ML18153A259
| ML18153A259 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/05/1998 |
| From: | Haag R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 9806170012 | |
| Download: ML18153A259 (19) | |
Text
June 5, 1998 Virginia Electric and Power Company ATTN:
Mr. J. P. O'Hanlon Senior Vice President - Nuclear Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen. VA 23060
SUBJECT:
PLANT PERFORMANCE REVIEW (PPR) - SURRY NUCLEAR STATION
Dear Mr. O'Hanlon:
On May 7. 1998. the NRC staff completed the semiannual Plant Performance Review (PPR) of Surry Nuclear Plant.
The staff conducts these reviews for all operating nuclear power plants to develop an integrated understanding of safety performance.
The results are used by NRC management to facilitate planning and allocation of inspection resources.
The PPR for Surry involved the participation of all technical divisions in evaluating inspection results and safety performance information for the period October 1997 through April 1998.
PPRs provide NRC management with a.current summary of licensee performance and serve as inputs to the NRC Systematic Assessment of Licensee Performance (SALP) and Senior Management Meeting (SMM) reviews. contains a historical listing of plant issues. referred to as the Plant Issues Matrix (PIM). that were considered during this PPR process to arrive at an integrated view of licensee performance trends.
The PIM includes only items from inspection reports or other docketed correspondence between the NRC and Virginia Electric and Power Company.
The PPR may also have considered some predecisional and draft material that does not appear in the attached PIM. including observations from events anq inspections that had occurred since the last NRC inspection report was issued. but had not yet received full review and consideration. This material will be placed in the Public Document Room as part of the normal issuance of NRC inspection reports and other correspondence.
This letter advises you of our planned inspection effort resulting from the Surry PPR review.
It is provided to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be
\\ /;
resolved in advance of inspector arrival onsite. Enclosure 2 details our inspection plan for the remainder of 1998.
The rationale or basis for each inspection outside the core inspection program is provided so that you are aware of the reason for emphasis in these program areas. Resident inspections are not listed due to their ongoing and continuous nature.
During this scheduling cycle. we will be focusing some of our discretionary inspection effort on the resolution of open inspection items. Therefore.
additional inspections may be conducted. which are not listed on Enclosure 2.
...-.(\\"'/:1
- ., I I.1. ":l 9806170012 980605 PDR ADOCK 05000280 G
PDR OFFICIAL COPY
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e e:
VEPCO 2
to close open inspection items that are ready to be resolved.
You will be notified at least 3 weeks prior to the start of these inspections.
The NRC' s general policy for reactor inspections is that each inspection sha 11 be announced. except when announcing the inspection could reasonably compromise the objectives of the inspectors. Therefore. some specific inspections. such as in the security and radiological protection areas. are not included on Enclosure 2 and may not be announced.
We will inform you of any changes to the enclosed inspection plan. If you have any questions. please contact me at 404-562-4500.
Docket Nos. 50-280. 50-281 License Nos. DPR-32. DPR-37
Enclosures:
- 1. Plant Issues Matrix
- 2.
Inspection Plan cc w/encls:
J. H. McCarthy, Manager Nuclear Licensing and Operations Support Virginia Electric & Power Company 5000 Dominion Boulevard Glen Allen. VA 23060 David A. Christian. Manager Surry Power Station Virginia Electric & Power Company 5570 Hog Island Road Surry. VA 23883 W. R. Matthews. Manager North Anna Power Station P. 0. Box 402 Mineral. VA 23117 Chairman Surry County Board of Supervisors P. 0. Box 130 Dendron. VA 23839 Sincerely, Orig signed.*oy Robert C. Haag Robert C.
Haag, Chief Reactor Projects Branch 5 Division of Reactor Projects
OFFICE SIGNATURE NAME DATE COPY?
e VEPCO Virginia State Corporation Commission Division of Energy Regulation P. 0. Box 1197 Richmond. VA 23209 Michael W. Maupin Hunton and Williams Riverfront Plaza. East Tower 951 E. Byrd Street Richmond. VA 23219 State Health Commissioner Office of the Commissioner Virginia Department of Health P. 0. Box 2448 Richmond. VA 23218 Attorney General Supreme Court Building 900 East Main Street Richmond. VA 23219 Distribution w/encls:
L. Pl i sea. RII L. Garner. RII D. Jones. RII R. Aiello. RII G.. Edi son. NRR PUBLIC NRC Resident Inspector U.S. Nuclear Regulatory Commission Surry Nuclear Power Station 5850 Hog Island Road Surry. VA 23883 NRC Resident Inspector U.S. Nuclear Regulatory Commission 1024 Haley Drive Mineral. VA 23117 3
5/
/98 YES NO
DATE TYPE(s)
SEC.SFA
- rtC>R~~t,~t~J~j~1i]it1tiii~tifi 3/21/98 Positive SAQV 3/21/98 Positive SAQV 3/20/98 Positive 2n/98 Negative 217/98 Positive MAINT 2/4/98 Negative FROM: 10/1/97 TO: 4/30/98 United States Nuclear Regulatory Commission PLANT ISSUES MATRIX by SALP Functional Area SURRY SOURCE(s)
ID'd ISSUE(s)
IR-98-03 NRC IR.98-03 NRC IR-98-03
. NRC The licensee's deficiency identification and reporting and corrective action programs were effectively identifying issues, and recommending and implementing appropriate corrective action. There were approximately 45 overdue responses to deviation reports with the majority being assigned to engineering. The licensee has initiated action _to resolve this backlog. Licensee self-assessment effectively evaluated the corrective action program.
The licensee's oversight process was effective in identifying programmatic problems. With the exception of an audit finding that was not clearly characterized, the reviewed audits exhibited good self assessment techniques and met program requirements.
Observed Unit 1 shutdown activities were conducted in accordance with approved procedures. Command and control during unit stabilization at four percent power was good and operators controlled plant parameters well during generator voltage regulator testing.
IR-98-01, LER 280/98-03 LICENSEE The licensee identified that under certain conditions the seven day fuel oil design basis requirement for the No 3 emerg_ency diesel generator could not be met.
Procedural controls were implemented to ensure the fuel oil supply was adequate to meet design basis requirements.
IR-98-01 NRC Cold weather preparations were adequately'implemented and were in accordance with approved procedures. Licensee identified discrepancies were corrected prior to the onset of cold weather.
IR-98-01, LER 280/98-02 LICENSEE The licensee was unable to identify the cause of the Unit 1 voltage regulator failure that resulted in a reactor trip. Unit 1 plant response following an automatic reactor trip was normal and plant systems operated as designed. The voltage regulator was in manual at the time of the trip. The voltage regulator was repaired for automatic operation.
Page 1 of 14 FOR PUBLIC RELEASE Enc;losur~ 1 05-Jun-98 SMM CODES.
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SURRY 05-Jun-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMMCODES 2/2/98 LER LER 50-280/98004 LICENSEE Fire Watch Released Prematurely Resulting in Violation of TS 3.21.B. 7 1 2 3 4 5 A DODOO e DODOO C (21 DOD 2/2/98 Positive IR-98-01, LER 280/98-02 SELF Unit 1 plant response following an automatic reactor trip was normal and plant 1 2 3 4 5 systems operated as designed. Subsequent startup activities were conducted in accordance with approved procedures and in a controlled manner.
A f21DDD D e DODOO C D DD.
12/4/97 Positive IR-97-12 NRC Management's decision to hold Unit 2 power at approximately 35% while resolving 1 2 3 4 5 issues with an Anticipated Transients Without Scram Mitigating System Actuation Circuitry setpoint and with TDAFWP was conservative and demonstrated a good A [2]0DDD safety perspective.
e DODOO C D ODD 12/2/97 Negative IR-97-12, LER 281/97004 NRC The plant response to a Unit 2 manual reactor trip was normal except for a problem 1 2 3 4 5 with control rod indications. With the unit stabilized at hot shutdown, inattention of the operating crew to plant conditions resulted in SG PORV actuations.
A (21 (21 (21 D D e DODOO C D DOD 11/27/97 VIO IR-97-12 NRC A violation was identified involving the failure to prope°rly perform the verification that 1 2 3 4 5 the AAC Diesel Generator breaker control switches were in the Auto-after-Trip position as required by operator logs.
A t8lDt8lD D B DODOO C D oore 11/26/97 Weakness IR-97-12 NRC While returning the AAC DG to service, the operating crews demonstrated a 1 2 3 4 5 willingness to accept inadequate instructions and exhibited a lack of attention to detail and questioning attitude. This evolution also revealed a weakness in control A DDt8lD D of trainees.
B DDf21D D C D DOD 11/26/97 VIO IR-97-12 SELF A violation was identified for the failure to have appropriate instructions available to 1 2 3 4 5 the return the AAC Diesel Generator to service following maintenance activities.
Resulted in generator being unavailable for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
A t8lDDD D B Dt8lDD D C D ODD FROM: 10/1/97 TO: 4/30/98 Page 2 of 14 FOR PUBLIC RELEASE Last Updated: 5/30/98
SURRY 05-Jun-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMMCODES 11/12/97 Positive IR-97-10 NRC Licensee actions to identify and report the Anticipated Transient Without A Scram 1 2 3 4 5 Mitigation System Actuation Circuitry enable setpoint problem exhibited a good questioning attitude and conservative approach to operations.
A ODD~~.
B DODOO C D DOD 10/31/97 Positive IR-97-10 NRC Control room charts were observed to be operating correctly and control room logs 1 2 3 4 5 were routinely reviewed by operations personnel. Plant startup evolutions were conducted in accordance with approved procedures.
A ~D~DD B DODOO C D ooce 10/28/97 LER LER 280, 281/97012 & 01 LICENSEE EQ Unanalyzed Condition/Outside App. R Design Basis Due to Unlatched Doors.
1 2 3 4 5 A DDD~D B DODOO C D DOD 10/28/97 NCV IR-97-10, NCV 50-280, LICENSEE A Non:cited Violation was identified concerning the failure to perform a TS required 1 2 3 4 5 281/97010-03, LER 97010 surveillance on the diesel driven fire pump within the required frequency due to personnel error.
A DD~DD B DODOO C D DOD 10/27/97 Negative IR-97-10 NRC In general the licensee's preparation of the U2 containment prior to restart from the 1 2 3 4 5 refueling outage was adequate. Minor deficiencies were identified that indicated a more thorough licensee walkdown should have been performed. These items were A D~DD~
corrected prior to containment closeout.
B DODOO C D ooe 10/14/97 Positive IR-97-10, LER NRC The licensee's actions to identify an intake canal level probe common mode failure 1 2 3 4 5 280,281/97009-00, 01 scenario demonstrated a good safety perspective and were conducted in a conservative and professional manner. The licensee initiated a root cause A Dl2JDD l2l evaluation to determine the cause of the failures.
0000[2]
B C D DOD 10/12/97 Positive IR-97-10 NRC Observations by the inspectors during the defueling of the U2 reactor indicated a 1 2 3 4 5 well controlled process being carried out in accordance with TS. Effective foreign material exclusion practices were in place.
A l2JDl2JD D B Dl2JDDD C D DOD FROM: 10/1/97 TO: 4/30/98 Page 3 of 14 FOR PUBLIC RELEASE LastUpdated: 5/30/98
DATE TYPE(s)
SEC.SFA 1017/97 Positive 10/5/97 Positive 10/4/97 Positive 10/4/97 NCV lf41HliNJD~~l\\\\tl~~st*t 4/28/98 NCV 4/24/98 Positive 3/21/98 NCV FROM: 10/1/97 TO: 4/30/98 SOURCE(s)*
IR-97-10 IR-97-10 IR-97-09 IR-97-09, NCV 280,281/97009-01 ID'd NRC NRC NRC NRC
$URRY ISSUE(s)
Increased U1 reactor coolant activity indicated that a fuel cladding defect had occurred. The licensee was monitoring and trending coolant activity on a routine basis. The inspector periodically reviewed reactor coolant sampling results and verified that activity was well below Technical Specification allowable values.
The operators performed their assigned duties in an excellent manner during the U2 shutdown for a scheduled refueling outage. The SRO maintained excellent command and control during the evolution. Briefing that were thorough and detailed were made prior to each significant evolution.
Hydrogen concentration has continued to decrease within the Unit 1 containment following installation of a portable autocatalytic recombiner. The portable recombiner appears to be functioning appropriately to reduce hydrogen concentration.
A Non-Cited Violation was identified for an inadequate procedure that failed to verify proper system alignment and resulted in an inadvertent makeup to the SFP from the Unit 2 refueling water storage tank. The corrective actions implemented should prevent recurrence.
IR-98-04, NCV 9~004-03 LICENSEE A non-cited violation was identified concerning maintenance personnel failing to IR-98-04 IR-98-03, NCV 98-003-01, LER 98-001 NRC verify that they were working on the proper component before starting preventive maintenance activities. As a result, work to be performed on the B charging pump normal suction valve was performed on the pump's normal discharge valve.
Identification and corrective actions for this matter were prompt and thorough.
Emergency Diesel Generator Number 3 alarm relay replacement activities were accomplished in accordance with the work package instructions. The electricians performing the work were knowledgeable of how to perform the activities. The
. tagout for the work was acceptable.
LICENSEE A Non-Cited Violation was identified for failure to obtain valid vibration data during an auxiliary feedwater pump surveillance test. Faulty test equipment resulted in the Technical Specification Violation.
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C A
B C
A B
C A
B C
A B
C A
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A B
C 05-Jun-98 SMMCODES 1 2 3 4 5 IZJDDDD DODOO IZl DD D 1 2 3 4 5 IZJODDD DODOO D DD.
1 2 3 4 5 0~000 o~ooo D 0012]
1 2 3 4 5 IZJDDDD DODOO D DD!Zl 1 2 3 4 5 DDIZJD~
DODD D ODD.
1 2 3 4 5 DIZJIZJDD D00DD D DOD 1 2 3 4 5 00000 012Jl2lD D D ODD Page 4 of 14 FOR PUBLIC RELEASE Last Updated: 5/30/98
SURRY 05-Jun-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMMCODES 3/21/98 Positive IR-98-03 NRC Turbine driven auxiliary feedwater pump testing was performed in accordance with 1 2 3 4 5 approved procedures,. and the pump met all acceptance criteria prior to return to service. The pre-job briefing was thorough.
A DD0DD B DODOO C D DOD 3/21/98 Positive IR-98-03 NRC Un interruptible power supply 18-2 maintenance activities were performed in 1 2 3 4 5 accordance with approved procedures, and the technicians performing the work activities were knowledgeable and used good electrical work practices.
A DD0DD B DD121DD C D DD.
2/8/98 Positive IR-98-01 NRC Replacement of a gamma-metrics excore power supply was performed 1 2 3 4 5 successfully. The technicians demonstrated attention to detail and a questioning attitude while following up on the cause of the power supply failure.
A DD0DD B 0000121 C D ODD 2/7/98 Positive IR-98-01 NRC The licensee has made significant improvements since the original Maintenance 1 2 3 4 5 Rule baseline inspection and now has a very comprehensive Maintenance Rule Program.
A DDDDD B Dl2IDl2I D C D D121D 2/7/98 Positive IR-98-01 NRC Surveillance activities involving the analog rod position system charging pump 1 2 3 4 5 operability and the reactor trip portion of the reactor protection system were completed in a thorough and professional manner. Personnel were knowledgeable A DD121DD of the tasks. The involved plant groups coordinated their activities well.
B DD121DD C D DD~
1/29/98 VIC IR-98-01, VIC 280,281/98-NRC A violation of 10 CFR 50, Appendix 8, Criterion XVI was identified for failure to 1 2 3 4 5 01-02 promptly correct a degraded (high vibrations) Number 3 Emergency Diesel Generator auxiliary oil pump motor. The motor failed and resulted in the diesel A D121DDD generator being inoperable.
B 0121000 C D DD121 12/27/97 Negative IR-97-12 NRC Surveillance activities involving the control room chillers, an emergency service 1 2 3 4 5 water pump, and the TDAFW pump were completed in a thorough and professional manner. Procedures were detailed. Coordination between various plant groups was A DD121DD good.
B 0121000 C D ODD FROM: 10/1/97 TO: 4/30/98 Page 5 of 14 FOR PUBLIC RELEASE Last Updated: 5/30/98
SURRY 05-Jun-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMMCODES 12/27/97 Negative IR-97-12 NRC The operating experience review staff failed to recognize the applicability of improper 1 2 3 4 5 reactor trip bypass breaker testing to Surry after this issue was identified in October, 1996, at the licensee's North Anna Station.
A DODD~
B D~DDD C D ODD 12/27/97 NCV IR-97-12, LER 280,281 LICENSEE A noncited violation was identified for failing to test the remote manual undervoltage 1 2 3 4 5 97011 trip prior to placing the reactor trip bypass breakers inservice as required by Technical Specifications.
A DODD~
B 0121000 C D DD.
12/27/97 Positive IR-97-12 NRC Maintenance activities involving EDG radiator louvers, control room chiller, and the 1 2 3 4 5 screen wash system were completed in a thorough and professional manner.
Maintenance personnel were knowledgeable of the assigned tasks. Procedures
.A DD121DD were detailed and used on the job.
B 0121000 C D DOD 11/15/97 URI IR-97-10, URI 50-NRC The inspector questioned the basis of a licensee's interpretation of TS surveillance 1 2 3 4 5 280,281/97010-04 frequency requirements. For several tests, TS specified the frequency as "Each Refueling Shutdown" or "Refueling", however, the tests were being performed during A DDDDD plant power operations. Additional 1eview is being performed on this issue.
B 0121000 C D ODD 11/15/97 Positive IR-97-10 NRC Thirteen observed surveillance tests were performed satisfactorily. Procedures were 1 2 3 4 5 present and in use. Effective crew briefing were accomplished prior to performing the tests.
A DD121DD B 0121000 C D oore 11/15/97 Positive IR-97-10 NRC Maintenance activities on protective relays and the condenser water box were 1 2 3 4 5 performed satisfactorily. Supervisory oversight ensured that the work procedures were adequate and being followed.
A DD~DD B DODOO C D 121DD 11/15/97 Positive IR-97-10 NRC The licensee's flow accelerated corrosion monitoring program continued to be a well-1 2 3 4 5 engineered and conservative program.
A DDDDD B 0121000 C D D121D FROM: 10/1/97 TO: 4/30/98 Page 6 of 14 FOR PUBLIC RELEASE Last Updated: 5/30/98
SURRY 05-Jun-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMMCODES 11/15/97 Positive IR-97-10 NRC The licensee's inservice inspection results were well documented, and the bases for 1 2 3 4 5 conclusions were conservative.
A DODOO-B 00000 C D ODD 10/24/97 Positive IR-97-10 NRC Testing of the U2 pressurizer power operated relief valves was conducted in a 1 2 3 4 s cautious and controlled manner and as specified by the procedure. The Senior Reactor Operator supervising the test demonstrated superior command and control A 0000 D over the evolution.
00000 B
C D oore 10/22/97 Strength IR-97-10 NRC Consistent evaluations of eddy current inspection results and *conservative tube 1 2 3 4 5 plugging decisions were strengths in the licensee's steam generator inspection program.
A DODOO B 00000 C D DOD 10/20/97 VIO IR-97-12, VIOL 281/97-NRC A violation was identified for failµre to perform post maintenance testing which was 1 2 3 4 5 12-03 specified in work instructions for the Unit 2 TDAFWP governor replacement.
A 00000 B 0000 D C D ODD 10/15/97 Positive IR-97-10 NRC Surveillance activities associated with safety injection accumulator check valve 1 2 3 4 5 testing and Number 3 EDG testing were conducted in accordance with approved procedures and met acceptance criteria.
A 00000 B 00000 C D ooe 10/11/97 VIO IR-97-10, VIO 50-SELF A violation was identified for inadequate work instructions resulting in the failure to 1 2 3 4 5 281/97010-05, LER implement the prerequisite requirements of a safety evaluation during th!!
280,281/97008 replacement of a Consequence Limiting Safeguards relay.
A DODOO B 00000 C D 000 10/5/97 Positive IR-97-10 NRC The licensee rebuilt the pressurizer Power Operated Relief Valves during the U2 1 2 3 4 5 Refueling Outage. Following return of the unit to service, no indication of seat leakage was observed. Previously, the Unit 1 PORVs _repair efforts were not A 00000 successful in correcting seat leakage.
B 00000 C D ODD FROM: 10/1/97 TO: 4/30/98 Page 7 of 14 FOR PUBLIC RELEASE Last Updated: 5/30/98
SURRY 05-Jun-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMMCODES 10/4/97 Positive IR-97-09 NRC The licensee's actions with regard to surveillance, testing and maintenance of the 1 2 3 4 5 auxiliary shutdown panels and the remote monitoring panels were excellent.
Switches and meters had appropriate operability checks. The UFSAR accurately A DDDDD reflected plant conditions for the panels and corresponding procedures.
B 0121000 C D ODD 10/4/97 Positive IR-97-09 NRC Reactor Protection System Logic Testing was performed in an excellent manner.
1 2 3 4 5 The l&C technicians were methodical and cautious. Repeat backs and verifications were consistently performed.
A DD121DD B 0121000 C D DD.
3/20/98 Positive SAQV IR-98-03 NRC The engineering self-assessment program was comprehensive with good procedural 1 2 3 4 5 controls. Audit reviews revealed a good ability to perform audits, be self-critical and address concerns with timely corrective actions. The environmental qualification A DDD*D 121 area seal-assessment was well performed.
B DODOO C D 01210 3/20/98 Positive IR-98-03 NRC The licensee's plans and procedures for the installation of a freeze seal on a 12-inch 1 2 3 4 5 safety injection accumulator discharge line were thorough. Adequate contingencies were implemented prior.to the placement of the freeze seal.
A DODOO B Dl2IDl2I D C D D121D 2/7/98 Positive IR-98-01 NRC Temporary Modification S1-98-02 to install a temporary resistance temperature 1 2. 3 4 5 detector int he C main feedwater line was adequately implemented and the associated safety evaluation justified implementation of the temporary modification.
A DODD.
B 01210121 C D D121 D.
11/19/97 Positive IR-97-10 NRC Letdown line modifications were completed during the U2 refueling outage to correct 1 2 3 4 5 previous problems in which several socket weld failures occurred in the letdown system.
A DDDDD B Dl2IDl2I D C D DD121 FROM: 10/1/97 TO: 4/30/98 Page 8 of 14 FOR PUBLIC RELEASE Last Updated: 5/30/98
SURRY 05-Jun-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMMCODES 3/21/98 Positive SAQV IR-98-03 NRC The licensee has complied with the program requirements for conducting audits of 1 2 3 4 5
radiological protection and chemistry activities. Extensive documentation of supporting details for the audit conclusions was provided. The audits were of A DODD~
sufficient scope and depth to identify potential problems. Corrective actions were B DODOO documented and tracked for completion.
C ~"""ooo 3/21/98 Positive IR-98-03 NRC The licensee has effectively implemented the radiological environmental monitoring 1 2 3 4 5 program. The sampling, analytical and reporting program requirements were met and the sampling equipment was being well maintained.
A DDDDD B DODOO C ~ ooie 3/21/98 Positive IR-98-03
- NRC The licensee has maintained an effective program for the control of liquid and 1 2 3 4 5 gaseous radioactive effluents from the plant. The radiation doses resulting from those releases were a small percent of regulatory limits.
A DODOO B DODOO C ~ DOD 3/21/98 Positive IR-98-03 NRC The licensee closely monitored annual and outage collective dose and was generally 1 2 3 4 5 very successful in meeting established as low as is reasonably achievable goals.
Maximum individual radiation exposures were controlled to levels which were well A DODOO within the licensee's administrative limits and the regulatory limits for occupational B DODOO does specified in 1 O CFR 20.120(a).
C ~ DOD 1/30/98 Positive IR 98-02 NRC The licensee's overall effectiveness of controls for identifying, analyzing, and 1 2 3 4 5 resolving problems was found superior. The licensee's adequacy of corrective actions to prevent recurring problems was found superior also (Security Area). The A DODD~
inspectors determined that there were strengths in the controls for issues that could B DODOO enhance plant operations or safety. No weaknesses were found that could degrade plant operations or safety.
C ~ DD-1/30/98 Positive IR 98-02 NRC The inspectors verified that the total number of trained security officers and armed 1 2 3 4 5 personnel immediately available to fulfill response requirements met the number specified in the Physical Security Plan. One full-time member of the security A DODOO organization who has the authority to direct security activities did not have duties B DODOO that conflicted with the assignment to direct all activities during an incident. The licensee's response strategy was good and weapons employment was adequate to C ~ DOD meet the design~basis threat.
1/30/98 Strength IR 98-02 NRC The inspector's evaluation of the effectiveness of licensee management related to 1 2 3 4 5 the administration of the security program was found to be superior and considered a strength to the security program.
A DDDDD B DODOO C ~ ~DD FROM: 10/1/97 TO: 4/30/98 Page 9 of 14 FOR PUBLIC RELEASE Last Updated: 5/30/98
SURRY 05-Jun-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd -
ISSUE(s)
SMMCODES 1/30/98 Strength IR 98-02 NRC The inspectors concluded through observation and interviews of security personnel, 1 2 3 4 5 and document reviews that the security force was being trained in a superior manner and according to the Training Qualification Plan and regulatory requirements. This A DDDDD area of the security program was considered a strength by the inspectors.
B DDl2lDD C 12] DOD 1/30/98 Positive IR 98-02 NRC Responses by security to security threats, contingencies, and routine response 1 2 3 4 5 situations, including drills, were consistent with security procedures, the Physical Security Plan, and Security Contingency Plan.
A DD12JDD
-B DODOO C 12] oore 1/30/98 Positive IR 98-02 NRC The inspectors concluded through observations, interviews, and procedure review, 1 2 3 4 5 that the security force had the requisite knowledge to cope with the design-basis threat described in 10 CFR 73.1 (a).
A DDDDD B DDl2lDD C 12] DOD 1/30/98 Negative IR 98-02 NRC One vulnerability in the protected area access control area and two vulnerabilities in 1 2 3 4 5 the protected intrusion detection system were found.
A Dl2JDDD B DODOO C 12] DOD 1/30/98 Positive IR 98-02 NRC The inspectors determined that the licensee's access control equipment and 1 2 3 4 5 personnel, intrusion detection equipment, assessment abilities, and alarm station operations met the requirements of the Physical Security Plan.
A Dl21DDD B Dl2JDDD C 12] ooce 1/26/98 DEV IRs 97-09 & 12, DEV 5-LICENSEE Following an enforcement conference this item which was first proposed as a 1 2 3 4 5 280, 281/ 97-009-09 violation for failure to meet the requirements of Appendix R for circuit breaker coordination was issued as a deviation from a commitment of the UFSAR.
A DDDl2JD B DODOO C 12] ODD 1/26/98 VIO IRs 97-09 & 12, EA 97-NRC Following an enforcement conference a SL IV Violation was issued for failure to 1 2 3 4 5 474 02014, EEi 970009-report the Appendix R discrepancies to the NRC in accordance with 10 CFR 50. 72.
06 A DDDDl21 B DODD l2J C [8J ODD FROM: 10/1/97 TO: 4/30/98 Page 10 of 14 FOR PUBLIC RELEASE Last Updated: 5/30/98
DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd 1/26/98 VIO IRs 97-09 & 12, EA 97-NRC 474 01023, EEi 97009-05 1/26/98 VIO IRs 97-09 &12, VIO EA LICENSEE 97-474 01013,LER 280/97007 12/27/97 Positive IR-97-12 NRC 12/27/97 Positive IR-97-12 NRC 12/27/97 Strength IR-97-12 NRC 12/27/97 Positive IR-97-12 NRC 11/15/97 Positive IR-97-10 NRC FROM: 10/1/97 TO: 4/30/98 Page 11 of 14 SU RRY ISSUE(s)
Following a n enforcement conference a Severity Level Ill Violation was issued for the licensee to correct the Appendix R discrepancies in a timely the failure of manner.
Following a n enforcement conference a Severity Level Ill violation was issued for ate fire protection features which failed to meet the requirements of ppendix R. The control room complex and safety related vital electrical the inadequ 10CFR50A panels were not fully protected. One train of systems necessary to achieve and shutdown condition from either control room or emergency control mote shutdown panels) would not be free from fire damage. EA 97-474 maintain hot stations (re 01013, NOD 280,281/97009-09 The license e had implemented and maintained a program for obtaining and amples of reactor coolant and containment atmosphere under accident n accordance with TS requirements and UFSAR commitments.
analyzing s conditions i The license e's water chemistry control program for monitoring primary and water quality had been implemented in accordance with the TSs secondary requirement sand industry guidelines for pressurized water reactor water chemistry.
The license e's program for transportation of radioactive materials had been mplemented pursuant to Department of Transportation and NRC Enhanced procedures for shipping radioactive materials were a effectively i regulations.
strength.
The tcital nu mber of temporary modifications, four on Unit 1 and none on Unit 2, willingness to correct problems in an expeditious manner. The TMs had ations which were completed prior to installation.
indicated a safety evalu The review of three quarterly Security Event Logs verified that the licensee was y analyzing, tracking, resolving and documenting safeguards events.
appropriate!
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B C
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B C
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B C
A B
C 05-Jun-98 SMMCODES 1 2 3 4 5 0001210 DODOO 12]
0012]
1 2 3 4 5 DDDl2JD DODD*
l2l DD 1 2 3 4 5 DODOO 0121000 12] ODD 1 2 3 4 5 DODOO DODOO 12] ODD 1 2 3 4 5 DODOO DODD*
l2l DD 1 2 3 4 5 DODOO DDDl2JD D 0012]
1 2 3 4 5 DODOO DDDDl2l 12]
0012]
FOR PUBLIC RELEASE Last Updated: 5/30/98
SURRY 05-Jun-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMMCODES 11/15/97 Positive IR-97-10 NRC Intrusion detection systems and assessment aids were functional, well maintain~d.
1 2 3 4 5 effective for both covert and overt penetration attempts and met licensee, 0[2]00D
- commitments.
A B DODOO C r2] DOD 11/15/97 Positive IR-97-10 NRC Criteria in Chapters 1,4, and 6 of the Physical Security Plan and Security Plan 1 2 3 4 5 Implementing Procedures were complied with for alarm stations and communications.
A DDDDD B Dr2JDDD C r2] 0019 11/15/97 Positive IR-97-10 NRC The evaluation of the licensee's program for protected area access controls for 1 2 3 4 5 packages, personnel and vehicles revealed that the criteria of the Physical Security Plan were being followed.
A DODOO B DODOO C '[2] ODD 11/15/97
.Positive IR-97-10 NRC
- A significant amount of activity was removed from the Reactor Coolant System by 1 2 3 4 5 shutdown chemistry controls in order to reduce exposure to workers during the U2 Refueling Outage.
A DODOO B DODOO C [2J DOD 11/15/97 Positive IR-97-10 NRC Personnel entering the Radiological Controlled Area were adequately briefed on 1 2 3 4 5 radiological hazards and protective measures.
A DODOO B DODOO C r2] DD-11/15/97 Positive IR-97-10 NRC During the U2 refueling outage, the licensee was properly monitoring and controlling 1 2 3 4 5 personnel radiation exposure and posting area radiological conditions in accordance with 10 CFR Part 20.
A DODOO B DODOO C r2] ODD 10/4/97 NCV IR 97-09, NCV 280, LICENSEE A Non-Cited Violation was identified concerning the failure to perform fire watch 1 2 3 4 5 281/97009-08 tours within the specified one hour time frame.
A DODOO B Dr2lr2lD D C r2] ODD FROM: 10/1/97 TO: 4/30/98 Page 12 of 14 FOR PUBLIC RELEASE Last Updated: 5/30/98
DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd 10/4/97 Negative IR 97-09 NRC 10/4/97 Positive IR 97-09 NRC FROM: 10/1/97 TO: 4/30/98 Page 13 of 14 SURRY ISSUE(s)
A justification for changes to the Radwaste Facility building structure, equipment and facility process was not being maintained.
Excellent housekeeping was provided for the Radwaste Facility with good implementation of the station's fire prevention procedures and maintenance of the fire protection equipment.
A B
C A
B C
05-Jun-98 SMMCODES 1 2 3 4 5 DDDt2JD
- DODOO l8l ODD 1 2 3 4 5 Dt2JDDD DODOO t2J 009 FOR PUBLIC RELEASE Last Updated: 5/30/98
DATE SURRY 05-Jun-98 TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
1A OPERATION PERFORMANCE - Normal Operations 18
- OPERATION PERFORMANCE - Operations During Transients 1C OPERATION PERFORMANCE - Programs and Processes 2A MATERIAL CONDITION - Equipment Condition 28 MATERIAL CONDITION - Programs and Processes 3A HUMAN PERFORMANCE - Work Performance 38 HUMAN PERFORMANCE - KSA 3C HUMAN PERFORMANCE-Work Environment 4A ENGINEERING/DESIGN - Design 48 ENGINEERING/DESIGN - Engineering Support 4C ENGINEERING/DESIGN -
Programs and Processes 5A PROBLEM IDENTIFICATION & SOLUTION - Identification 58 PROBLEM IDENTIFICATION & SOLUTION - Analysis 5C PROBLEM IDENTIFICATION & SOLUTION - Resolution SALP Functional Areas:
ENG MAINT OPS ENGINEERING MAINTENANCE OPERATIONS PL T SUP PLANT SUPPORT ID Code:
LICENSEE --[LICENSEE NRC NRC SELF SELF-REVEALED e
EEis are apparent violations of NRC requirements that are being considered for escalated enforcement action in accordance with the "General Statement of Policy and Procedure for NRC Enforcement Action" (Enforcement Policy), NUREG-1600. However, the NRC has not reached its final enforcement decision on the issues identified by the EEis and the PIM entries may be modified when the final decisions are made. Before the NRC makes its enforcement decision, the licensee will be provided with an opportunity to either (1) respond to the apparent violation or (2) request a predecisional enforcement conference.
URls are unresolved items about which more information is required to determine whether the issue in question is an acceptable item, a deviation, a nonconformance, or a violation.
However, the NRC has not reached its final conclusions on the issues, and the PIM entries may be modified when the final c_onclusions are made.
e FROM: 10/1/97 TO: 4/30/98 Page 14 of 14 FOR PUBLIC RELEASE Last Updated: 5/30/98
INSPECTION*PROCEDURE/
TEMPORARY INSTRUCTION TITLE/PROGRAM.AREA IP 62700 MAINTENANCE PRACTICES IP 81700 PHYSICAL SECURITY PROGRAM FOR POWER REACTORS IP 84750 RADIOACTIVE WASTE TREATMENTA AND EFFLUENT ND ENVIRONMENTAL MONITORING IP 86750 SOLID RADIOACTIVE WASTE MANAGEMENT &
TRANSPORTATION OF RADIOACTIVE MATERIALS IP 92903 FOLLOWUP -
ENGINEERING IP 92902 FOLLOWUP -
MAINTENANCE IP 92902 FOLLOWUP -
MAINTENANCE IP 83750 OCCUPATIONAL RADIATION EXPOSURE IP 62700 MAINTENANCE PRACTICES SURRY INSPECTION PLAN NUMBER OF PLANNED INSPECTION INSPECTORS DATES 1
JULY 1998 1
JULY 1998 1
AUGUST 1998 1
AUGUST 1998 1
AUGUST 1998 1
SEPTEMBER 1998 1
OCTOBER 1998 1
NOVEMBER 1998 TYPE OF INSPECTION/
COMMENTS REGIONAL INITIATIVE/
FOCUS ON POST-MAINTENANCE TESTING PROBLEMS CORE CORE REGIONAL INITIATIVE/
A/E FOLLOWUP (2 WEEKS)
REGIONAL INITIATIVE/
FOCUS ON PRA FOR MAINTENANCE RULE e
REGIONAL INITIATIVE/
FOCUS ON MAINTENANCE RULE PERIODIC ASSESSMENTS APART WEEK AT NORT ANNA)
CORE/FOCUS ON OUTAGE ACTIVITIES REGIONAL INITIATIVE/
FOCUS ON PORV
INSPECTION PROCEDURE/
TITLE/PROGRAM AREA NUMBER OF PLANNED INSPECTION TYPE OF INSPECTION/
TEMPORARY INSTRUCTION INSPECTORS DATES COMMENTS IP 73753 INSERVICE 1
NOVEMBER 1998 CORE/FOCUS ON SERVICE INSPECTION WATER PIPING IP 81700 PHYSICAL SECURITY 1
DECEMBER 1998 CORE k~2~~~sFOR POWER Surry 2 of 2