ML17291A846
| ML17291A846 | |
| Person / Time | |
|---|---|
| Site: | Nuclear Energy Institute |
| Issue date: | 10/16/2017 |
| From: | Pimentel F Nuclear Energy Institute |
| To: | Boland A Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17291A846 (8) | |
Text
FRANCES PIMENTEL Senior Project Manager, Risk and Technical Support 1201 F Street, NW, Suite 1100 Washington, DC 20004 P: 202.739.8132 fap@nei.org nei.org October 16, 2017 Ms. Anne T. Boland Director, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Industry Comments on the Proposed Directors Decision for the Open Phase Condition 2.206 Petition. (ML17156A214)
Project Number: 689
Dear Ms. Boland:
The Nuclear Energy Institute (NEI) 1, on behalf of the industry, appreciates the opportunity to provide industry comments on the Proposed Directors Decision for the open phase condition (OPC) 2.206 petition (ML17156A214).
We understand that in accordance with NRC Management Directive 8.11, Review Process for 10 CFR 2.206 Petitions, the petitioners and appropriate NRC licensees may provide comments on the Proposed Directors Decision. Following a review of comments received, the NRC will consider them and issue a Final Directors Decision with no further opportunity for comment. The industry agrees with the Directors proposed decision to deny the petition. The comments provided herein are intended to promote better alignment between staff and the industry regarding implementation of the NEI OPC voluntary industry initiative (VII) 2.
The VII was developed by the industry as an aggressive action to ensure that an OPC will not prevent the functioning of important-to-safety structures, systems and components at nuclear power plants. As discussed in the VII, an open phase condition is defined as an open phase, with or without a ground, that is located on the high voltage side of a transformer connecting a General Design Criterion (GDC) 17 off-site power circuit to the transmission system. The industry committed to implement OPC solutions that address the objectives and criteria in the VII by the end of 2018.
1 The Nuclear Energy Institute (NEI) is the organization responsible for establishing unified industry policy on matters affecting the nuclear energy industry, including the regulatory aspects of generic operational and technical issues. NEI's members include all entities licensed to operate commercial nuclear power plants in the United States, nuclear plant designers, major architect/engineering firms, fuel cycle facilities, nuclear materials licensees, and other organizations and entities involved in the nuclear energy industry.
2 Nuclear Energy Institute (NEI) Open Phase Condition Initiative (VII), Revision 1, dated March 16, 2015 (ML15075A455, ML15075A456).
Ms. Anne T. Boland October 16, 2017 Page 2 The references to 10CFR50.55a(h)(2) and 10CFR50.55a(h)(3) found in Section C, Applicable NRC Regulatory Requirements and Guidance, of the Proposed Directors Decision are of particular concern to the industry. This section appears to set expectations that designs to address the OPC vulnerability should meet Institute of Electrical and Electronic Engineers (IEEE) Class 1E requirements, which apply only to safety-related structures, systems, and components. The majority of stations are implementing, or have already implemented, Non-1E (non-safety related) OPC modifications, in accordance with the VII. In our view, it is inappropriate to apply IEEE Standard (Std.) 279, Criteria for Protections Systems for Nuclear Power Generating Systems, or IEEE Std. 603, IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations, to an Open Phase Isolation System (OPIS) installed on a Non-Class 1E circuit, because such systems do not scram or trip the reactor, or actuate an engineered safety feature. Furthermore, it is not necessary to apply IEEE Std. 279 or IEEE Std. 603 to OPC detection and actuation systems installed on Non-Class 1E circuits in order to achieve an acceptable level of safety. The approach provided in the VII effectively addresses the vulnerability to OPC events without OPC design compliance to 10 CFR 50.55a(h)(2) and (3). Accordingly, the references to 10CFR50.55a(h)(2) and 10CFR50.55a(h)(3), along with IEEE Std. 279 and IEEE Std. 603 as applied to the OPIS, should be removed from this section.
The attached table contains additional, specific comments and recommendations for your consideration in finalizing the Directors Decision. Below are examples where information in the Proposed Directors Decision appears to be inaccurate or inappropriate and are illustrative of the concerns provided in the attached table:
- 1. The description of the Oconee event inaccurately describes the interim corrective actions implemented at Oconee, which were successful in discovering the open phase condition and in prompting appropriate responses. The interim corrective actions were put in place to allow adequate time for each station to assess specific vulnerabilities and to address them to the appropriate level. Modifications are not complete; therefore automatic alarms in the main control room should not have been expected.
- 2. Equating a design basis event to a loss of offsite power in the case of an open phase condition is incorrect due to the fact that disconnection of faulted offsite power circuits is the protective action. Generally loss of offsite power is considered loss of the grid, and subsequent reliance on the standby power sources. An open phase is a fault that requires the upstream breaker to be opened to isolate the fault from onsite circuits.
An additional concern is that the Proposed Directors Decision discusses a white paper prepared by the NRC that provides a risk assessment of the impact of a postulated loss of a single phase in a three-phase high voltage offsite power circuit 3. The risk assessment supported the proposition that the original, as-discovered electrical configuration of nuclear power plants was susceptible to an OPC, and has the potential to be risk significant.
3 Preliminary Risk Estimate on the Impact of Open Phase Condition (OPC), dated May 16, 2017 (ML17234A631).
Ms. Anne T. Boland October 16, 2017 Page 3 An industry evaluation of the NRCs white paper risk assessment providing the basis for the potential risk characterization identified there are areas of conservatism in the model that could be refined to improve realism in the NRC assessment. For example, the potential increase in risk is overestimated by a factor of 16 to 1,600 depending on the specific plant configuration. Accounting for recent unrelated plant modifications at some plants, the overall core damage frequency and associated potential impact of an OPC on risk have been significantly reduced. Also, the benefit associated with the installation of OPIS is overstated for some facilities. Most plants have two different transformer/voltage regulator paths to the safety related buses. For these plants, an OPC would only impact a single train. Plants with redundant, non-safety related power paths would require a common mode OPC event. This would further lower the risk for those plants. In addition, operator training and awareness of the potential for an OPC contributes to the reduction in risk with or without installation of an OPIS. In summary, the conclusion that the OPIS greatly reduces the vulnerability to an OPC should be tempered given the above observations.
We appreciate the opportunity to comment on the Proposed Directors Decision for the OPC 2.206 petition.
If you have any questions concerning the contents of this letter and the attached table, please contact Steve Geier (202-739-8111; seg@nei.org) or me (202-739-8132; fap@nei.org).
Sincerely, Frances Pimentel Attachment c: John Lubinski, NRR/DE Jessie Quichocho, NRR/DE/EEOB
Attachment Page 1 of 5 NEI/Industry Comments on NRC Proposed Directors Decision for the Open Phase Condition 2.206 Petition Item Page / Proposed Directors Decision Comment Suggested Resolution Section Wording 1 Pg. 6 / The NRC also communicated The NRC provided a letter to NEI containing Re-word to, The NRC communicated four Sect. II.B functional criteria for demonstrating the four functional requirements for functional criteria for demonstrating compliance with existing regulatory demonstrating compliance with existing compliance with existing regulatory requirements. regulatory requirements. requirements in a letter to NEI 2 Pg. 9 / Applicable NRC Regulatory 10CFR50.55a(h)(2) and (3) is listed under References to 10CFR50.55a(h)(2) and Sect. II.C Requirements and Guidance. the header of Applicable NRC Regulatory 10CFR50.55a(h)(3), along with IEEE Std. 279 Continued reference to Requirements and Guidance. This section and IEEE Std. 603 should be removed from 10CFR50.55a(h)(2) and (3) appears to set expectations that designs to this section address the OPC vulnerability should meet IEEE Class 1E requirements, which apply only to safety-related structures, systems, and components. The majority of stations are implementing Non-1E (non-safety related) OPC modifications, in accordance with the VII. In our view, it is inappropriate to apply IEEE Standard Std. 279, or IEEE Std. 603, to an Open Phase Isolation System (OPIS) installed on a Non-Class 1E circuit, because such systems do not scram or trip the reactor, or actuate an engineered safety feature 3 Pg. 9 / Applicable NRC Regulatory Open phase events and design basis events Clarify independence of events in the Sect. II.C Requirements and Guidance. are independent and should not be document.
considered simultaneously. This type of review has already been documented in
Attachment Page 2 of 5 Item Page / Proposed Directors Decision Comment Suggested Resolution Section Wording GSI-171 and clarification of independence of events should be clearly stated.
4 Pg. 11 / Description of the Oconee event. Bulletin response stated open phase was Add to the Oconee event description that Sect. II.D not part of their original design and open phase was not part of Oconees licensing basis. Modifications are not original design and licensing complete at this time; therefore automatic basis; therefore, automatic alarms in the alarms in the MCR should not have been MCR should not have been expected.
expected.
5 Pg. 11, The NRC inspectors determined that The Oconee Bulletin 2012-01 Response It should be noted that the interim Last interim compensatory measures were (ML12300A426) provided the following corrective actions implemented at Oconee Paragraph in place at the facility at the time of the information for Question 1: were successful in discovering the open (in regards event and that the open phase phase which prompted appropriate to Oconee condition was identified during a In both voltage monitoring schemes, responses. The interim corrective actions event) / routine walk-down surveillance, not 230kV and 4160V, there are control room were put in place to allow adequate time Sect. II.D from automatic alarms in the control indications provided for a single phase for each station to assess specific room as expected by the licensee. condition (open circuit). The control room vulnerabilities and to address them to the would receive annunciators and computer level appropriate. The results of these The inspectors noted in the inspection points of an under voltage condition on assessments will determine to what degree report that when the startup that phase, but no automatic trip would be additional modifications are required.
transformer is not supplying the plant initiated. The control room operators buses, there is not enough current flow would respond per the appropriate Alarm .The fact that operators failed to for the installed relays to detect an Response Guide. See Attachment 3 Table 6 receive alarms in the control room open phase condition. The fact that for associated alarms. However, in certain intended to alert them of an open phase operators failed to receive alarms in the cases it is not known if the loss of phase condition during the December 7, 2015, control room intended to alert them of would be detected by the current relaying event at Oconee highlights the need to an open phase condition during the protection schemes to give control room assess potential vulnerabilities in order to December 7, 2015, event at Oconee indication. In general, there will be no plant respond and/or implement modifications
Attachment Page 3 of 5 Item Page / Proposed Directors Decision Comment Suggested Resolution Section Wording highlights the importance of response for an unloaded (e.g., ESF buses accordingly per the NEI Initiative.
implementing permanent design normally aligned to unit auxiliary changes at all affected facilities. transformer) power source in the event of a single-phase open circuit on a credited off-site power circuit because there is insufficient current to detect a single-phase open circuit for this configuration.
The Oconee Bulletin 2012-01 RAI Response (ML14035A453) provided the following information for Response 1:
- 2. ONS Operations personnel perform daily rounds of the switchyards. This is a general observation performed on the equipment to note any out of normal conditions and take appropriate actions.
The daily switchyard rounds procedure was revised to incorporate specific points to look for areas of degraded off site power vulnerabilities.
As predicted in the Bulletin Response, control room alarms were not received due to the lack of current available due to the source being unloaded at the time of the event. In addition, The RAI response provided an interim corrective action for Operations staff to perform daily
Attachment Page 4 of 5 Item Page / Proposed Directors Decision Comment Suggested Resolution Section Wording switchyard rounds which proved to be the method of discovery. The interim corrective actions in their entirety were put in place to allow adequate time for each station to assess specific vulnerabilities and to address them to the level appropriate. The results of these assessments will determine to what degree additional modifications are required.
6 Pg. 12 / The events that occurred at Byron Equating a design basis event to a loss of Detail actual safety significance basis rather Sect. II.D Station, Unit 2, and Oconee Nuclear offsite power in the case of an OPC is than the protective action.
Station are considered by the NRC to be incorrect due to the fact that disconnection safety significant because the of faulted offsite power circuits is the occurrence of the open phase condition protective action. Generally loss of offsite either resulted or could have resulted in power is considered loss of the grid, and a design basis event (i.e., loss of offsite subsequent reliance on the standby power power),. sources. An open phase is a fault that requires the upstream breaker to be opened to isolate the fault from onsite circuits.
Attachment Page 5 of 5 Item Page / Proposed Directors Decision Comment Suggested Resolution Section Wording 7 Pg. 12 / Paragraph starting with, The Excessive conservatisms were included in Remove specific risk values in the letter.
Sect. II.D importance of implementing the risk analysis. Actual risk has already permanent design changes at all been presented and discussed in public affected facilities is further supported meetings. NRC representatives indicated by information in a white paper., and that this overly conservative analysis was the remaining discussion about the only to be used for the methodology to white papers insights. determine real plant risks.
8 Pg. 13 / Based on risk insights derived from the Use of visual inspection in conjunction with Remove the inconsistent reference to Sect. II.D assessment, the NRC staff concluded maintenance intervals is the standard automatic detection of the event.
that the use of visual inspection rounds method for ensuring many of the in switchyard areas alone will have components in the PPS has the capability to minimal benefit for decreasing the allow current to flow to the safety related impact of open phases. However, the components.
use of a detection system and/or automatic actuation system (i.e., OPIS) would greatly reduce this vulnerability.