful completion of certain noted human-factors engineering reviews.
Until staff review is completed regarding the use of technical specifications for ATWS requirements, the licensee should continue with the scheduled installation and implementation (planned operation) of the ATWS design utilizing administratively controlled procedures.
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5.0 REFERENCES
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l 1.
Letter, C E. Rossi (NRC) to L. D. Butterfield (WOG), " Acceptance for Referencing of Licensing Topical Report," July 7,1986.
i 2.
Letter, R. A. Newton (WOG) to J. Lyons (NRC), " Westinghouse Owners Group Addendum 1 to WCAP-10858-P-A and WCAP-11233-A: AMSAC Generic Design Package," February 26, 1987.
3.
Letter, R. A. Newton (WOG) to J. Lyons (NRC), Westinghouse Owners Group Transmittal of Topical Report, WCAP-10858-P-A, Revision 1 AMSAC Generic Design Package," August 3, 1987.
4.
Letter, G. S. Thomas (PSNH) to U.S. NRC, "ATWS Mitigation System,"
December 15, 1988.
5.
Letter, G. S. Thomas (PSNH) to U.S. NRC, "ATWS Mitigation System,"
March 15, 1989.
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