ML20198T348
| ML20198T348 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 06/24/1997 |
| From: | Garner L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Mallett B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20198T318 | List: |
| References | |
| NUDOCS 9711140262 | |
| Download: ML20198T348 (3) | |
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From:- Larry Garnerj RII . . .
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. 6/24/97 4:24pm
Subject:
DPV ; ,
Hi Bruce,
' Attached to the DPV response was a note asking whether or not I would object to the DPV being made public. ~ I have no '
- objections to the PPV and my identity being publicly disseminated. If you have other questions, please contact me. .;
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U(6 Items of Interest ~
Region II For Week Ending: August 1, 1997 -
Florida Power Corooration - Crystal River Representatives from Florida Power Corporation were in the Regional Office on July 30, 1997 to attend a closed management meeting. The purpose of the meeting was to discuss the Security Improvement Plan for Crystal River Unit 3.
Southern Nuclear Operatina Comoany. Inc, On July 31 the Regional Administrator and NRC managers from Region II and NRR attended an NRC Interface Meeting with the Southern Nuclear Operating Company.
(SONOPC0) Inc. , in Birmingham Alabama. SONOPC0 made presentations by each site Vice President and Plant Manager regarding plant status and long term site prcjects. The NRC discussed agency processes for several programs including allegations, senior management meetings, and complaints of improper staff conduct Severe Weather Workshoo Florida Power & Light Company and Carolina Power & Light Company co-hosted a Severe Weather Workshop in Fort Lauderdale. Florida for representatives from both Region II and non-Region II utilities whose operations may be affected by severe weather. Officials from the State of North Carolina, the Federal Emergency Management Agency (FEMA). Region IV, and Region 11. also participated in this workshap.
The principal items of discussion included: Plant Restart Discussions following Natural Disasters NRC Administrative Letter 97-03, dated March 28.
1997. and the role and responsibilities of FEMA. in the conduct of Disaster Initiated Reviews following natural disasters, and its associated impact on plant restart.
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Florida Power and Licht Comoany - Turkey Point Turkey Point Unit 3 tripped on July 30. 1997. when the B Main Steam Isolation Valve (MSIV) tripped and closed at 100 percent power. The cause of the trip was determined to be a failed relay in the MSIV control circuit. The relay is a Westinghouse BFD22S relay which is normally energized when the MSIV is open.
The relay has been replaced and further review of the relay failure is being performed. All similar relays on MSIV circuits have been replaced on Unit 3.
The licensee plans to review those in Unit 4 during the next refueling outage.
Shortly after the trip. the "A" Auxiliary Feedwater (AFW). turbine-driven pump tripped on overspeed. The cause of this overspeed trip is being investigcted by the licensee. The licensee has three AFW. turbine driven pumps (A. B. and C). The third pump (C) was aligned to function as the A pump. Under this condition. Unit 3 can operate at power for 30 days. On July 31. 1997. Unit 3 went critical and was at 100 percent power with a 30-day LCO for the inoperable A.AFW pump.
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The resident inspector responded to the control room and observed post trip
/ actions and has verified technical specification requirements: , , ,
Differino Professional View - Summer SALP Report Region II completed action on a differing professional view (DPV). The DPV concerned the written assessment in the plant support section of the Summer SALP report issued on December 6, 1996. In summary the DPV encompassed three issues as follows: (1) Some examples in the SALP report in the plant support section were misused and did not su decline or challenge occurred. (2) pport thethe assessment plant that a performance support section of the report was inconsistent with the previous SALP report and the last )lant performance review, and (3) the use of non-cited violations to support t1e plant support section of the report was inappropriate since the violations represented isolated cases.
Region 11 convened a DPV review panel in accordance with NRC Hanagement Directive 10.159. The panel completed review of the issues, accepted some of the DPV submitter's views and provided a recommended course of action to the Regional Administrator in June 1997. The Regional Administrator accepted the course of action on June 19. 1997, and conveyed this to the DPV submitter and SALP Board. As a result, the SALP report was rewritten to address the DPV issues. The SALP report was revised and reissued to the licensee on July 30, 1997.
E&W - Naval Fuel Division On July 28, the license reported a loss of a criticality control under NRC Bulletin 91-01. The licensee discovered a transport cast in the uranium recovery area with material containing uranium-235 stored in such a manner.
such that the mass of U-235 was in excess of the criticality limit.
The licensee approved unloaded safety limits.thaThe cart and stored the U-235 in accordance with material had originally been transferred to the uranium recovery areas from the metallurgical laboratory. Therefore..the licersee halted transfers for this type material from the metallurgical laboratory until an investigation team completes review of the root causes and corrective actions. Region II issued a letter confirming this action on August 1.
the licensee'sAn NRC team, consisting of NMSS and Region Il staff, is inspecting actions, pr%
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NUCLE AR REGULATORY COMMISSION
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,,,,. July 30, 1997 South Carolina Electric & Gas Company ATTN: Mr. Gary J. Taylor Vice President, Nuclear Operations Virgil C. Summer Nuclear Station P. D. Box 88 Jenkinsville. SC 29065
SUBJECT:
RESPONSE TO COMMENTS ON V. C. SUMMER SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE (SALP) REPORT IN5PECTICN REPORT NO. 50 395/96 99
Dear Mr. Taylor:
~
Thank you for your response dated February 12. 1997, and for your presentation in the NRC, Region II office on March 18, 1997, which provided your coments ano views on the V. C. Summer SALP Report which was issued on December 6 1996. Based on your input, the SALP Board reconvened on March 26,1997, and reviewed the information that you provided.
In addition, the NRC also conducted an independent review of the SALP Report.
After considerable deliberation. I have decided that, for the reasons presented in Enclosure 1 several changes to the SALP Peport were appropriate.
No change to the Plant Support Category Rating was required; however, the original report was modified after review by the independent panel. Tne associated revised SALP pages are included as Enclosure 2.
Should you have any questions concerning this matter, please contact Mr. A. Belisle at (404) 562 4550.
Sincerely.
J / -
, lLuisA.Re Regional istrator Docket No. 50-395 License No. NPF 12
Enclosures:
- 1. Evaluation and Conclusions
- 2. Revised SALP Pages cc w/encls: See page 2 h 0 1 },
SCE&G 2 cc w/encls:
R. J. White Nuclear Coordinator (Mail Code 802)
S.C. Public Service Authority -
c/o Virgil C -Summer Nuclear Station P. D. Box 88 Jenkinsville, SC 29065 J. B. Knotts. Jr.. Esq.
. Winston and Strewn 1400 L Street, NW Washington, D. C. 20005 3502 Chairman Fairfield County Council P.-0. Drawer-60 Winnsboro, SC 29180 Virgil R. Autry. Director Radioactive Waste Management Bureau of Solid and Hazardous Waste Management S. C. Department of Health and Environmental Control 2600 Buli-Street Columbia, SC 29201 R. M. Fowlkes. Manager Operations (Mail Code 303)
South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station P, D. Box 88 Jenkinsville, SC 29065 April Rice, Manager Nuclear Licensing & Operating Experience (Mail Code 830)
South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station P. O. Box 88 Jenkinsville, SC 29065 INPO
% 0 NRC'S EVALUATIONS AND CONCLUSIONS ON SOUTH CAROLINA ELECTRIC AND GAS COMPANY'S (SCE&G) RESPONSE TO THE V. C. SUMMER SALP REPORT By letter dated February 12.'1997.- SCE&G provided. comments on the V. C. Summer ;
SALP Resort which was issued on December 6. 1996. The comments involved five areas t1at collectively comprise the Plant St'pport SALP-functional: area. The-specific comments from SCE&G are in quotes.
- 1. NRC Evaluation of Comments on Radiolooical Control Imorovements
- "In the area of Radiological Controls. V. C. Summer has realized significant reductions in dose, plant effluents, and radweste generation since the last SALP period. Redioactive meterial control performance and the number of NRC violations has remained constant when compared to the last assessment period. Improvements in the area have been made while at-the same time drastically lowering our threshold for problem reporting. Radiological Controls improvements far outweigh any issues identified during this SALP period as supported by the following
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SCE&G NRC
" Annual exposure has been reduced The lower radiation exposure was from the previous assessment period. considered and recognized by the SALP even if the dose from the 1994 steam Board.
generator replacement is excluded,"
" Outage dose in Refuel 9 was our lowest-in history and 9th lowest refueling dose ever for PWRs."
" Effectively reduced plant effluents. The doses from effluents were when compared to last SALP period." recognized by the NRC as being significantly below regulatory limits.
" Greatly reduced the amount of Reduc' t ion of radiological radweste contaminated trash generated and the amount of contaminated area annually." were toi.sidered by the SALP Board
" Contaminated surface area within the radiation control area (RCA)'is maintained less than 2%."
"During refueling outages, the This information was discussed at the containment building is maintained SALP Board.
accessible in street clothes."
"V. C. Summer Nuclear Station [VCSNS] No information was available to is recognized within the industry by confirm or deny this statement.
INP0 and our peers for our contamination control."
3 ENCLOSURE 1
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"NRC Inspection Reports have also The inspection history was considered included remarks complimentary of by the SALP Board, contamination control . (9415, 95 03.
& 95.19)"
"The number of NRC violations in SALP assessments are not a direct Radiological Controls is consistent function of the number of violations.
with the previous SALP period." Enforcement history wes considered by the SALP Board.
" Incidents of radioactive material The information regarding discovered outside of the RCA has contamination events during this remained constant when compared to assessment period was considered by the last SALP period. There has been the SALP Board: the write up was no instance of loss of contamination changed to reflect the results of the control from the protected area." independent review.
"A review of Region II SALP history The SALP Board reviewed V. C.
indicates other plants with recent Summer's performance in accordance incidents of contamination control with NRC's criteria and not in issues who subsequently received a comoarison with other sites.
superior rating in Plant Support."
Changes were made to the SALP Report in the Radiologi :' Control area. The statement involving the site ALARA program was modified to read:
The site ALARA program was effective in maintaining low site collective dose.
The statements involving contamination control were modified to read:
Personnel contamination control measures were generally successful throughout the period. There were some examples where control of contamination was lost, in that, contamination and contaminated material were found outside control boundaries.
- 2. NRC Evaluation of Comments on Emeraency Preoaredness
" Emergency Prepcredness at V. C. Summer has made improvements in the areas of Emergency Response Organization (ERO) staffing. computerized information exchange & status, accountability of non-essential personnel, and siren-availability. We have continued to receive positive feedback due to our close working relationship with state end local governments within our EPZ, and our annual evaluated exercise results showed improvements. Our continuous improvements in light of the lowered threshold for problem reporting, discussed earlier, far l outweigh arjy issues raised during the SALP period as supported by the following:
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SCE&G SRI "The ERG was placed in a four team This is new information. It was not *
. rntation.- this has. allowed for more independently verified during the effective table top' drills, improved SALP period, accountability and improved teamwork."
" Developed a computerized Emergency Information System (EIS) to enhance information exchange between the facilities . " '
' Installation of the biometrics ham This is new information. It was not geometry system has decreased the ir. dependently verified in Emergency time required to conduct Preparedness during the SALP period.
accountability. " Credit was noted for the biometric hand geometry system in the security area.
- VCSNS has been recogaized by the This was not inspected during the state for taking the lead role with SALP period.
South Carolina utilities in the effort Pc lace the State's eme g. ,, ; Wiac and dosimetry inventory. This action was in response to notification that FEMA would no longer fund the Radiological Defense Program."
" Siren performance has made steady Management support for the Early improvement compared to the last SALP Warning System (EWS) and telephone period. In 1996 VCSNS achieved an system was considered by the SALP unprecedented average operability of Board.
98.10% with a complete cycle test with 99.06% of sirens sounding. "
" Training drills are conducted with The fundamental initiator for each of interim Emergency Directors and the training drills fnr the four licensed operators during each months preceding the exercise, which licensed operator training cycle. is the evaluated event, appeared to These drills have been diverse and be the same as for each exercise. A challenging to ensure each shift's drill history with a spectrum of emergency classification ability." initiators, coupled with an exercise with a unique initiator, would have demonstrated a challenge to the integrated emergency response organization.
Changes were made to the SALP Report in the Emergency Preparedness area. The following statements were deleted:
4 However, actual response indicated some decline in performance.
.. and in maintaining awareness of siren system status in order to make timely reports.
Several improvements were made to . . . . to make them more reliable.
The statement involving the Alert and Notification System was modified to read:
The Alert and Notification System sirens had been effectively maintained.
No changes were appropriate for issues involving the four team notation the computerized information system. and taking the lead note with South Carolina.
- 3. NRC Evaluation of Comments on Fire Protection "The number of violations and negative comments contained in inspection reports has significantly decreased this SALP period despite the fact that we have replaced the fire detection system. rerouted sprinkler systems and rewritten our fire implementation procedures. An NRC inspection. conducted in October to assess performance for the entire SALP assessment period, was overall complimentary with only minor discrepancies noted. Our new fire protection team approach is committed to continuous improvement and problem solving to meet rising expectations and maintain a superior level of performance as evidenced by:"
SCE&G NRC "The number of violations and The inspection and enforcement negative comments contained in performance was considered by the inspection reports has significantly SALP Board.
decreased this SALP period."
" Replaced the fire detection computer The installation of this system was system with a new enhanced state of- in process at the time of the fire the art Simplex fire detection protection inspection in October system." 1996. The estimated installation completion was scheduled for late 1996. This new system was considered i
by the SALP Board.
" Performed a job task analysis for This item was not inspected.
personnel performing fire protection duties."
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" Formed a fire protection team This item was considered by the ;
(consisting of a Systen Engineer. Special Inspection Branch and SALP '
Design Engineer, Test Specialist I&C Board.
-Technician, Fire Protection Supervisor, a Licensing Representative and other plant .
I representatives as deemed necessary) which meets monthly to discuss fire protection issues."
' Changed personnel responsible for This item was considered by the oversight of the Fire Protection Special Inspection Branch and SALP program." Board.
' Revised the Fire Protection This item was considered by the Procedures to improve quality and Special Inspection Branch and SALP efficiency." Board.
" Conducted a performance based This item was not inspected.
engineering evaluation of the fire protection program and revised the testing program to incorporate the evaluation findings. This evaluation allowed the extensica of some testing frequencies based on historical equipment performance and system reliability."
Changes were made to the SALP Report in the fire protection area to reflect noted improvement in performance during the last six months of the assessment period. The statement involving Fire Protection program implementation was modified to read:
The Fire Protection program implementation was satisfactory early in the assessment period and improved to good by the end of this period.
This statement addresses the new fire detection system.
The statement invo'ving organization and staffing changes was modified to read:
Organization and staffing changes were made late in the period in an effort to improve performance and some improvement was evident.
This statement eddresses the fire protection team and changes in personnel oversight.
The statement involving housekeeping was modified to read:
Housekeeping, in general. was very good.
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~A review of fire protection procedures identified that the procedures were-adequate. No change was appropriate to the SALP Report fe procedure issues related to the joD task analysis and performance based engineering evaluation.
- 4. NRC Evaluation of Comments on Chemistry
" Performance within tSe chemistry area continues to be maintained at a superior level and SCE&G continues to make program enhancements as illustrated by the following:"
SCE&G Njlq
" Developed a program to incorporate a No independent NRC verification was secondary plant auxiliary system conducted on the program to corrosion monitorir.g system." incorporate e secondary plant auxiliary system corrosion monitoring
" Achieved the INP0 Chemistry Index system.
Performance Goal of <1.20 for the year."
"Het a challenging goal to maintain Lithium and Boron concentrations to help ensure low exposure rates during the refueling outage and during the
-operating cycle."
" Developed a program to convert to 3-methhoxpropylamine (HPA) secondary piant chemistry control.*
No changes were made to the SALP report in the chemistry area.
S. NRC Evaluation of Comments on Security
" Superior performance has been maintained within the area of Security, and SCEoG continues to make program e,hancements as evidenced by the following:"
SCE&G NRC
" Installed the biometrics hand This was recognized by the SALP geometry system.* Board.
" Installed the vehicle barrier This was not inspected during the system." SALP period.
"Upg"aded Perimeter Intrusion This was recognized by the SALP Detection System." Board.
" Converted to the I Star badging This was recognized by the SALP system." Board.
" Developed program to incorporate This was not inspected during the NEI's Personnel Access Date System." SALP period.
7 No changes were made to the SALP report in the security area. The statement, "the protected area access control equipment was reliable and effective."
includes inspection of biometrics, perimeter intrusion and badging.
Conclusion:
Based on our review of your response and the information provided by you during the March 18. 1997 meeting, we have concluded that, based on the inspections that were performed during the SALP period, your attention and involvement were normally well focused and resulted in a good level of safety performance. In addition, your programs and procedures normally provided the '
necessary control of activities but some deficiencies existed.
The SALP Board recommended no changes to the Category reting.
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.....j [' ATLANTA, G8EoRGIA 30303_- '4 i South Carolina Electric & Gas Company ATTN: Mr. Gary J..Yaylor1 _
Vice President, Nuclear Operations Virgil C, Summer Nuclear Station P. 0. Box 88=.
Jenkinsville, SC 29065-_ R L
SUBJECT:
SYSTEMATIC-ASSESSMENT OF L-ICENSEE PERFORMANCE-(SALP)
(INSPECTION REPORT NO. 50 395/96 99)'
Dear Mr. Taylor:
The U.S. Nuclear Regulatory Comicission (NRC) has completed the Systematic '
- Assessment of Licensee Performance (SALP):for the Summer Nuclear Plant.
The facility was assessed in four functional areas:for the period of January 29.-1995, _ through October 26, 1996. The results of the assessment-are documented in the enclosed SALP report whith will.be discussed with you -
at a public meeting at the Summer site on December 16, 1995, at 1:00 p.m.
Summer Nuclear Plant performance was assessed in four functional areas: Plant ~ -
Operations. Maintenance, Engineering.--and Plant Support. Performance in Operations and Haintenance remcined superior. Performance in Engineering- .
improved and .is now considered superior. Performance in Plant Support was good.
Plant Operations superior performance was characterized by stable power operations, strong operator knowledge and ability, and effecthe management self assessment activities. Superior performance in Haintenance was sustained by strong management support, a firm commitment to inspection and testing programs- and well +. rained and knowledgeable personnel . Engineering achieved superior performance due to an improved design control process. strong naintenance of the licensing basis, and effective support to other
-organizations. -Plant-Support performance was generally good with some examples where deficiencies existed.
Initiatives that contributed to superior performance in the majority _ of functional areas were strong management. support for benchmerking and-self-assessment activities including auditing and rotations of personnel. This included both staff a'd management in order to improve station self assessment and quality _ verification activities.
In'accordance with Section 2.790 of the NRC's " Rules of Practice," a copy of thi_s letter and its enclosure will be 'placed in the NRC Public' Document Room.
Enclosure 2 2
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V. PLANT SUPPORT This functional area addresses all activities related to the plant support function, including radiological _ controls, radioactive effluents, chemistry, emergency preparedness, security, fire protection, and housekeeping, The radiological control program was effective in protecting the health and safety of plant workers and members of the public. The onsite i radiation arotection program controlled inte nal and external radiation exposures aelow reguhtory limits. The site ALARA program was effective in maintaining low s te collective dose. Personnel contamination control measures were generally successful throughout the period. There were some examples uhere control of contamination was lost, in that, contemination and centaminated material were found outside control boundaries.
Offsite radiation exposure to members of the public was substantially below regulatory limits. The environmental monitoring program confirmed effective effluent controls in that only trace amounts of radioactivity were detected in the environs of the plant.
Effective chemistry programs were implemented to inhibit degradation due to corrosion of components in both primary and secondary systems. The program for handling, packaging and transport of radioactive materials functioned very well, The emergency preparedness program was generally effective in maintaining site readiness to respond to emergencies. A challenge was noted in developing challenging emergency exercise scenarios. The Alert and Notification System sirens had been effectively maintained.
Preparations for a hurricane minimized the risks and potential damage to plant facilities from rain and high winds.
The licensee continued to implement and support the Physical Security Plan, procedures and associated programs in an outstanding manner. The security program was strong and well managed. The protected area access control equipment was reliable and effective. Station management was active in identifying and correcting potential problems.
The Fire Prutection program implementation was satisfactory early in the assessment period and improved to good by the end of this period. Early in the period, a number of human performance errors existed, but a marked improvement was noted in the implementation of the program at the end of the period. Maintenance and testing of fire protection systems were good with a significant reduction in the backlog of fire protection related maintenance items. Organization and staffing changes were made late in the assessment and improved performance was evident. Quality assurance audits were thorough and corrective actions were timely.
Housekeeping, in general, was very good.
The Plant Support area is rated Category 2.
Enclosure 2 i