ML20245J267
| ML20245J267 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/13/1989 |
| From: | Whittier G Maine Yankee |
| To: | Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| GDW-89-209, MN-89-80, NUDOCS 8906300257 | |
| Download: ML20245J267 (40) | |
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Mainelyankee RELIABLE ELECTRICITY h0A MAINE SINCE 1972 EDISON DRIVE . AUGUSTA, MAINE 04330 . (207) 622 4868 June 13, 1989 HN-89-80 GDH-89-209 Region.I-United States Nuclear Regulatory Commission 475 Allendale Road
- King of Prussia, PA 19406 Attention: Mr. William.T. Russell, Regional Administrator
References:
(a) ~ License No. DPR-36 (Docket No. 50-309)
(b) USNRC Letter to Maine Yankee dated Harch 27, 1989 - NRC
-Safety System Functional Inspection Team Report No.
50-309/89-80 (c) . Maine Yankee Letter to USNRC dated May 30, 1989 (MN-89-74),
Component Cooling Heat Balance
Subject:
Response to NRC Safety System Functional Inspection Team Report No. 50-309/89-80 Gentlemen:
During January and February of this year, an NRC Team conducted a Safety.
System Functional Inspection (SSFI) at Maine Yankee. Reference (b) reported j the results of the inspection. The report documents the NRC team's conclusions as to perceived strengths and weaknesses in the areas inspected and requested a response. This letter contains Maine Yankee's responsa tc the
.SSFI report.
He found the SSFI inspection to be an intense but rewarding experience.
Through it we were able to confirm the fundamental validity and value of our on-going design basis recovery program. He also learned from the. team how to improve some aspects of our program. Of particular note, we feel, was the effective and professional exchange of information between our staff and the team members on a wide variety of technical and safety topics'. Our staff respected and appreciated the focus of the team on safety performance and the itillingness of team members and leaders to explain and discuss the bases for I their positions, i
Certain items were mentioned specifically in the cover letter transmitting the SSFI report. These items-are discussed briefly below. The attachments to this litter contain more detailed responses to the items discussed in the inspection report.
8906300257 890613 PDR .ADOCK 05000309 o PDC
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MaineYankee United States Nuclear. Regulatory Commission Page two Attention: Mr. Hilliam T. Russell MN-89-80 NRC Suaaestion: DC Power Buses - reconsideration of operability and reliability Maine Yankee Resoonse:
During the inspection, Maine Yankee _ changed .the procedure whi,4 governs DC bus cross-tie to provide a caution with respect to the cross-tie issue.
He have evaluated this issue further and plan to implement additional procedural controls. Refer to Attachment 1, response to Issue 2.
He have evaluated the concern about control of operability of DC buses in lower operating modes and plan to implement procedural controls to administrative 1y extend the applicability of Technical Specification j requirements for emergency power supply operability to lower operating j modes. Refer to Attachment 1, response to Issue 2. !
NRC Suaaestion: Short-Term Application of Probabilistic Risk Assessment (PRA)
Haine Yankee Resoonse:
Maine Yankee's PRA effort continues as discussed with the SSFI team. 1 Application of PRA in the sMet term is being made in review of shift ,
operations (described in more detail in Attachment l', response to !
Issue'1),
Inverter reliability has been addressea by implementation of a program of inspections and replacements of key components established in consultation ,
with the manufacturer and based on Maine Yankee's experience. The program (
includes performance measurements taken on-line as well as preventive j l-maintenance (PH) actions'at intervais of 1, 2, 3, and 6 refuelings. As a j result of this aggressive program to improve inverter reliability, which }
was instituted prior to either the SSFI or availability of PRA Phase I {
L results, there have been no inverter failures since the reliability issue j l was recognized. In addition to this PM program, an engineering effort to further develop the inverter reliability program was already scheduled.
The residual heat removal heat exchanger inlet valve reach reds and i controls are being addressed as a high priority item as discussed in l Attachment 1, response to Issue 1.
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x 4 MaineYankee-United States Nuclear Regulatory Commission Page three Attention: Mr. Hilliam T. Russell MN-89 80
.)i NRC Sugaestion: Improve Conservatism in Use of Component Replacement Procedures j!
Maine Yankee Resoonse: j He agree that in the cases of the battery replacements and Radiation Monitoring System (RMS) upgrades, use of a design change may have been the better approach.
f 1
In both cases, engineering and management were heavily involved in the '
planning, technical evaluation, and authorization of the work, and in both cases the results of the work were an improvement in plant safety and j reliability. 1 He have concluded that we should clarify our definition of design change and provide better guidance on how to decide whether.to handle a change as I a component substitution or a design change. Refer to Attachment 1, response to Issue (5).
Our specific responses to the issues enumerated in Section 1, Executive Summary, of Reference (b) are provided'in Attachment 1. The priority and schedule for commitments made during the course of the SSFI (as response to specific issues in the Inspection Report) are provided in Attachment 2.
Should you have any questions regarding our response, please contact me.
Very truly yours, MAINE YANKEE
...h/gf Agh c G. D. Whittier, Manager Nuclear Engineering and Licensing q JHG:BPB
' Attachments as stated c: Mr.. Richard H. Hessman Mr. Hilliam F. Kane
.Mr. Patrick M. Sears Mr. Cornelius F. Holden i
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ATTACHMENT 1 a s:
Executive Summary Issues Resoonse Issue (1):
An inconsistent safety perspective exemplified by your approach to resolving several longstanding problems such as: the root cause of the failures associated with valves PCC-43 and SCC-165 (Sections 3.1.1 and 3.1.4); the lack of control of instrument setpoints and a formal program to address instruments found out of calibration (Sections 3.3.1 and 2);
and, the role of Maine Yankee's QA audit program in identifying certain of those programmatic findings identified by the SSFI team.
Maine Yankee Resoonse:
Maine Yankee places a high priority on operating in a safety conscious ;
manner. He emphasize safety through continued use of currently employed -
management and leadership processes, and adoption of some newer management I processes.
One such new management process, described in general terms, involves focusing the Nuclear Safety Section (NSS) on independent review of the implications of potential safety issues using an enhanced awareness of overall plant safety gained through familiarity with the Maine Yankee PRA. -This focus has been instituted as a result of insights gained from i the SSFI team. l During the SSFI, we briefed the NRC inspection team on the progress made to date in the PRA effort. To date. Phase I has been completed. This
-phase addresses core melt probability. The final Phase I report has been issued to each member of the Nuclear Safety Section for familiarization, and the NSS staff is receiving training on the PRA. This PRA familiarity and training is already being put to use in on-shift review of plant
.rtatus and operation. Results of this review are provided on shift to the Plant Shift Superintendent, and also brought to.the daily management )
meeting by the NSS representative i As the ongoing PRA work progresses through Phase II (containment response) and Phase III-(off site consequences), and as the resulting detailed plant
- pecific -safety insights flow into the operating organization, we believe the result will be a more consistent ability to recognize and deal with potentir.lly safety significant plant issues.
i Another new process involves assigning members of the Plant Engineering d Department (PFD) to long term assignments in the maintenance organization. Additional staffing has been authorized for this purpose and new personnel are being hired. This will more closely link the maintenance and engineering functions technically as,d organizationally.
We believe this closer linkage will provide the engineering division with an additional channel of communication for identification of maintenance problems where engineering evaluation could help ensure a timely and comprehensive resolution. This organizational enhancement will also free maintenance supervisors from some of the more engineering oriented aspects 1 of.their duties and allow them to concentrate more on actual supervision of maintenance work in progress.
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- . TTACHMENT 1 (Sheet 2 of 10)
A further initiative involves increased engineering staffing in the PED plant based reliability unit. This part of PED monitors, measures, and tests performance of key plant equipment and assists in identifying and resolving plant equipment reliability questions. An engineer has recently joined Maine Yankee to fill an additional authorized position.
He believe the increased focus on plant safety and equipment reliability l described above, and the increase in engineering staff available to support safety initiatives and resolution of problems will provide an improvement in the consistency of Maine Yankee's safety perspective.
Responses to the specific items mentioned in this finding are provided below.
Valves PCC-M-43 and SCC-M-165:
Modifications that were previously identified as necessary to improve the reliability of these valves are currently scheduled to be 1 completed by August 31, 1989. These modifications include changing the closing circuits to close on limit and installing mid-span bearing l guides on the reach rods.
Control of Instrument Setooints:
Maine Yankee will develop a setpoint basis document and implement procedure changes required to control setpoint revisions, currently scheduled for completion by December 31, 1989. Loop accuracy calculations are scheduled to be included in the basis document.
Calibration procedures are scheduled to be revised, to agree with the calculations, during the procedure review cycle subsequent to December 31, 1989, and all should be revised by December 31, 1991.
Instruments Found Out of Calibration: ,
(Note - The applicable report secticn is 3.3.3)
The Instrumentation and Controis Section Preventive Maintenance Program is currently scheduled to be revised, by the 1990 refueling outage, to provide a formal review of as-found conditions when performing calibrations Role qf_Riine YAnhe's OA._Agdit Program: ,
The fundamental role of the QA Audit Program is to evaluate the output j of selected Maine Yankee processes for technically significant i deviations that have nuclear safety and reliability implications. l This includes continuing evaluations of the capabilities of Maine Yankee internal self-assessment processes to find and correct substantive technical problems and to prevent problem recurrence. The Audit Program retains its traditional mandate to verify compliance with 10CFR50 Appendix B, committed standards and Regulatory Guides. ,
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ATTACHMENT 1 (Sheet 3 of 10) 1' l As of January, 1988 Maine Yankee management renamed the QA Department l l- the Quality Programs Department (QPD), and gave the new department manager direction to develop and implement means to. evaluate performance. Since then, a number of process changes have been implemented to improve the ability of the Audit Program to identify and resolve performance issues.
Performance-based inspection training has been provided to both Yankee Atomic and Maine Yankee Auditors, using the same contractor program used by the NRC for training of their own inspectors.
" Performance-based findings", in this context, means those that have nuclear safety and reliability impact.
The Audit Program is focused on monitoring of actual plant activities. The audit schedule has been modified, where possible, to coincide with the plant activities of interest. Recent examples include the ISI/IST Audit and the Radcon Implementation Audit conducted during the 1988 refueling outage.
Root cause training is being provided to department managers and selected section heads and supervisors. In addition, three QA Engineers have. received root cause training. The QA Supervisor has been trained to facilitate cross functional problem solving groups, called Performance Improvement Teams. The first test of this group process began May 10, 1989, with the first formal meeting of the DR/R0 Performance Improvement Team which was chartered by the President of the Company.
The Audit Program is one input to the Maine Yankee Corrective Action System (Procedure 0-16-1). This procedure was revised in November 1988' to improve the Company's ability to identify recurrences and to improve effectiveness of correctivo actions. These changes include new reaMrements to determine whether each deficiency is a recurrence ani to request more complete corrective action response, including root cause determination, for lower tier findings which have recurred.
Audit reports have been reformatted to explicitly state the performance basis for each finding where such basis exists. The Assurance of Quality (A00) Section of each report contains the audit i team's evaluation of the effectiveness of internal asse!,sment systems related to the functional area being audited '
Pre-audit meetings with the audited organizations, OPD representative (s), and the designated audit team leaders, are used to ensure that audit plans include importar,t areas Of concern. This, along with technical specialist support from three other Yankee plants, has been instrumental in producing substantive a performance-based audits of MY programs and processes. MY upper management has given the Audit Program freedom to audit MY functional .
areas against broad industry standards of performance rather than only l against narrowly defined committed standards. Recent examples of this new approach include 1989 audits of Security, Procurement and Training. .
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AIIA_CHMENT 1 (Sheet 4 of 10) l In sum, the QA Audit Program has been upgraded to be more attuned to I the nuclear safety and reliability issues encountered during audits l
and within related problem identification and corrective action processes. The Quality Programs Department Manager and Maine Yankee management are continuing to seek out and implement further improvements to the Audit Program. In addition, the Department is working to sharpen the safety perspective of the Company through the Performance Improvement Team process and root cause training.
Issue (2):
Technical Specifications or other administrative controls which do not address the ability to cross-tie direct current (DC) buses 1 and 3, thus allowing a common mode failure to render both diesel generators inoperable, and that do not place any restrictions on the removal from service of all DC buses when shut down (Section 3.2.5).
Maine Yankee Resoonut:
Cross-tie DC Buses It has not been customary to cross-tie the DC buses unless there has been a case of immediate need for battery bank or battery charger maintenance. In the case of battery bank maintenance, cross-connecting the buses seems prudent at least for a limited time since the cross-tie provides a backup source of power in the event of battery charger failure to the bus with its respective battery bank disconnected. In the case of battery charger maintenance, cross-connecting the buses seems prudent, again for a limited time, because it providet for the battery benk, on the affected bus, to be maintained at full charge while its respective battery charger is disconnected for maintenance. He believe that the concern for cross-tieing DC buses can be adquately addressed by application of appropriate administrative controls.
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I 4 a: ATTACHMENT-1 (Sheet 5 of 10) u ...
? Recognizing that the plant is more susceptible to a common mode H failure while the #1 and #3 DC buses are cross-connected, Procedure
'1-22-2, BATTERY AND. VITAL BUS OPERATION, was revised during the inspection, via.a Procedure Change Report, to provide a precaution with respect to the cross-tie issue. , The following additional administrative controls will be placed in effect:
- Procedure A0P 2-13, LOSS OF A VITAL DC BUS, will be revised to-
- ensure that all cross-connecting is done in accordance with E Procedure 1-22-2, BATTERY AND VITAL BUS OPERATION.
- Procedure 1-22-2, BATTERY AND VITAL BUS OPERATION, will be revised to include the following restrictions:
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- 1. Whenever the plant is in Condition 6 or above cross-connecting DC buses 1 and 3 will be limited to a maximum of seven days.
The seven-day time period-would be consistent with the remedial action statement of Technical Specification 3.12 for the loss of a DC bus and should be a reasonable amount of time to repair a battery charger should one become unavailable.
- 2. At the end of the seven-day period, if the DC buses 1 and 3 must remain cross-connected, the plant will be shutdown in accordance with Technical Specification 3.0. A.
These additional' actions are currently scheduled to be completed by June 30. 1989.
EC Buses When Shutdown Technical Specification 3.8 specifies the conditions of plant equipment necessary to ensure the capability to remove energy from the reactor core. Included as acceptable. cooling mechanisms are the Residual Heat Removal System Train A and the Residual Heat Removal System Train B'. .These systems are but two of six cooling mechanisms that could be used to achieve compliance with this specification.
Although not required by Technical Specification 3.8, it has been the past practice, at Maine Yankee, to raaintain at least two power sources available to the RHR systems when they were being utilized to meet compliance with this specificnion. However, in crder to further ercure increased reliability of the RHR Systems, when they are required to be operable, Procedure 1-22-2, BATTERY MD VITAL BUS OPERATION, and Frocedure 1-7-2, OPERATIONS AT COLD SHUTDONN. will be revised as follows:
l' Whenever Residual Heat Removal (RHR) System Train A or B are required to be operable, its respective DC bus, with its associated battery bank connected, will be in service.
These revisions are currently scheduled to be completed by June 30, 1989.
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.: Y ATTACHMENT 1 (Sheet 6 of 10)
Issue (3):
Short circuit protection on the DC-buses and motor thermal protection in general (Section 3.2.5).
Maine Yankee Note - The applicable report sections are 3.2.2 and 3.2.1.1.
Maine Yankee Resoonse:
Short Circuit Protection on DC Buses:
Maine Yankee has currently scheduled revision of the DC short circuit calculation E-1 and the battery sizing calculation MYC-104 by December 31, 1989. Based on these calculations, Maine Yankee will reduce the maximum DC fault current to match the ratings of the existing DC breakers by adjusting.the cable length (i.e. resistance) between the batteries and their respective buses. The cable length adjustment will be accomplished as soon as practical and is currently scheduled to be completed by the end of the 1990 refueling outage. Maine Yankee considers the breaker fault current ratings to be an equipment reliability concern and not a safety concern. Short circuit protection is not required for DC system normal operation but is necessary for the operation of the breakers during a worst case fault.
Motor Thermal Protection:
The Inspection Report indicates, in Section 3.2.1.1, that "Neither Maine Yankee, Yankee Atomic Electric Company.(YAEC), nor Stone ant Webster could locate'any motor thermal capability curves or pump n tor acceleration data...(and) without thermal damage information from the manufacturer, no conclusion can be drawn as to whether this setpoint is conservative."
The 4000 V motor protection philosophy utilized at Ma'ine Yankee is based on industry standards ano guidelines and the good engineering judgment of experienced engineers. Although we appreciate the NRC concern for specific motor thermal damage information, we would like to point out that temperature sensitivity is not the ultimate concern of relay engineers when establishing relay settings and protection capability. First, thermal damage curves from motor manufacturers are generalizations based on calculated and empirical data; and second, motor insulation systems can support temperature excursions beyond ratings without loss of equipment life.
Nonetheless, we believe Maine Yankee's ptotection chilosophy is extremely conservative in that we use two independent type relays for each motor: a Westinghouse BL-1 relay, and a General Electric IAC-66K relay. Outputs from these relays provide two separate pretrip alarms that warn of an impending overload condition. Trips are also provided for overload, locked rotor, and fault protection.
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ATTACHMENT 1 (Sheet 7 of 10). i l
1 The'BL-1 is a " replica relay" that has a time-current characteristic-that closely approximates the average heating curve of motors. The BL-1 is a sophisticated relay that has " thermal-memory" that permits utilization of the full inherent thermal capability of the motor, thus, it will trip faster if the motor were previously running or were exposed to a number of successive starts. The BL-1 is often recommended for.use when motor thermal damage data is not available or is questionable; however, our documentation and work files indicate that thermal damage time-current curves were available and were considered by the relay engineers who established the setpoints.
t Since the thermal damage curves appear to have been taken into account l when the setpoints were calculated, and since we have not had adverse experience in the seventeen years the plant has been operating (i.e.
no spurious motor trips or failu.e to. trip when required or motor ,
damage) we do not believe this item requires immediate action.
However, we do intend to recognize recovery of motor overload t
protection setpoint basis as an element in design basis recovery in the future. He intend to draft a motor overload protection setpoint manual,-which will provide the setpoints.and setpoint bases as a reference manual. He plan to establish a schedule for this activity by September 1, 1989. .
liina (4):
The inability to determine CCH system capability to perform its intended i safety function because of questions regarding: the effects of thermal l shrink and swell (Section 3.1.6); air accumulator capacity to isolate 4 non-essential loads-(Section 3.1.3); performance testing of the RHR heat ,
exchanger and new CCH heat exchangers; and, the lack of a complete CCH system heat balance (Section 3.1.2).
liaing Yankee Resoonse:
Shrink and_Swgil- ;
A preliminary review of the effects of thermal shrink and swell of the PCC/ SCC volume completed during the inspection indicated that system i operability will not be adversely affected. )
l Maine Yankee has currently scheduled completion of a formal calculation to document consideration of thermal shrink and swell of PCC/ SCC volume by Ortober 31, 1989. The effects of surge tank vent i valve closure will be included. The temperature range of PCC/ SCC will i be established by the PCC/ SCC heat load study currently in progress.
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I l l ATTACHMENT 1~(Sheet 8 of 10)
} 6 -.. l l .
Air Accumulator Caoacity:
The calculation for the trip valve accumulator design basis has been
-updated with revised input assumptions. The revised calculation shows j that the accumulator system was, in fact, capable of performing its '
intended function. The revised calculation incorporated more conservative assumptions in'some areas while taking credit for i previously uncredited performance. capability. In addition, Maine j l- Yankee identified the- following two operational changes to further l H assure that the SCC trip valves will remain closed in the event of an accident requiring closure, assuming total loss of the instrument air-- !
system some accumulator air leakage, and air pressure loss due to i turbine hall temperature changes: l
- Procedure A0P 2-36, RESPONSE TO SAFEGUARDS ANNUNCIATORS, has been revised to require manual closure of the SCC trip valves within-24 hours of a valid automatic closure.
- The accumulator low pressure alarm is currently scheduled to be reset to 92 psig, by June 30, 1989, to assure adequate air volume is available (during normal plant operation) to shut the trip valves and hold them shut for twenty-four hours.
Performance Testina of Heat Exchanaers:
Maine Yankee will investigate means of verifying the adequacy of the RHR and PCC/ SCC heat exchanger performance levels to meet design basis requirements. The investigation is currently scheouled to be completed by the 1990 refueling outage, lleat Balance:
Maine Yankee has provided information regarding this concern to the NRC with Reference (c). Maine Yankte has contracted Stone and Webster Engineering Corporation to perform a current PCC/ SCC system heat load study based on updated plant design. This study is currently scheduled for completicn by Octeber 31, 1989.
Issue (5):
The apparent use of ccmponent replacement (Section 7.2) when the rigor of the design process is more appropriate (Sections 3.2.4 and 5.1).
HAi ne Yankee Resoon a:
As explained in the cover letter, we agree that in both cases the design change process could have been used to advantage, and we are reviewing our decision process guidelines tc better address this in the future. He currently plan to revise appropriate procedures by October 31, 1989.
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AUACHMENT 1 (Sheet 9 of 10)
He think the results obtained using the component substitution process were satisfactory. The batteries were installed correctly, in.accordance with manufacturer's requirements; the-battery PM Program discrepancies,-
described in paragraph 5.1 of the Inspection Report, were actually in the process of being updated as a result of the component replacement process but were;not yet completed at the. time of the inspection. The battery installation was preceded by a previous battery installation conducted under the design change procedure, directed by the same engineer.
Similarly, no deficiencies were discovered due to the radiation monitors' replacements; in fact, a previons NRC Inspection Report No. 50-309/88-23 stated that the resulting calibrations are a "noted strength of the licensee's radioactive effluent control program".
Maine Yankee is, nonetheless, committed to improving the control of the component substitution process. A new technical evaluation procedure has been developed since the inspection. The draft EPRI guideline on technical evaluation of replacement items was used for guidance. This procedure provides assurance, as required by ANSI N18.7, that quality at least equivalent to that specified in the original design basis and requirements, material specifications, and inspection requirements are maintained. One of the authors of the EPRI technical evaluation guideline has reviewed our procedure, and his comments will be addressed.
Additional Issues Raised in Reoort Section 1 Issue: 1 Component labeling was identified as an issue warranting further manhgement attention, particularly for those design evolutions requiring manual operator action (9 ctions 3.1.7 hnd 4.1).
Maine YanM a lg.sp_qnig:
Maine Tankee will selectively relabel valvet that wot,ld require manual operator action, as directed by the Emergency Operating Procedures (EOPs). Specifically, the service water heat exchanger valves that are operated to effect realignment will be relabeled. and the E0Ps have been reviewed to determine what other valve relabeling is warranted. A total of 153 valves are directed to be operated by the E0Ps. Special labels, whicn have a fairly long lead time, have been ;
ordrred. He currently plan to complete the relabeling effort b.y '
September i, 1989.
151RE:
Inconsistencies were found in the preventive maintenance requirements l' for certain valves, in that similar valves were not being consistently maintained (Section 5.4.1).
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ATTACHMENT 1 (Sheet 10 of 10)
Maine Yankee Resoonse:
s Two check valves (PCC-72 and SCC-4) which perform the same function for two redundant systems were not subject to the same treatment by the PM program (PCC-72 was subject to periodic preventive maintenance while no PMs were required for SCC-4).
Investigation into the PM program and history file did not identify any recurring operational problem with PCC-72 nor any identified problems with SCC-4. The reason why PCC-72 was placed on a five-year PM could not be identified. Consistency was achieved with the two valves by removing PCC-72 from the PM program while the NRC team was on-site. These valves will be reviewed for incorporation in the In-Service Testing Program, as discussed under the next issue.
As a result of investigating this issue, Maine Yankee has revised Procedure 5-207-6, MAINTENANCE DEPARTMENT ADMINISTRATION OF THE PREVENTIVE MAINTENANCE PROGRAM, to require formally documenting, approving, and retaining PM program changes.
Issue:
In Section 6, the Team concluded that the surveillance testing program was generally adequate, but several check valves were found that should have been included in the In-Service Testing Prograat (Section 3.1.5). j Maine Yankee Resoonse:
The In-Service Testing (IST) Program is being reviewed and is currently scheduled to be revised by the 1990 refueling outage. The l valves in question (PCC-445, 446, 508 and 509) as well as the valves addressed in the foregoing issue (PCC-72 End SCC-4) will be included in this revision.
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js 1 ATTACHMENT 2 L .
l Priority and Schedule for Commitments Made During SSFI (As response to specific issues in the Inspection Report) l
, 1 1 J The matrix which follows documents Maine Yankee's response to the specific issues raised in the NRC SSFI Team Report. The' issues are listed (as Description) in roughly the order as presented in the report.
Item Numbers were assigned for ease of cross-reference and tracking purposes; these numbers should not be confused with Action Item Numbers assigned and tracked during the course of the actual inspection.
Description is a restatement of the issue documented in the report.
Reference to the report paragraph (s) which discuss (es) the issue is included.
The Plans column provides Maine Yankee's current plans for response to the issue.
The Status / Comments column includes indication of high priority items, some status information, and/or actions taken.
During the course of the inspection, Maine Yankee actively maintained an issues tracking' document, "SSFI Audit Action Item Status Summary." The document was used to assure that each issue perceived by Maine Yankee was documented and responded to. Where appropriate, Maine Yankee committed to appropriate follow-up items. Although the attached matrix differs in format, sequence, etc., from that developed during the inspection, we have attempted to reflect all of our prior commitments in the attached.
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