ML18152B713
| ML18152B713 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/02/1998 |
| From: | Haag R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 9812180060 | |
| Download: ML18152B713 (32) | |
Text
-
Virginia Electric and Power Company ATTN:
Mr. J. P. O'Hanlon December 2, 1998 Senior Vice President - Nuclear Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060
SUBJECT:
INSPECTION PLAN - SURRY POWER STATION
Dear Mr. O'Hanlon:
On November 2, 1998, the NRC staff completed an inspection resource planning meeting. The staff conducted this review for all operating nuclear power plants in Region II to develop an integrated inspection plan. We conducted this meeting in lieu of the semiannual Plant Performance Review, which the*staff has moved to February 1999 because of the agency's shift to an annual Senior Management Meeting cycle.
This letter advises you of our planned inspection effort resulting from the inspection planning meeting. We have provided it to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved before the inspector's arrival onsite. Enclosure 1 details our inspection plan for the next 4 months. We have provided the rationale or basis for each inspection outside the core inspection program 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 continue to focus some of our discretionary inspection effort on the resolution of open inspection items. Therefore, we may conduct additional inspections, which are not listed on Enclosure 1, to close open inspection items that are ready to be resolved. We will notify you at least 3 weeks before the start of these inspections.
The NRC's general policy for reactor inspections is that we will announce each inspection, unless announcing the inspection could compromise the objectives of the inspectors.
Therefore, we may not have included some specific inspections on Enclosure 1, such as in the security and radiological protection areas, and these inspections may not be announced. contains a historical listing of plant issues, called the Plant Issues Matrix (PIM).
The PIM includes only items from inspection reports or other docketed correspondence between the NRC and Virginia Power and Electric Company. This material will be placed in the Public Document Room.
9812180060 981202 PDR ADOCK 05000280 G
VEPCO 2
We will inform you of any changes to the enclosed inspection plans. If you have any questions, please contact me at (404) 562-4550.
Docket Nos. 50-280, 50-281 License Nos. DPR-32, DPR-37
Enclosures:
- 1. Inspection Plan
- 2. Plant Issues Matrix cc w/encls.:
J. H. McCarthy, Manager Nuclear Licensing and Operations Support Virginia Electric & Power Company 5000 Dominion Boulevard Glen Allen, VA 23060 E. S. Grecheck Site Vice President Surry Power Station Virginia Electric & Power Company 5570 Hog Island Road Surry, VA 23883 W.R. Matthews Site Vice President North Anna Power Station P. 0. Box402 Mineral, VA 23117 Chairman Surry County Board of Supervisors P. 0. Box 130 Dendron, VA 23839 cc w/encls. continued: See page 3 Sincerely, Orig signed by Robert C. Haag Robert C. Haag, Chief Reactor Projects Branch 5 Division of Reactor Projects
VEPCO cc w/encls.: Continued Virginia State Corporation Commission Division of Energy Regulation P. 0. Box 1197 Richmond, VA 23209 Donald P. Irwin, Esq.
Hunton and Williams 951 East Byrd Street Richmond, VA 23219-4074 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 3
OFFICE SIGNATURE NAME VEPCO Distribution w/encls.:
L. Plisco, RII R. Aiello, RII P. Fillion, RII R. Gibbs, RII D. Jones, RII W. Stansberry, RII G. Edison, 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 4
INSPECTION TITLE/PROGRAM PROCEDURE/
AREA TEMPORARY INSTRUCTION
.PHYSICAL IP 81700 SECURITY PROGRAM FOR POWER REACTORS IP 84750 RADIOACTIVE WASTE TREATMENT, AND EFFLUENT AND ENVIRONMENTAL MONITORING IP 86750 SOLID RADIOACTIVE WASTE MANAGEMENT &
TRANSPORTATION OF RADIOACTIVE MATERIALS IP 92904 FOLLOWUP-ENGINEERING IP 92903 FOLLOWUP-ENGINEERING IP 81700 PHYSICAL SECURITY PROGRAM FOR POWER REACTORS SURRY*
INSPECTION PLAN NUMBER OF PLANNED INSPECTORS INSPECTION DATES 1
DECEMBER 1999 1
JANUARY 1999 1
JANUARY 1999 1
FEBRUARY 1999 1
FEBRUARY 1999 TYPE OF INSPECTION/
COMMENTS CORE CORE REGIONAL INITIATIVE -
FOLLOWUP ON FIRE PROTECTION RELATED e
VIOLATION REGIONAL INITIATIVE -
A/E FOLLOWUP AND GL 96-01 CORE
INSPECTION TITLE/PROGRAM NUMBER OF PLANNED TYPE OF INSPECTION/
PROCEDURE/
AREA INSPECTORS INSPECTION COMMENTS TEMPORARY DATES INSTRUCTION IP 71001 LICENSED 3
MARCH 1999 CORE-ONE WEEK OPERATOR INITIAL EXAM PREP.
REQUALI Fl CATION ONE WEEK INITIAL PROGRAM EXAMS EVALUATION IP 60855 OPERATION OF AN 1
MARCH 1999 REGIONAL INITIATIVE -
ISFSI FACILITY MONITORING IP 82701 OPERATIONAL 1
MARCH 1999 CORE STATUS OF THE EMERGENCY PREPAREDNESS PROGRAM IP 92903 FOLLOWUP-1 MARCH 1999 REGIONAL INITIATIVE -
ENGINEERING A/E FOLLOWUP IP 92903 FOLLOWUP-1 MARCH 1999 REGIONAL INITIATIVE -
ENGINEERING MAINTENANCE RULE (PAA)
Page 2 of 2 e
~aye; I ol ~
United States Nuclear Regulatory Commission Dale: 12/02/1998 Time: 16:53:36 Region II PLANT ISSUE MATRIX SURRY By Primary Funcflonal Area Functlonal Template Dale Source Area ID Type Codes Item Description 10/24/1998
- 1998008 Prl:.ENG NRC NEG Prl: 48 An Informal process was used to ensure an adequate water thermal barrier was being maintained on lhe Sec:
Sec: 4C containment side of the safety Injection containment suction gate valves lo prevent pressure locking of these valves during an accident. Once the Inspectors Identified this lo the licensee. a procedure change was issued Ter: lA to give specific formal guidance to plant operators. A 10 CFR 50.59 safely evaluation was performed which supported the revision.
09/05/1998 1998007 Prl: ENG NRC POS Prl: 4C The Maintenance Rule periodic assessment met the requirements of paragraph (a)(3) of ll1e Maintenance Rule.
Sec:
Sec:
Ter:
09/05/1998 1998007 Prl: ENG NRC WK Prl: 58 There was a weakness. acknowledged by the licensee. In the area of documenting how significant Information e Sec:
Sec:4B such as Information notices Is disposed when that disposition Involves closure without a detailed review by an Operating Experience group reviewer.
Ter:
09/05/1998 1998007-01 Pri: ENG NRC VIOIV Prl: SC A violation was Identified for not correcting design problems. conditions adverse lo quality. in a timely manner.
Sec:
Sec: 4A In 1992 the licensee Identified that the selpolnt for the overcurrent protection of the Inside recirculation spray pump motors could result In spurious tripping upon motor starting. and that there was no analysis or lest to Ter: 4C demonstrate that the components In the 125 VDC Station Battery Distribution System would receive roted voltage tor all design basis scenarios. However. these conditions were not corrected as of August 1998. This Item was previously Identified In IR 98-201.
09/05/1998 1998007-02 Prl: ENG Licensee NCV Prl: SB A Non-Cited Violation was Identified concerning surveillance test control. When In the test alignment. the Sec:
Sec:5C Emergency Ventilation FIitration System was outside the design basis. The cause of this problem was that the test procedure OPT-ZZ-001 did not adequately control the test In that It did not specify restoring the normal alignment Ter:
Immediately following the test. nor did It Initiate an Limiting Condition tor Operation (LCO) clock when the test alignment was entered.
09/05/1998 1998007-03 Pri: ENG NRC URI Prl: 4C Failure lo submit LER within 30 days. The llcensee stated the Interpretation that 10 CFR 50.73(a)(l). which requires Sec:
Sec:
that LERs be submitted within 30 days otter discovery of the event, allows tor evaluation lime In lhe case of design basis Issues. Their practice has been to start the 30 day clock upon final determination that the condition e Ter:
Is In fact reportable.
09/05/1998 98007-00 Prl: ENG NRC NOED Prl: 4A Violations of 10 CFR 50.7l(e) for failure to update the UFSAR and 10 CFR 50.59 for the facility not being as Sec:
Sec:
described In UFSAR were Identified. However. the NRC Is exercising discretion and refraining from issuing a Notice of Violation In consideration of the llcensee having a good UFSAR review program in progress. This Item Ter:
was previously Identified In IR 98-201.
10/24/1998 1998008 Pri: MAINT NRC POS Prl: 3A Service water strainer maintenance activities were completed In a thorough and professional manner.
Sec:
Sec:3B Maintenance personnel were knowledgeable of the assigned task. procedures were detailed and actively used on the Job. and cooperation and coordination between the various plant groups were good.
Ter:
llem Type (Compliance,Followup,Otl1er), From 09/01/1998 To 12/02/1998
Page: :lolb United States Nuclear Regulatory Commission Dale: 12/02/1998 Time: 16:53:36 Region II PLANT ISSUE MATRIX SURRY By Primary Funcflonal Area Functional Template Dale Source Area ID Type Codes Item Description 10/24/1998 1998008 Prl: MAINT NRC POS Prl: 3C Control room leakage testing using the Unit 1 cable tunnel air bottles was performed In accordance wilh Sec:
Sec:2B procedural requirements and demonstrated the ablllty to maintain the control room envelope at positive pressure for one hour. Additionally, senior reactor operator oversight was detailed.
Tar:
10/24/1998 1998008 Pri: MAINT NRC POS Prl: 3C Maintenance personnel completed the reactor coolant filter replacement using approved procedures.
Sec:
Sec: 2B Appropriate coordination. pre-Job preparation. and supervisory oversight enabled the maintenance crew lo successfully replace the filter while giving appropriate consideration to as-low-as-ls-reasonably achievable Ter: 3A principles.
10/24/1998 1998008 Pri: MAINT NRC POS Prl: 5A The post maintenance testing (PMT) program was effective for Its Intended function and was implemented e properly. The PMT program self-assessment identified valuable recommendations. which were being Sec:
Sec:2B Implemented. for Improving the program. Deviation reports related to PMT were adequately dlsposilioned. Post Ter: 3A maintenance tests were performed as stated In work orders.
10/24/1998 1998008-0l Pri: MAINT NRC EEi Prl: 2B A vlolatlon was Identified for falling to follow procedure requirements by running the control room air filtration Sec:
Sec:JA system with painting occurring In the vicinity of the Intake of the system. Pending the licensee's development of corrective actions. this matter will be tracked as an EEi.
Ter:
09/05/1998 1998007 Prl: MAINT NRC POS Prl: 2B Unit 2 turbine Inlet valve freedom testing was accomplished In accordance with the procedure requirements Sec:
Sec:
and the test results were acceptable.
Ter:
09/05/1998 1998007 Prl: MAINT NRC POS Prl: 2B Ventilation damper maintenance activities were properly documented and procedures were present at the Job Sec:
Sec:JA site during work activities.
Ter:
e 10/24/1998 1998008 Prl: OPS NRC NEG Pri: SC The Inspectors determined that the Component Cooling Water system valve alignment procedure did not Sec:
Sec: lA address all the valves In the system. The licensee Issued a deviation report otter the Inspectors informed management that some of these problems had been Identified In June 1997 and no permanent proc.edure Ter:
change had been Initiated.
10/24/1998 1998008 Prl: OPS NRC POS Pri: lA Reactor coolant system dralndown activities to flange level were well controlled and accomplished In Sec:
Sec:JA accordance with the procedural requirements.
Ter:
Item Type (Compliance,Followup,Olher), From 09/01/1998 T9 12/02/1998
3 of 5 Page:
United States Nuclear Regulatory Commission Dale: 12/02/1998 Time: 16:53:36 Region ti PLANT ISSUE MATRIX SURRY By Primary Functional Area Functional Template Dale Source Area ID Type Codes Item Description 10/2'1/1998 1998008 Prl: OPS NRC POS Prl: 1A The shutdown of Unit 1 for a scheduled refueling outage was well executed. During a problem wi1h an electrical Sec:
Sec: 3A breaker. plant conditions were well managed by the control room operations staff.
Tar: 2A 10/2'1/1998 1998008 Pri: OPS NRC POS Prl: 2A The Inspectors performed a detailed walkdown of the Unit 1 containment following plant shutdown. Overall Sec:
Sec:
condition of the Unit 1 containment was observed to be very good with minimal leaks noted.
Tar:
10/2'1/1998 1998008 Prl: OPS NRC POS Prl: 2A Portions of the Unit 1 Component Cooling Water system which support spent fuel pit cooling and residual heat e Sec:
Sec: lA removal and the Unit 2 Low Head Safety Injection system were properly aligned and material condition of 1he equipment was good.
Ter:
10/2'1/1998 1998008 Prl: OPS NRC POS Prl: 3A The reactor operator restoration brief for unlnterruptlble power supply 282 was thorough. Operators exhibited a Sec:
Sec: lA good questioning attitude by asking questions to ensure that requirements were understood and by discussing previous restoration problems. The operators correctly used simultaneous verification. verified expected system Tar:
response and adhered to procedures during the restoration.
10/2'1/1998 1998008 Prl: OPS NRC POS Prl:5A Management Safety Review Committee members exhibited a questioning attitude and utilized open discussion Sec:
Sec:
to effectively Identify, assess and recommend solutions to technical Issues. The Inspectors also verified that a quorum was present.
Tar:
09/05/1998 1998007 Prl: OPS NRC NEG Prl: 28 During review of procedure 2-0P-51.5A. "Charging Pump CC and SW Systems Valve Alignment," the inspectors Sec:
Sec:
determined the Charging Pump Component Cooling Water surge tank sight glass Isolation valves were not verified open by the valve alignment procedure. The licensee revised the procedure to require that the valves Tar:
be verified open.
e 09/05/1998 1998007 Prl: OPS NRC POS Prl: lA The Unit 1 Auxlllary Feedwater system was properly aligned for standby operation. The Unit 2 charging pump Sec:
Sec:
component cooling system was properly aligned for normal operation.
Ter:
09/05/1998 1998007 Prt: OPS NRC POS Prl: lA Licensee actions In preparation for the potential arrival of Hurricane Bonnie were conservative and station Sec:
Sec: 18 operation was not Impacted by the storm.
Ter:
llem Type (Compliance,Followup,O!her), From 09/01/1998 To 12/02/1998
DATE TVPE(s)
SEC.SFA I OPERATIONS 7/25/98 Negative ENG 6/13/98 URI 6/13/98 Strength ENG 6/13/98 Positive 6/13/98 Positive 6/13/98 Positive FROM: 10/1/97 TO: 8/31/98 United States Nuclear Regulatory Commission PLANT ISSUES MATRIX by SALP Functional Area SURRY SOURCE(s)
ID'd ISSUE(s)
- IA 98-06 SELF Marine fouling of canal level probes which has caused slow Instrument response limes continues to be an operational concern. The licensee has Implemented Increased Inspections, testing, and cleaning of the probes to ensure operability in the short term and has Initiated a root cause evaluation to develop long term corre.ctive actions.
IA 98-05 281/98005-01 LICENSEE An unresolved Item was Identified concerning non-conservative power calculations resulting from out of calibration feedwater resistance temperature detectors.
IA 98-05 NRC Although not required by regulations, the licensee performs monthly sampling of containment air to determine the hydrogen concentration. The sampling resulted in the Identification and correction of a steam leak which had increased the Unit 2 containment hydrogen concentration from non-detectable to 0.72 percent. The containment air sampling program for hydrogen is considered a strength.
IA 98'.05 NRC The Unit 1 startup was performed In a well controlled manner and In accordance with operating procedures. The operating crew was well focused on tasks throughout the evolution.
IA 98-05 NRC Operations demonstrated a good questioning attitude by Identifying that normally closed containment Isolation sample valves were leaking into a sample sink.
Declaring the containment Isolation valves Inoperable, securing the leak path from containment by closing manual valves and calculating the contribution to the total containment leakage adequately addressed the leakage through both containment Isolation valves.
IA 98-05 NRC The licensee's sensitivity to a minor Increase (approximate 0.20 gpm) In reactor coolant system leakage was noteworthy. The source of increased leakage was promptly Identified as a non-lsolable leak In the C reactor coolant pump seal injection line. Technical Specification requirements were complied with by placing Unit 1 In cold shutdown.
Page 1 of 21 FOR PUBLIC RELEASE Last Updated:
02-Dec-98 SMM CODES 1 2 3 4 5
A 0000 l'Sl B DODD l'Sl C D ODD e 1 2 3 4 5
A DODOO B 0[8)0[8]0 C o. DOD 1 2 3 4 *5 A 0000[8]
B DODOO C [8]
DOD 1 2 3 4 5 A [8]0[8]00 B DODOO C D DOD e 1 2 3 4 5
A 00000 B DODOO C D DOD 1 2 3 4 5 A l.8lDDDC8l B l.8lDDD D C D ODD 7/25/98
SURRY 02-Dec-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 5/2/98 Positive IA 98-04 NRC The Unit 1 manual Auxiliary Feedwater System isolation valves inside containment 1 2 3 4 5 were properly aligned for normal operation and were properly identified.
A 00000 B DODOO C D DOD 5/2/98 Negative IA 98-04 SELF The licensee performed an inadequate tagout on the bearing cooling water system 1 2 3 4 5 which demonstrated a lack of sensitivity to the tagout process. Based on this event
!8lDC8lDD and previous problems the Inspectors are concerned with the declining performance A
by some operations department personnel in regards to the tagout process and DODOO configuration control.
B C D ODD e 5/2/98 Positive ENG IA 98-04 NRC The licensee's actions related to spent fuel storage pool Issues were in accordance 1 2 3 4 5 with commitments made to the NRC-The inspectors verified that a change to the pool high temperature alarm and operational procedural enhancements have been A DODOO made. The one remaining commitment, providing emergency power lo the spent DODOO fuel pool cooling pumps, was scheduled for completion by the end of February B
1999.
C D D C8l C8l 5/2/98 Positive IA 98-04 NRC Unit 1 startup activities were accomplished In accordance witli approved procedures 1 2 3 4 5 in a thorough and controlled manner. The operating crew exhibited good communications during the startup activities and distractions in the control room A 00000 were minimized DODOO B
C D 12.1 DD 5/2/98 VIO IA 98-04, VIO 98004-02 NRC A violation was Identified concerning an inadequate operating procedure revision 1 2 3 4 5
which failed to properly adjust the steam generator power operated relief valve se_lpoinls. The failure lo Identify the procedure Inadequacy prior to and while A DDC8lDD performing the procedure demonstrated a lack of attention to detail on the part of the DODOO operator, other members of the operating crew Involved with the setpoinl change, B
and the procedure writers.
C D 12.1 DD 5/2/98 Positive ENG IA 98-04 NRC Licensee actions with respect to a residual heat removal system through-wall flaw 1 2 3 4 5 e demonstrated a good safely perspective and conservative decision making.
Technical Specification requirements concerning decay heal removal loops were A 012.100[8]
met. The decision lo remove the flaw intact to try to determine the root cause was DODOO appropriate.
B C D DD 12.1 3/21/98 Positive SAQV IA 98-03 NRC The licensee's deficiency Identification and reporting and corrective action programs 1 2 3 4 5 were effectively Identifying Issues, and recommending and implementing appropriate corrective action. There were approximately 45 overdue responses to A ODDO C8l deviation reports with the majority being assigned to engineering. The licensee has 00000 initiated action to resolve this backlog. Licensee self-assessment effectively B
evaluated the corrective acti!)n program.
C D 000 FROM: 10/1/97 TO: 8/31/98 Page 2 of 21 FOR PUBLIC RELEASE Last Updated: 7/25/98
- SURRY 02-Dec-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12/27/97 Negative IA 97-12, LEA 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 operailng crew to plant conditions resulted In Stearn Generator Powe: Operated A 1'3]1'3][2]00 Relief Valve actuations.
DODOO B
C D DOD 12/27/97 Weakness IA 97-12 NRC While returning the Alternate AC Diesel Generator to service, the operating crews 1 2 3 4 5 demonstrated a willingness to accept Inadequate instructions and exhibited a lack of DDl2?lD D attention to detail and questioning attitude. This evolution also revealed a weakness A
In control of trainees.
D0[8]DD B
C D DOD e 12/27/97 VIO IA 97-12 NRC A violation was Identified Involving the failure to properly per1orrn the verification that 1 2 3 4 5 the Alternate AC Diesel Generator breaker control switches were in the Auto-after-Trip position as required by operator logs.
A C8]0C8]0 D B DODOO C D ODD 12/27/97 VIO IA 97-12 SELF A violation was Identified for the failure to have appropriate instructions available to 1 2 3 4 5 the return the Alternate AC 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 00000 B 0[8)00 D C D DOD 11/26/97 LEA LEA 280, 281/97012-00 LICENSEE EQ Unanalyzed Condition/Outside App. R Design Basis Due to Unlatched Doors.
1 2 3 4 5
& 97012-01 A DDOl2?l D B DODOO C D DOD 11/15/97 Positive IR97-10 NRC Observations by the inspectors during the defueling of the Unit 2 reactor indicated a 1 2 3 4 5 -
well controlled process being carried out In accordance with Technical Specifications. Effective foreign material exclusion practices were in place.
A 00000 B 0[8)000 C D ODD 11/15/97 Negative IA 97-10 NRC In general the licensee's preparation of the Unit 2*containrnent prior to restart from 1 2 3 4 5 the refueling outage was adequate. Minor deficiencies were identified that indicated a more thorough licensee walkdown should have been performed. These items A 0000 0 were corrected prior to containment closeout.
DODOO B
C D DOD FROM: 10/1/97 TO: 8/31/98 Page 4 of 21 FOR PUBLIC RELEASE Last Updated: 7/25/98
SURRY 02-Dec-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 3/21/98 Positive SAQV IR 98-03 NRC The licensee's oversight process was effective In Identifying programmatic 1 2 3 4 5 problems. With the exception of.an audit finding that was not clearly characterized, DODD [8]
the reviewed audits exhibited good self assessment techniques and met program A
requirements.
DODOO 8
C D DOD 3/21/98 Positive IR 98-03 NAC Observed Unit 1 shutdown activities were conducted in accordance with approved 1 2 3 4 5 procedures. Command and control during unit stabilization at four percent power 1'21000 D was good and operators controlled plant parameters well during_ generator voltage A
regulator testing.
DODOO 8
C* D DOD e 2ll/98 Negative IA 98-01, LEA 280/98-03 LICENSEE The licensee Identified that under certain conditions the seven day fuel oil design 1 2 3 4 5 basis requirement for the No 3 emergency diesel generator could not be met.
000[8] D Procedural controls were Implemented to ensure the fuel oil supply was adequate lo A
meet design basis requirements.
000[8] D 8
C D DD l8l 2ll/98 Positive MAINT IA 98-01 NAC Cold weather preparations were adequately Implemented and were in accordance 1 2 3 4 5 with approved procedures. Licensee Identified discrepancies were corrected prior to the onsef of cold weather.
A [8][8]000 8 DODOO C D ODD 2ll/98 Negative IA 98-01, LEA 280/98-02 LICENSEE The licensee was unable to Identify the cause of the Unit 1 voltage regulator failure 1 2 3 4 5 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 A [8][8]000 In manual at the time of the trip.. The voltage regulator was repaired for automatic DODO@
operation.
8 C D ODD 2!7/98 Positive IA 98-01, LEA 280/98-02 SELF Unit 1 plant response following an automatic reactor trip was normal and plant 2 3 4 5 e systems operated as designed. Subsequent startup activities were conducted in accordance with approved procedures and In a controlled manner.
A @DODD 8 DODOO C D DOD 12/27/97 Positive IA 97-12 NAC 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 setpolnt and with Turbine Driven Auxiliary Feedwater Pump was A 1'21000 D conservative and demonstrated a good safety perspective.
DODOO 8
C D ODD FROM: 10/1/97 TO: 8/31/98 Page 3 of 21 FOR PUBLIC RELEASE Lest Updated: 7/25/98
Page: 4 of 5 United States Nuclear Regulatory Commission Date: 12/02/1998 Time: 16:53:36 Region II PLANT ISSUE MATRIX SURRY By Primary Functional Area Funcfional Template Dale Source Area ID Type Codes Item Description 10/24/1998 1998008 Prl: PLTSUP Licensee NEG Prl: IC Improper pre-staging of some personnel during an emergency drill resulted in a failure to demonstrate. by one Sec:
Sec:
position. that minima! staffing In the Technical Support Center could be accomplished within ll1e required time frame.
Ter:
10/24/1998 1998008 Prl: PLTSUP NRC POS Prl: lC The licensee was properly monitoring and controlling personnel radiation exposure during the Unit I Refueling Sec:
Sec:
Outage and posting area radiological conditions In accordance with 10 CFR Part 20. The licensee had Implemented an eHectlve shutdown chemistry control plan and closely monitored primary coolant chemistry Ter:
during the shutdown for the Unit 1 Refueling Outage.
10/24/1998 1998008 Pri: PLTSUP NRC POS Prl: lC The overall performance of the emergency response organization during an emergency drill demonstrated the -
Sec:
Sec:
licensee's ability to adequately execute the emergency plan.
Ter:
09/05/1998 1998007 Prl: PLTSUP NRC POS Prl: lC The licensee was maintaining radioactive effluent monitoring Instrumentation In an operable condition and Sec:
Sec: 2A performing the required surveillances to demonstrate their operability.
. Ter: 28 09/05/1998 1998007 Pri: PLTSUP NRC POS Prl: lC The licensee was maintaining the Control Room Emergency Ventilation System in an operable condition and Sec:
Sec: 2A performing the required surveillances lo demonstrate operability of the systems.
Ter: 28 09/05/1998 1998007 Prl: PLTSUP NRC POS Prl: lC The onslte meteorological measurements* program was Implemented In accordance with the Updated Final Sec:
Sec:20 Safety Analysis Report.
Ter:
e 09/05/1998 1998007 Pri: PLTSUP NRC POS Prl: lC Health physics practices were observed to be proper and high radiation doors were found lo be in good Sec:
Sec:JA condition and tocked.
Ter: lA llem Type (Compliance,Followup,Other), From 09/01/1998 To 12/02/1998
Page: 5 ol 5 United States Nuclear Regulatory Commission PLANT ISSUE MATRIX Dale: 12/02/1998 Type Codes:
BU Bulletin CDR Construction DEV Deviation EEi Escalated Enforcement Item IFI Inspector follow-up item LER Licensee Event Report UC Licensing Issue MISC Miscellaneous MV Minor Violation NCV NonCited Violation NEG Negative NOED Notice of Enforcement Discretion NON Notice of Non-Conformance P21 Parl 21 POS Positive SGI Safeguard Event Report STR Strength URI Unresolved Item VIO Violation WK Weakness By Primary Functional Area Legend Template Codes:
lA Normal Operations 1B Operations During Transients JC Programs and Processes 2A Equipment Condition 28 Programs and Processes 3A Work Performance 38 KSA 3C Work Environment 4A Design 48 Engineering Support 4C Programs and Processes SA Identification SB Analysis SC Resolution ID Codes:
NRC NRC Self Sell-Revealed Licensee Licensee Functional Areas:
OPS Operations MAINT ENG PLTSUP OTHER Maintenance Engineering Plant Support Other Time: 16:53:36 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 Polley). 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.
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. A URI may also be a potential violation that Is not likely to be considered for escalated enforcement action. However, the NRC has not reached its final conclusions on the issues. and the PIM entries may be modified when the final conclusions are made.
Item Type (Compliance,Foliowup,Other), From 09/01/1998 To 12/02/1998 e
SURRY 02-Dec-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 11/15/97 Positive IA 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 wilh approved procedures.
A 00000 B DODOO C D DOD 11/15/97 NCV IR 97-10, NCV 50-280, LICENSEE A Non-Cited Violation was Identified concerning lhe failure lo perform a Technical 1 2 3 4 5 281/97010-03, LEA 97010 Specification required surveillance on the diesel driven fire pump within the required frequency due lo personnel error.
A 00000 B DODOO C D DOD -
11/15/97 Positive IR 97-10 NRG Licensee actions to idenlify and report lhe 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 000[8] t8l B DODOO C D DD D 11/15/97 Positive IR 97-10 NRC Increased Unit 1 reactor coolant activity indicated lhal a fuel cladding defect had 1 2 3 4 5 occurred. The licensee was monitoring and trending coolant activity on a routine basis. The Inspector periodically reviewed reactor coolant sampling results and A IEIDDD D verified that acllvily was well below Technical Specification allowable values.
DODOO B
C [8]
ODD 11/15/97 Positive IR 97-10, LEA 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 Dt8lDD t8l evaluation to determine the cause of the failures.
0000[8]
B C D ODD 11/15/97 Positive IR 97-10 NRC The operators performed their assigned duties in an excellent manner during the U2 1 2 3 4 5 e shutdown for a scheduled refueling outage. The SRO maintained excellent command and control during the evolution. Briefing lhat were thorough and detailed A [8]0000 were made prior to each slgnilicanl evolution.
DODOO B
C D ODD 10/4/97 Positive IR 97-09 NRG For the specific Items inspected, the Surry Operator Requalilication Program fully 1 2 3 4 5 meets lhe requirements and intent of 10CFR55.59(c). The inspectors noted much improvement in the operator requalification program since the last inspection of the A DODOO program.
DODOO B
C !cl ODD FROM: 10/1/97 TO: 8/31/98 Page 5 of 21 FOR PUBLIC RELEASE Last Updated: 7/25/98
SURRY 02-Dec-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 10/4/97 Positive IA 97-09 NRG Hydrogen concentration has continued to decrease within the Unit 1 containment 1 2 3 4 5.
following Installation of a portable autocatalytic recomblrier. The portable recombiner appears to be functioning appropriately to reduce hydrogen A 00000 concentration.
012]00 D B
C D DD l2l 10/4/97 NCV IA 97-09, NCV LICENSEE A Non-Cited Violation was Identified for an Inadequate procedure that failed to verify 1 2 3 4 5 280,281/97009-01 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 A l'EIDDD D prevent recurrence.
DODOO B
C D DD l2l a 10/4/97 Positive IA 97-09 NRG The inspectors verified that Technical Specification requirements were satisfied 1 2 3 4 5 during Unit 1 operation with both Power Operated Retie! Valves isolated.
A l'EJDDD D B DODOO C D DOD 10/4/97 Positive ENG IA 97-09 NRC Licensee actions to repair a minor through wall leak on service water piping were 1 2 3 4 5 conducted in a conservative manner. Operations personnel exhibited a good questioning attitude during Identification of the leaking service water line.
A DDl'EID D B 12lDDDD C D DOD i MAINTENANCE ' / *:* ~'-\\,
>t,**1 7/25/98 NCV ENG IA 98-06, NCV 98006-01 LICENSEE A non-cited violation was issued for the licensee's failure to perform several 1 2 3 4 5 surveillance tests in accordance with Technical Specification requirements. A number of surveillance tests with a specified frequency of 'Each Refueling A DODD 1'E1 Shutdown' were performed with the unit on-line. Subsequent to this finding, a 012]000 Technical Specification amendment was approved to change the specified B
frequency for the tests to once per 18 months. This action closes Unresolved Item C D DD D e 97010-04 (opened on 11/15/97).
7/25/98 Positive IR-98-06 NRG The A Reserve Station Service Transformer load Tap Changer controller relay was 1 2 3 4 5 calibrated in accordance with approved procedures and all test acceptance criteria was met.
A 00[8]00 B 0121000 C D DOD FROM: 10/1/97 TO: 8/31/98 Page 6 of 21 FOR PUBLIC RELEASE Last Updated: 7/25/98
SURRY 02-Dec-98 DATE TVPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 7/25/98 Positive ENG IR-98-06 NRC Canal leve_l probe testing was conducted In accordance with approved procedures.
1 2 3 4 5
The control room was expeditiously notified of the unsatisfactory test results.
00000 A
B 0121000 C D DOD 7/25/98 Positive IR-98-06 NRC Unit 2 reactor coolant pump undervoltage relay replacement activities were 1 2 3 4 5
conducted In a methodical manner In accordance with procedural requirements.
Reactor protection system testing after the relay replacement was conducted in A 0012100 accordance with approved procedures. No deficiencies were identified.
016.JDD D B
C D ODD -
6/13/98 Negative IA 98-05 NRC Reactor coolant system valve 1-RC-6 was replaced In accordance with approved 1 2 3 4 5
procedures. A negative finding was Identified, In that, following removal and prior lo Installing the new valve, continuous monitoring of the freeze seal was not provided A 0012100 by maintenance personnel. This did not meet station management's expectations DODOO which had been conveyed to maintenance prior to the freeze seal installation.
B C D DD D 6/13/98 Positive IR 98-05 NRC Unit 2 turbine governor valve maintenance was well coordinated between operations 1 2 3 4 5
and maintenance. The valve was repaired and returned to service expeditiously following Initiation of the work activity.
A 00000 B 0121000 C D ODO 5/2/98 NCV IA 98-04, NCV 98004-04 LICENSEE A non-cited violation was identified for application of a higher than specified torque 1 2 3 4 5 for the body to bonnet fasteners on two safety injection check valves. An incorrect pressure/torque conversion chart for the torquing device was used to apply an A 00000 approximate torque valve of 4500 loot-pounds In lieu of the specified 2600 loot-00000 pounds of torque.
B C D DOD 5/2/98 Positive IA 98-04 NRC Surveillance activities for a containment radiation monitor were performed in 1 2 3 4 5 a accordance with procedure requirements and the instrumentation and control technicians performing the procedure were knowledgeable of the procedure A 00000 requirements.
0012100 B
C D DOD 5/2/98 Positive IA 98-04 NRC Emergency Diesel Generator Number 3 alarm relay replacement activities were 1 2 3 4 5 accomplished in accordance with the work package instructions. The electricians performing the work were knowledgeable of how to perform the activities. The A 00000 tagout for the work was acceptable.
00000 B
C D ODD FROM: 10/1/97 TO: 8/31/98 Page 7 of 21 FOR PUBLIC RELEASE Last Updated: 7/25/98
SURRY 02-Dec-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 5/2/98 NCV IR 98-04, NCV 98004-03 LICENSEE A non-cited violation was Identified concerning maintenance personnel failing to 1 2 3 4 5
verily 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 A 00000 normal suction valve was performed on the pump's normal discharge valve.
DODOO Identification and corrective actions for this matter were prompt and thorough.
B C D ODD 3/21/98 NCV IR 98-03, NCV 98-003-LICENSEE A Non-Cited Violation was Identified for failure to obtain valid vibration data during an 1 2 3 4 5 01, LEA 98-001 auxiliary leedwater pump surveillance test. Faulty test equipment resulted in the Technical Specification Violation.
A 00[8]00 B D0t8lO, C 0 DO 3/21/98 Positive IR 98-03 NRC Tl,nblne 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 00000 B DODOO C D ODO 3/21/98 Positive IR 98-03 NRC Unlnterruptlble 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 e_lectrlcal work practices.
A 00000 B DOIEJOO C 0 DOD 2/7/98 Positive IR 98-01 NRC Tlie llcenr'3e 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 DODOO B
~ 0~ :*
C 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 00000 of the tasks. The involved plant groups coordinated their activities well.
00000 B
C 0 DOD 2/7/98 Positive IR 98-01 NRC Replacement of a gamma-metrics excore power supply was performed 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 00000 B DODO r2J C 0 DOD FROM: 10/1/97 TO: 8/31/98 Page 8 of 21 FOR PUBLIC RELEASE Last Updated: 7/25/98
SURRY 02-Dec-98 DATE TVPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 2(7/98 VIO IR 98-01, VIO 280,281/98-NRC A violation of 10 CFR 50, Appendix B, 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 auxlllary oil pump motor. The motor failed and resulted in the diesel A 00000 generator being inoperable.
B 00000 C D 000 12/27/97 Positive IA 97-12 NRC Surveillance aclivilies Involving the control room chUlers, an* emergency service 1 2 3 4 5 water pump, and the Turbine Driven Auxiliary Feedwaler Pump were completed in a 00000 thorough and professional manner. Procedures were detailed. Coordination A
between various plant groups was good.
0[2]00.
B C D DD 12/27/97 Negative IR 97-12 NRC The operating experience review staff failed lo 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, al the licensee's North Anna Station.
A 0000!81 B 00000 C D DOD 12/27/97 NCV IR 97-12, LEA 280,281 LICENSEE A nonclled violation was Identified for failing lo test the remote manual undervoltage 1 2 3 4 5 97011 trip prior lo placlng the reactor trip bypass breakers inservice as required by Technical Specifications.
A 00000 B 00000 C D DOD 12/27/97 Positive IR 97-12 NRC Maintenance actlvilies Involving Emergency Diesel Generator radiator louvers, 1 2 3 4 5 control room chiller, and the screen wash system were completed In a thorough and 0012100 professional manner. Maintenance* personnel were knowledgeable of the assigned A
tasks. Procedures were detailed and used on the job.
012]00.
B C D DD 12/27/97 VIO IA 97-12, VIOL 281/97 NRC A violation was Identified for failure lo perform post maintenance testing which was 1 2 3 4 5 03 specified in work instructions for the Unit 2 Turbine Driven Auxiliary Feedwater Pump governor replacement.
A 0012100 B 00000 C D ODD 11/15/97 Positive IR 97-10 NRC Testing of the Unit 2 pressurizer power operated relief valves was conducted In a 1 2 3 4 5 cautious and controlled manner and *as specified by the procedure. The Senior Reactor Operator supervising the lest demonstrated superior command and control A 1210000 over the evolution.
012]000 B
C D DOD FROM: 10/1/97 TO: 8/31/98 Page 9 ol 21 FOR PUBLIC RELEASE Last Updated: 7/25/98
DATE TYPE(s) 11/15/97 Positive 11/15/97 VIO 11/15/97 Positive 11/15/97 Positive 11/15/97 Positive 11/15/97 Positive 11/15/97 Strength FROM: 10/1/97 TO: B/31/98 SEC.SFA SOURCE(s)
IR 97-10 IR 97-10, VIO 50-281/97010-05, LEA 280,281/97008 IR 97-10 IR 97-10 IR 97-10 IR 97-10 IR97-10 ID'd NRC.
SELF NRC NRC NRC NRC NRC Page 10 of 21 SURRY ISSUE(s)
The licensee rebuilt the pressurizer Power Operated Relief Valves (PORVs) during the U2 Refueling Outage. Following return of the unit to service, no Indication of seal leakage was observed. Previously, the Unit 1 PORVs repair efforts were not successful In correcting seat leakage.
A violation was Identified for Inadequate work Instructions resulting In the failure to Implement the prerequisite requirements of a safety evaluation during the replacement of a Consequence Limiting Safeguards relay.
Thirteen observed surveillance tests were performed satisfactorily. Procedures were present and In use. Effective crew briefing were accomplished prior lo performing the tests.
Maintenance activities on protective relays and the condenser water box were performed satisfactorily. Supervisory oversight ensured that the work procedures were adequate and being followed.
Surveillance activities associated with safety Injection accumulator check valve testing end Number 3 Emergency Diesel Generator testing were conducted in accordance with approved procedures end met acceptance criteria.
The licensee's flow accelerated corrosion monitoring program continued to be a well-engineered and conservative program.
Consistent evaluations of eddy current Inspection results and conservative tube plugging decisi.ons were strengths In the licensee's steam generator inspection program.
02-Dec-98 SMM CODES 1 2 3 4 5 A 0[8]000 B 0[8]000 c D DD D 1 2 3 4 5 A DODOO B 0000-C D 000 1 2 3 4 5 A 00000 B 00000 c D DD D 2 3 4 5 A 00000 B DODOO c D
c D DD 1 2 3 4 5 A DODOO B 012]000 c D 00 D 1 2 3 4 5 A DODOO B 012]000 c D DD D FOR PUBLIC RELEASE Last Updated: 7/25/98
DATE TYPE(s)
SEC.SFA 11/15/97 Positive 10/4/97 Positive 10/4/97 Strength 10/4/97 Posilive 10/4/97 Positive 10/4/97 Negalive 10/4/97 Negative
- ENGINEERING FROM
- 10/1/97 TO: B/31/98 SOURCE(s)
IA 97-10 IA 97-09 IA 97-09 IA 97-09 IA 97-09 JR 97-09 IR 97-09, IFI 280, 281 /97009-02 ID'd NAC NAC NAC NAC NRC NAC NAC Page 11 or 21 SURRY ISSUE(s)
The licensee's lnservlce Inspection results were well documented, and the bases for conclusions were conservative.
During the troubleshooting effort for the #1 Emergency Diesel Generator louver controller !allure, maintenance personnel were deliberate and acted In a professional manner.
Forlegn Malerlal Exclusion worker qualification training was considered a strength in that II personalized the negative affects that foreign material can have on employee safely and dose, as well as, the economic impact on the company.
The licensee's actions with regard to surveillance, testing and maintenance of the auxillary shutdown panels and the remote monitoring panels were excellent.
Switches and meters had appropriate operability checks. The UFSAR accurately reflected plant conditions for the panels and corresponding procedures.
Reactor Protection System Logic Testing was performed in an excellent manner.
The l&C technicians were methodical and cautious. Repeat backs and verifications were consistently performed.
The licensee has made an effort lo determine the cause ol 111 Emergency Diesel Generator louver controller failures but has not been successful. Additional effort is required lo return the louvers lo fully functional condition.
Maintenance performed on the Emergency Service Waler Pumps was completed in a satisfactory manner. Problems with marine growth on the pumps have not been adequately resolved. An inspection followup item is being opened lo track the licensee's resolution 02-Dec-98 SMM CODES 1 2 3 4 5 A DODOO B D IZ]D DD c D DD D 1 2 3 4 5 A 00000 8 oooop c D DD 1 2 3 4 5 A DODOO B 012]000 c D DD D 1 2 3 4 5 A DODOO B DIZlDDD c D DD D 1 2 3 4 5 A DDIZlOD B D 121 DD.
c D DD 1 2 3 4 5 A DODOO B 0000121 C D DD 121 1 2 3 4 5 A DODOO B 0000121 C D DOD FOR PUBLIC RELEASE Last Updated: 7/25/98
SURRY 02-Dec-9B DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 7/25/9B Positive IR-98-06 NRC Temporary Modifications (TMs) for Installing a mechanlcal jumper to a reactor 1 2 3 4 5 coolant pump oil system and an electric jumper to the reactor protection system were reviewed. Both TMs provided adequate safety evaluatlons and work A DODOO Instructions to Implement the TMs.
DODOO B
C D 01'21 D 6/13/9B Positive IR 9B-05 NRC The safely evaluatlon assessments of two modifications were thorough. The use of 1 2 3 4 5 mock-ups for training of personnel on modification Installation and system operation DODOO was an excellent practice.
A B 0001'2]'
C D D 18J 6/13/9B Positive IR 9B-05 NRC Modilicatlori procedures and guidelines provided an effective process for modification Implementation. Updated drawings were placed In the control room, the 1 2 3 4 5 document control system, the Technical Support Center, and the Simulator Control A DODOO Room before modified systems were placed In operation. The drawing change DODOO process Included a second verification lo ensure drawings were updated prior lo a B
modified system being declared operable.
C D 01'21 D 5/2/9B Positive IR 98-04 NRC Safety Evaluation 9B-0040 and Engineering Transmittal 9B-0058 adequately justified 1 2 3 4 5 a temporary modification lo plug a leaking reactor coolant pump thermowell.
00000 A
B D0018JD C D DOD 3/27/9B Negative ENG IR 98-201 LICENSEE A weakness In design control regarding the Intake canal level instrumentation 2 3 4 5 existed where Instrument uncertainties were not accounted for In the setpoints and Tech Spec and non-conservative use of water temperature in determining Instrument A DDDl2lD uncertainty. The Instrument safety limit Is 23' and the TS selpolnt is 23'6". The DODO.
calculated Instrument uncertainty was 6.49". Based on a licensee review of B
calibration data no Immediate operability concern existed.
C D DD 3/27/9B Negative ENG IR 98-201 NRC The licensee did not have a robust amount of electrical calculations to support the 1 2 3 4 5 AC and DC system design basis. The following documents were unavailable during DODOO the design Inspection: cable ampaclty calculation to verify cable sizing; calculations A
lo demonstrate that the penetration circuits were within design limits; evaluations to D001'2l D show the adequacy of breaker-to-breaker or breaker-to-fuse coordinations; analysis B
which justified the sizing of the DC penetrations; analysis which examined the fault C D 01'21 D currents lo the DC components and their distribution circuitry; and analysis which showed that the DC voltage at the component level was adequate to operate the devices.
FROM: 10/1/97 TO: B/31/98 Page 12 of 21 FOR PUBLIC RELEASE Last Updated: 7/25/9B
DATE TYPE(s) 3/27/98 URI 3/27/98 URI 3/27/98 Licensing FROM: 10/1/97 TO: 8/31/98 SEC.SFA ENG ENG ENG SOURCE(s)
ID'd IR 98-201/URI 98201-09, NRC IR 98-07 IR 98-201/URI 98201-08, NRC IR 98-07 IR 98-201/IFI 98201-01, IR 98-07 NRC Page 13 of 21.
SURRY ISSUE(s)
The design Inspection team Identified concerns with licensee's practice of connecting the DC busses with both batteries still tied to the busses. This alignment had not been analyzed nor was It reflected In the present version of the UFSAR. The determination of whether shutting the DC tie breaker with both batteries connected to the DC busses constitutes a potentlal Unreviewed Safely question.
Update From IR 98-07, 9/5/98:
In the response to the design Inspection report (98-201) the licensee committed to perform an evaluation to determine whether modifications were required lo comply with Safety Gulde 6. The licensee also committed to develop design change packages to support Implementation by the end of Unit 2 2000 RFO and by the end of Unit 1 2001 RFO. The Inspectors verified that this Item had been Incorporated In the licensee's commitment tracking system and CTS No. 4262 had been assigned for monitoring closure of all corrective actions. However, final disposition of this manner Is pending evaluation of the USO.
The design of the emergency diesel generator (EOG) battery transfer which provided the ability to transfer DC power between EDG 1, 2, and 3 was not supported by the existing design bases or the UFSAR. The design of the EDG battery transfer-scheme was weak In that It could potentially lead to common mode failure of the EDGs associated with one unit. The determination of whether the design of the EDG transfer switch constitutes a potential Unreviewed Safety question.
Update From IR 98-07, 9/5/98:
In the response lo the design Inspection report (98-201) the licensee stated the switch has been disabled by locking them in the 'open' position: A Request for Engineering Assistance (REA) has been submitted for preparation of a design change package to either physically remove or physically secure the throw over switches lo prevent their use In the future. Although these corrective actions were adequate to address the Issue, the URI will remain open pending review by the NRG to determine whether an unreviewed safety question was involved during past operation.
The design Inspection team had concerns with the use of containment over pressure to satisfy net positive suction head (NPSH) requirements for the Low Head Safely Injection (LHSI) and Recirc Spray (RS) pumps. Although team found that VEPCO had always credited the use of containment overpressure in determining the available NPSH for the LHSI pumps, based on the small amount ol NPSH margin available and the potential negative Impact of unqualified coatings in containment an IFI has been opened.
Update From IA 98-07, 9/5/98:
The NRG is reviewing Information on this Issue supplied by the licensee In response to the design inspection report (IR 98-201), in response to generic letter 97-04,
'Assurance of Sufficient Containment Heat Removal,' and in response lo a re.quest for additional information.
02-Dec-98 SMM CODES 1 2 3 4 5 A 0001'210 B 00000 c O DO 0 1 2 3 4 5 A 00000 B DODOO c D ODD 1 2 3 4.
A DDOIZJD B 00000 C 0 DOD FOR PUBLIC RELEASE Last Updated: 7/25/98
SURRY 02-Dec-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 3/27/98 Negative ENG IR 98-201/IFI 98201-20, NRC The design lnspecHon team Identified concerns with the effect on the net positive 1 2 3 4 5
IR 98-07 suction head (NPSH) for the Low Head Safety Injection (LHSI) and recirculation spray pumps because of unqualified coating on the reactor coolant pump (RCP)
A 0[810[8]0 motors. Licensee's preliminary review Indicated that the sump blockage from the 000[8]0 RCP. motor coatings would not result In operability concern for the LHSI and the RS B
pumps. Because there maybe additional unqualified coatings Inside containment C D DOD that could delamlnate and migrate to the containment sump screens, additional analysis Is necessary to ensure adequate NPSH for the LHSI and the Reclrc Spray (RS) pumps. IFI 50-280/98201-20 has been opened to track this Issue.
Update From IR 98-07, 9/5/98:
e In their response to the design Inspection report (IA 98-201 ), the licensee outlined their program for resolving the Issue of whether debris from unqualified coatings and other debris could clog the containment sump screens. The licensee presented a detailed program flow chart which depicted 22 specific activities arranged in three phases. The Inspectors concluded that Implementation of the coatings/debris program should resolve this Issue. IFI 98201-20 was closed In IR 98-07, Section E8.22 3/27/98 URI ENG IA 98-201/URI 98201-03, NRC A safety Injection (SI) system design deficiency could result In potential dead 1 2 3 4 5
IR 98-07 heading of the low head safety Injection (LHSI) pumps. The SI systems for both units were susceptible to the pump-to-pump Interaction, although only 2SI-P-1A was A DDDl.8l D found to be operating near dead head conditions.
00000 B
Update From IR 98-07, 9/5/98:
C D DOD The licensee In their response letter to the design Inspection (IR 98-201) committed to Implement a plant modification during the 1999 Refueling Outage (RFO) for Unit 2 and the 2000 RFO for Unit 1 In order to resolve this Issue. The licensee also committed to review their response to NRC IEB 88-04, 'POTENTIAL SAFETY-RELATED PUMP LOSS,' to ensure that there are no other Invalid assumptions regarding pumps that are susceptible* to potentially harmful Interactions. The review will be completed by October 1, 1998, and a revised response submitted ii necessary. The URI remains open pending evaluation of other potential design basis Issues.
3/27/98 Positive ENG IR 98-201 NRC The design Inspection team found that safety injection (SI) system, the recirculation 1 2 3 4 5 spray (RS) system, and their support-Interface systems were capable of performing D~DIZlD their design-basis safety functions. Adequate AC and DC power supply systems A
were available for both normal and accident conditions.
DODOO B
C D DOD 3/21/98 Positive SAQV IR 98-03 NRC The engineering sell-assessment program was comprehensive with good procedural 2 3 4 5 controls. Audit reviews revealed a good ability to perform audits, be sell-critical and 00000 address concerns with timely corrective actions. The environmental qualificalion A
area seal-assessment was well performed.
DODOO B
C D 000 FROM: 10/1/97 TO: 8/31/98 Page 14 of 21 FOR PUBLIC RELEASE Last Updated: 7/25/98
DATE TVPE(s)
SEC.SFA SOURCE(s)
ID'd 3/21/98 Positive IR 98-03 NRC 2/1/98 Positive IR 98-01 NRC 11/15/97 Positive tR 97*10 NRC 10/4/97 Positive IR 97*09 NRC 7/25/98 Negative IR 98-06 NRC 7/25/98 Positive IR-98-06 NRC 7/25/98 Positive IR-98-06 NRC FROM: 10/1/97 TO: 8/31/98 Page 15 of 21 SURRY ISSUE(s)
The llcensee's plans and procedures for the lnstallatlon of a freeze seal on a 12-inch safety Injection accumulator discharge line were thorough. Adequate contingencies were Implemented prior to the placement of the freeze seal.
Temporary Modification St-98-02 lo Install a temporary resistance temperature detector In the C main feedwaler line was adequately Implemented and the associated safety evaluation Justified Implementation of the temporary modification.
Letdown llne modifications were completed during the U2 refueling outage lo correct previous problems In which several socket weld failures occurred In the letdown system.
The Safely Evaluation addressing Service Waler expansion Joint operability was thorough and adequately Justified system qperabillty. The decision lo defer modification of the Unit 2 expansion Joints inside the containment for 2 weeks until an Refuellng Outage appeared appropriate.
The Inverter to the security unlnterruptlble power system has been out of service since February 1998. The removal from service was prompted by the fact that the Inverter continued to experience failures. The llcensee plans to Install a new inverter by the end of December 1998. In the event primary power ls lost lo security essentlal loads, compensatory measures have been incorporated in the Operating Procedure.
The personnel search equipment, and perimeter intrusion detection and assessment aids functioned In compliance with Physical Security Plan and implementing procedures. The llcensee employed appropriate compensatory measures when security equipment failed or its performance was Impaired.
Based on a review of 12 lnstrumentallon preventive maintenance inspection records for security-related equipment and observations of seven-day tests of the detection and assessment aids at the Independent Spent Fuel Storage Installation (ISFSI),
site perimeter intrusion detection equipment, and access search equipment, the inspector concluded that the licensee's security testing and maintenance program adequately ensured the reliability of the security equipment and devices.
02-Dec-98 SMM CODES 1 2 3 4 5 A DODOO B 0[8]0[8]0 c D D18JD 1 2 3 4 5 A DODOO B 0[8]0[8]-
C D 0[8]~
1 2 3 4 5 A DODOO B 018]0[8]0 c D DD l8J 1 2 3 4 5 A DODOO B 000[8][8]
c D ODD 1 2 3 4 5 A Dl8JDD~
B DODD.
c D DD D 1 2 3 4 5 A Dl8JDDD B DODOO c [8]
ODD 1 2 3 4 5 A 00000 B 00000 c l8J DOD FOR PUBLIC RELEASE Last Updated: 7/25/98
SURRY 02-Dec-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 7/25/98 Strength
. IR-98-06 NRC The llcensee's alarm stations, communications, and personnel and package access 1 2 3 4. 5 control to the protected and vital areas met the criteria of the Physlcal Security Plan and appropriate security procedures. The personnel access control program was.
A DODOO considered a strength In the security program..
DODOO B
C [8]
ODD 3/21/98 Positive SAQV IR 98-03 NRC The llcensee has complled 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 DDDDIEI sufficient.scope and depth lo ldenllly potentlal problems. Corrective actions were DODD' documented and tracked for completlon.
B C IE!
D D 3/21/98 Positive IR 98-03 NRC The llcensee has eflectlvely lmpiemented the radiological environmental monitoring 1 2 3 4 5 program. The sampllng, analytical and reporting program requirements were met and the sampllng equipment was being well maintained.
A DODOO B DODOO C [8]
ODD 3/21/98 Positive IR 98-03 NRC The llcensee 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 121 DD.D 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.
DODOO Maximum Individual radiation exposures were controlled to levels which were well A
within the licensee's administrative limits and the regulatory limits for occupational DODD.
does specified In 1 O CFR 20.120(a).
B C IE]
DD I
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 lo prevent recurring problems was found superior also (Security Area). The A 0000121 Inspectors determined that there were strengths in the controls for issues that could DODOO enhance plant operations or safety. No weaknesses were found that could degrade B
plant operations or safety.
C [8]
DD 121 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 avallable to fulfill response requirements met the number specified In the Physical Security Plan. One lull-lime member of the security A DODOO organization who has the authority to direct security activities did no! have duties DODOO
!hat conflicted with !he assignment to direct all activities during an Incident. The B
- licensee's response strategy was good and weapons employment was adequate to C [8]
DOD meet the design-basis threat.
FROM: 10/1/97 TO: 8/31/98 Page 16 of 21 FOR PUBLIC RELEASE Last Updated: 7/25/98
SURRY 02-Dec-98 DATE TYPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 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 lo the security program.
A DODOO 8 DODOO C 0 0 DD 1/30/98 Strength IR 98-02 NRC The Inspectors concluded through observation and Interviews of security personnel, 2 3 4 5 and document reviews that the security force was being trained In a superior manner and according lo lhe Training Qualification Plan and regulatory requirements. This A DODOO area of the security program was considered a strength by the Inspectors.
- 0000, 8
C 0 DD 1/30/98 Positive IA 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 DDl'2lD D 8 DODOO C ra ODD 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 1 O CFR 73.1 (a).
A DODOO 8 00000 C 0 DOD 1/30/98 Negative IR 98-02 NRC One vulnerability In the protected area access control area and two vulnerabilities in 2 3 4 5 the protected Intrusion detection system were found.
A D0D0D 8 DODD.
C 0 DD 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 00000 8 00000 C ra DOD 12/27/97 DEV IR 97-12 &97-09, DEV 50-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 !allure to meet the requirements of Appendix R for circuit breaker coordination, was Issued as a deviation from a commitment of the UFSAR. This A 00000 Item was previously Identified In IR 97-09 as EEi 50-280,281/97009-04 (10/4/97).
DODOO 8
C 0 DOD FROM: 10/1/97 TO: 8/31/98 Page 17 of 21 FOR PUBLIC RELEASE Last Updated: 7/25/98
SURRY 02-Dec-98 DATE TYPE(s)
SEC. SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 12127/97 VIO IR 97-12 & 97-09, EA 97-NRC Following an enforcement conference a SL IV Vlolallon was Issued for failure lo 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 This flem was previously Identified In IR 97-09 as EEi 50-280, 281/97009-06 A DODD l'2l (10/4/97).
8 DODD l'2l C 181 ODD 12127/97 Positive IR 97-12 NRC The licensee had Implemented and maintained a program for obtaining and 1 2 3 4 5 analyzlng samples of reactor coolant ani:I containment atmosphere under accident DODD.
conditions In accordance with TS requirements and UFSAR commllmenls.
A 8 018100 C 181 ODD 12127/97 Positive IR 97-12 NRC The licensee's waler chemistry control program for monitoring primary and 1 2 3 4 5 secondary water quallly had been Implemented In accordance with Technical Speclflcallon requirements and Industry guldellnes for pressurized waler reactor A DODOO waler chemistry.
8 DODOO C 181 DOD 12127/97 Strength IR 97-12 NRC The llcensee's program for transportation of radioactive materials had been 1 2 3 4 5 eflecllvely Implemented pursuant to Department of Transportation and NRC regulallons. Enhanced procedures for shipping radioactive malerlals were a A DODOO strength.
8 DODOO C 181 DOD 12127/97 Positive IR 97-12 NRC The lolal number of temporary modifications (TMs), four on Uni! 1 and none on Unit 1 2 3 4 5 2, Indicated a willingness lo correct problems in an expeditious manner. The TMs had safely evaluallons which were completed prior lo lnslallallon.
A DODOO B 0000p C D DD 12/27/97 VIO IR 97-12 & 97-09, EA 97-NRC Following an enforcement conference a Severity Level Ill Violation was Issued for 1 2 3 4 5 474 01023, EEi 97009-05
!he failure of !he licensee to correct the Appendix R discrepancies in a timely manner. This item was previously Identified in IR 97-09 as EEi 50-280, 281/97007-A 00000 05 (10/4/97).
DODOO 8
C 0 DD 181 12/27/97 VIO IA 97-12, & 97-09, EA LICENSEE Following an enforcement conference a Severity Level Ill violation was Issued for 1 2 3 4 5 97-474 01013,LER the Inadequate fire protection features which failed lo meet lhe requirements of 280/97007 10CFR50 Appendix R. The control room complex and safely related vital electrical A 00000 panels were not fully protected. One !rain of systems necessary lo achieve and maintain ho! shutdown condilion from either control room or emergency control DODOO stations (remote shutdown panels) would nol be free from fire damage. EA 97-474 B
01013. This Item was previously Identified in IR 97-04 as EEi 280,281/97009-03 C
(10/4/97).
181 DOD FROM: 10/1/97 TO: 8/31/98 Page 18 of 21 FOR PUBLIC RELEASE Last Updated: 7/25/98
SURRY 02-Dec-98 DATE TVPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 11/15/97 Posilive IR 97-10 NRC The review of three quarterly Security Event Logs verified that the licensee was 1 2 3 4 5 approprlately analyzlng, tracking, resolvlng and documenting safeguards events.
A DODOO B DDDDr2l C
[8J DD r2l 11/15/97 Positive IA 97-1.0 NRC Intrusion detection systems and assessment aids were functional, well maintained, 1 2 3 4 5 effective for both covert and overt penetration attempts and met licensee commitments.
A 00000 B DODO-,
C t8l D D 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 lmplementlng Procedures were complied with for alarm stations and communications.
A DODOO B D r2l DD.D C [8J DOD 11/15/97 Positive IR 97-10 NRC The evaluation of Iha 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 [8J ODD 11/15/97 Positive IA 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 [8J ooe 11/15/97 Positive IR 97-10 NRC Personnel entering the Radiological Controlled Area :,vere adequately briefed on 1 2 3 4 5 radiological hazards and protective measures.
A DODOO B DODOO C 0 ODD 11/15/97 Positive IR 97-10 NRC During the Unit 2 refueling outage, the licensee was properly monitoring and 1 2 3 4 5 controlling personnel radiation exposure and posting area radiological conditions in accordance with 10 CFR Part 20.
A DODOO B DODOO C 0 DOD FROM: 10/1/97 TO: 8/31/98 Page 19 of 21 FOR PUBLIC RELEASE Last Updated: 7/25/98
SURRY 02-Dec-98 DATE TVPE(s)
SEC.SFA SOURCE(s)
ID'd ISSUE(s)
SMM CODES 10/4/97 NCV IA 97-09, NCV 280, LICENSEE A Non-Cited Vlolatlon was ldentlffed concerning the failure to perform lire watch 1 2 3 4 5.
281/97009-08 tours within the specified one hour time frame.
A DODOO B D018JOO C 18)
DOD 10/4/97 Positive IA 97-09 NRC The llcensee took positive action to enhance the preventive maintenance being 1 2 3 4 5 performed on the storage of spare safety related electric motors and rotating DODOO mechanical components.
A B 018)00, C D DD 10/4/97 Negative IA 97*09 NRC A Justlffcatlon for changes to the Radwaste Faclllty building structure, equipment and 1 2 3 4 5 faclllty process was not being maintained.
DDDl'2sl0 A
B DODOO C 18) tJ DD 10/4/97 Positive IA 97-09 NRC Excellent housekeeping was provided for the Radwasle Facllliy with good 1 2 3 4 5 lmplementatlon of the station's lire prevention procedures and maintenance of the 018)000 lire protection equipment.
A B DODOO C 18)
DOD e
FROM: 10/1/97 TO: 8/31/98 Page 20 of 21 FOR PUBLIC RELEASE Last Updated: 7/25/98
DATE TYPE(s)
SEC.SFA SOURCE(s)
SMM Template Codes:
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 SURRY ID'd ISSUE(s)
SALP Functional Areas:
ENG MAINT OPS PLTSU SAOV ENGINEERING MAINTENANCE OPERATIONS PLANT SUPPORT SAFETY ASSESSMENT & av 02-Dec-98 SMM CODES ID Code:
~~~NSEE-1~~~NSEE SELF SELF-REVEALED EEis ere 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 predeclslonal enforcement conference.
UF.lls 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 conclusions are made.
FROM: 10/1/97 TO: B/31/98 Page 21 of 21.
FOR PUBLIC RELEASE Last Updated: 7/25/98