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| | U.S. NUCLEAR REGULATORY COMMISSION REGION I . |
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| | Report N /88-15 Docket N License No. NPF-57 Licensee: Public Service Electric & Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038 Facility Name: Hope Creek-Nuclear Generating Station Inspection At: -Hancock Bridge, New Jersey Inspection Conducted: Apri.1 18-22, 1988 |
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| | Inspector: du bDN |
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| | Henri F. van Kessel, Reactor Engineer date Approved by: h, K , k dw G[4!87 Dr. P. K. Eapen, Chidf Special Test da t'e Programs Section, EB, DRS Inspection Summary: Inspection on April 18-22, 1988 (Inspection Number 50-354/88-15) |
| | Areas Inspected: Routine Unannounced Inspection of the startup test program following the first refueling, including the review of startup test procedures and test results evaluation, an independent calculation of the core thermal power balance, and the review of activities in the QA/QC interface with the afore said startup test program. |
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| | M ection Results: No violations or deviations were identifie See Attachment C for acronyms used in this report. |
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| | 8806160164 880608 PDR ADOCK 05000354 o DCD L |
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| | J 1.0 Persons Contacted Public Service Electric and Gas (PSE&G)- |
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| | *R. W. Beckwith, Station Licensing Engineer it T. Brown, Nuclear Technical Engineer |
| | *J. DeFebo, Quality Assurance Engineer J..M. Haun, Senior Nuclear Supervisor |
| | *S. L. Funsten, Maintenance Controls Engineer 1 |
| | *R. T. Griffith, Sr. , Principal QA Engineer ; |
| | *S. LaBruna, General Manager Hope Creek Operations |
| | * LaVecchia, Princ'ipal QA Engineer |
| | *J. E. Metro, Reactor Staff Engineer |
| | *J. Nichols, Technical Manager HC0 > |
| | J. O'Brien,-Reactor Engineer i R. J. Schmidt, Technical Engineer C. Vondra, Operations Manager U.S. Nuclear Regulatory Commission |
| | * W. Meyer, Senior Resident Inspector |
| | * Denotes those present during exit meeting held on April 22, 1988 2.0 Startup Test Program (72700) |
| | 2.1 Startup-Test Procedure Review The startup test procedures as listed in Attachment A were reviewed |
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| | * Management review and approval |
| | * Procedure format |
| | * Clarity of stated objectives |
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| | * Prerequisites |
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| | * Environmental conditions , |
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| | * Acceptance criteria and their sources |
| | * References l * Initial conditions , |
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| | * Attainment of test objectives |
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| | * Test performance documentation and verification a Degree of detail for test instructions |
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| | Restoration of system to normal after testing |
| | * Identification of test personnel |
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| | Evaluation of test data |
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| | Independent verification of critical steps or parameters |
| | * Quality control and assurance involvement Findings No noncompliances were identified by the inspector within the scope of this inspectio .2 Test Result Evaluation The test procedures listed in Attachment A (with asterisk) were reviewed to verify that adequate testing was accomplished in order to satisfy regulatory guidance and licensee commitments and to ascertain whether uniform criteria were being applied for evaluating completed preoperational tests in order to assure their technical and administrative adequac The test results were reviewed for: |
| | * Test changes |
| | * Test exceptions |
| | * Test deficiencies |
| | * Acceptance criteria |
| | * Performance verification |
| | * Recording of conduct of test |
| | * QC inspection records |
| | * System restoration to normal |
| | * Independent verification of critical steps or parameters |
| | * Identification of test personnel |
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| | Verification that the test results have been approved |
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| | The following observations were made for the procedures within the scope of this inspection: |
| | Core Power Distribution Limits: RE-ST.ZZ-001 |
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| | (1) The plant was operated within the licensed power distribution limits. A P-1, the periodic NSS Core Performance Log, had been - |
| | printed out from the process computer every hour. In all of these cases, the MFLCPR, MFLPD, and MAPRAT were smaller than unity indi-cating that the corresponding values in the Technical Specification for the Critical Power Ratio, the Linear Heat Generation Rate and the ' |
| | Maximum Average Planar Linear Heat Generation Rate, respectively, had not been exceede (2) The means used to confirm operation within the limits mentioned under (1) above consisted of the standard General Electric Company (GE) computer software as supplied for BWRs 4/5 and, as such, had been reviewed by NRR some time ag (3) The licensee is preparing a backup software program. A 10 CFR 50.59' type evaluation will be made for this backup program upon completio (4) An 00-1 program, "Whole Core LPRM Calibration and Base Distributions," had been run at the 75% and the 100% power plateau. |
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| | 1 The TIP machine normalization factors were obtained by traversing each probe, one at a time, through the common calibration tub There are 5 TIP machines and 43 channels. A flux chart was produced for each channel at 100% power on April 17, 1988. The normalization of the TIP readings is done by the OD-1 software program. These data were used for APRM calibration. When the LPRM goes out of calibration, Base Crit Code will be printed on the P-1 printou (5) The APRM set points did not have to be adjusted for CMPF peaking factor at core max fraction of limiting power density greater than |
| | . design value because they could stay within the time limit (6 hrs.) |
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| | by changing control rod patter (6) APRM gain adjustments were made at 98.8% power on April ; |
| | 17, 1988. An 00-3, "Core Thermal Power and APRM Calibration," was |
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| | made to provide new Gain Adjustment Factors (GAFs). This was done |
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| | at the 100, 89, 63, and 24 percent power levels. |
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| | i (7) TIP traces were made after adjustments to observe the impact on CMPF values at the 75% and 100% power plateau In each case proper APRM calibration was obtained as indicated by the absence of Base r Crit Codes on the P-1 printou ! |
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| | ,m,.,-a--o,-wm, m-,,,mvg,-------,---.--r-- - - - - --- r-n---,- |
| | - - - -- ,--,---m, y .,n --a .w-.,---,-, w- , . , - - - - ,. , , , , -, e,v.,,em,--.--w -,7, |
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| | (8) Although the process computer has not malfunctioned to date, a f |
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| | GE document (NE00 25443) can be used to ascertain that the plant is |
| | ' operating within licensed limits when the process computer is dow The GE document (NEDO-25443)* was reviewed by NRR. The licensee is preparing an independent software program which car be used on > |
| | another available computer. This program will be essentially the |
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| | same as the GE plant monitoring program but can be run on another compute t |
| | *NE00 25443, "P-1 Backup (PIB), a manual method for core performance .i evaluation and LPRM calibration," by G. R. Parkos, November 1981, General Electri (9) An 00-1 was made just before LPRM gain changes at 100*4 powe Gain adjustments were made. A new 00-1 was produced after these gain adjustments'. All final GAF values were within the Tech. Spec. |
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| | LPRM Calibration: RE-ST.SE-003 |
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| | (1) LPRM calibration had been performed at the different power h levels in accordance with the procerkr (2) APRMs had been recalibrated following LPRM gain adjustments in accordance with step 5.1.16 in the procedure. (See, for example, * |
| | APRM calibration calculation / data sheet, dated 4-17-88, attachment 1 i |
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| | of RE-ST.SE-002), t (3) The identification of LPRM calibrations is tracked by the data , |
| | . on Attachment 1 of the procedur These data are used to detect loss of sensitivity of the sensors. A program is being written in , |
| | ; the Fuel Group to do this on the computer. At present, this work is done manually. |
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| | i (4) LPRM readings were obtained at core conditions existing prior to r |
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| | i amslifier gain adjustments. (See "as foJnd" values on Attachment |
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| | 1). The performance of a full core flux map, by means of the TIP . |
| | syst en., was obtained prior to making amplifier gain changes as can ; |
| | be seen in the 00-1 edit. A P-1 calculation was performed after the ; |
| | full core flux map for the calibrated APRM readings (See P-1 dated 4-17-88,0256). |
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| | 1 (5) Calculations were made for the new input calibration currents to |
| | : be applied to the respective LPRM amplifiers (See Attachment 1). |
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| | !- These calculated input currents were applied to make the proper LPRM ' |
| | calibration adjustment , |
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| | (6) Each APRM channel was by passed during its espective LPRM group - |
| | adjustments in accordance with paragraphs 5,1.7 Ond 5.1.8 of l IC-CC.SE-029, "channel calibration nuclear instrut'entation system - ' |
| | l LPRM gain calibration." ; |
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| | (7) Reviews were made of the Full Core Flux Map and a P-1 af ter the LPRM calibration adjustments. All of the GAFs were verified to be within the established limit (8) An 0D-3 was made following the LPRM calibrations to assure that APRM settings were within Tech. Spec. Limits (see for example the 00-3 made on April 17, 1988) |
| | APRM Calibration: RE-ST.SE-002 (1) The APRM system was properly calibrated to the Core Thermal Power as can be seen, for instance, in Attachment 1 of the procedure, dated April 17, 198 (2) As a prerequisite (2.3 paragraph), the core was maintained at steady state operating conditions at the desired power level and recirculation flow rate during the calibratio (3) Only one APRM channel, per RPS bus, was bypassed at a tim Since there is only one switch per RPS bus, there is no physical possibility for this to happe (4) The APRMs were adjusted to read calculated % of rated power ar (videnced, for example, by the calculation of Attachment 1 of the procedure, dated April 21, 1988. The same reference also shows the |
| | "as left" APRM readings versus !; thermal powe Core Thermal Power Evaluation: RE-RA.ZZ-001 (1) The power range nuclear instruments were properly adjusted to agree with the heat balance results as evidenced by Attachment 1 of the procedure for the 98.7?; power level during startu (2) An independent hand calculation was made by the inspector using the licensee's procedure (RE-RA.ZZ-001). The results are discussed in this report under Section (3) The results of this procedure were reviewed and approved by the licensee's designees in accordance with Administrative Procedure AP.12. Approvals were made by the Senior Reactor Superviso Determination of Reactor Shutdown Margin (SDM): RE-ST.ZZ-007 (1) Changes to SDM, due to inoperative control rods, were not experienced during this startu (2) The SDM af ter startup was in agreement with the Technical Specifications as evidenced by the completed attachments of this procedure, dated April 10, 1988, soon after criticalit . . |
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| | (3) The reactor went critical on 2152 notche The demonstrated SDM=1.983% Ak/k as shown in Attachment 3 of the procedur The SDM is required to be greater than .769% ak/ (4) The licensee reviewed the data supplied by the vendor (GE) and amongst others used it in their own SOM determination. The data were presented by GE in their Document No. 23A5879, rev. O, "Hope Creek Cycle 2, Cycle Management Report", by H. H. Yeager. , dated March 25, 1988. PSE&Gs fuel department produced, independently, a document by the same title i .e., NFU-0092, dated March 29, 1988. The latter document, however, does not contain any reference to the GE-document, raising the impression that the GE data were not used in the preparation of same or for comparison of results. This item was discussed with the representatives of the nuclear fuel departmen They concurred that the reference should be made because the compari-son of the data of the two reports was made and, in the case of the SDM, the pSE&G data were more conservative. The GE document will be added to the reference listing of the pSE&G repor (5) No stuck out rod problems were experienced and, therefore, no special SDM determination had to be mad . 0A/QC Interface The participation of Station QA in test witnessing of the post refueling startup tests was evaluated by the inspector. The Station QA Surveillance Reports as listed in Attachment B were reviewe The inspector observed that none of the QA Surveillance reports contained any unsatisfactory finding. The check lists appeared to cover all of the important acceptance criteria and none of these criteria were violated during the test Station QA Surveillance Report No. 88-246, however, found that testing was performed while the system (in test) was legitimately being worked on under work order 880303065 and had relay E21-K14B missing (in plastic bag) |
| | from the system. This finding was not identified as an unsatisfactory item. The inspector discussed this item with the QA personnel responsible for the surveillance. The QA personnel provided the following statement |
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| | e an explanation: |
| | l "There was a lack of communications between the supervisors in the I&C Department, which permitted IC-FT-BB-004 to be run; however, the Operations Department had declared this system INOPERABLE prior to performance of IC-FT-BB-004. Since we were in a refuel outage, this system was not required to be operable in Mode 5 with cavity flooded. |
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| | [ When a. system is not required for a particular operating condision or is in an outage declared IN0 PERATIVE by operations, it is a normal , |
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| | acceptable practice for multiple Station departments to perform several ' |
| | maintenance functions in parallel. Upon completion of the maintenance, a-channel calibration / functional--test is performed prior to declaring the * |
| | -system operable." |
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| | In the case noted above, the I&C miscommunication resulted in an attempt to run the Functional Test prior to completion of maintenance wor The requirements of the Station retest program and the fact that the system had previously been declared inoperable provide the necessary insurance that return to operable status would bt achieved." |
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| | The inspector found the above explanation to be adequat No discrepancies or unacceptable conditions, other than the one mentioned |
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| | above, were noted in the review of the QA Surveillance report : |
| | ' Independent Effort The inspector, independently, calculated the thermal power balance for the |
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| | core in accordance with instructions contained in procedure RE-RA.ZZ-001 and for the data of April 16, 198 Discrepancies were found fo.- |
| | formulae line items [6] and [7] where the formulae include a factor of 32 i |
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| | to be subtracted from the mV reading in each case. This factor no longer |
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| | exists because the transmitter range was changed to (0-166mV). The i results for the April 16 data were not affected because an alternate method was used to calculate the pertinent value Another discrepancy involved line items [4] and [5] on page 2 of |
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| | Attachment The mV values versus temperature on the table of page S ' |
| | were misread causing the calculated temperatures to be higher for the correct readings. The impact of the latter discrepancy was that the j calculated core thermal power wcs 2 Kdth, higher than the actual. |
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| | l The licensee issued rev. 3 of procedure RE-RA.ZZ-001 containing the |
| | ; corrections to lines A203 and A204 for the new transmitter range |
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| | (0-160mV). Plant Tours , |
| | . The inspector made tours of the plant including the control room, the control building, turbine building, and the reactor building to observe |
| | ! housekeeping, testing activities and cleanlines . |
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| | ; The inspector, noted that APRM A and B are in one compartment of panel l 10-C608. Both channels have to be bypassed at the same time to avoid the , |
| | ;' possibility of inadvertent reactor scrams. A warning to this effect is posted on the cabinet door. This design feature is common for BWR 4/5 designs and has been reviewed by the NRC in the past. |
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| | 6. Exit Interview At the conclusion of the site inspection, on March 22, 1988, an exit interview was conducted 'vith the licensee's senior site representatives (denoted in Section 1). The findings were identified and previous inspection items were discusse i At no time during this inspection was written material provided to the licensee by the inspector. Based on the NRC Region I review of this report and discussions held with licensee representatives during this inspection, it was determined that this report does not contain information subject 10 CFR 2.790 restriction _ _ _ - - - - - - - - - _ _ _ _ _ _ |
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| | Attachment A Procedure Review Proc. N Title Rev. No. Approval Date RE-FR.ZZ-008fQ) Verification of Fuel Location 2 02-18-88 RE-RA.BB-001(Q) Recirculation Flow Determination 1 05-12-86 RE-RA.BB-002(Q) Core Flow Determination 1 09-23-86 |
| | *RE-RA.ZZ-001(Q) Core Thermal Power Evaluation 1 09-02-86 RE-RA.ZZ-005(Q) Reactor Period Measurement 1 03-10-86 RE-RA.ZZ-005(Q) Reactor Period Measurement 1 03-10-86 RE-SO.RJ-003(Q) NSS Computer Reinitialization 1 11-21-86 and 00-15 program operation RE-SO.SE-001(Q) Traversing Incore Probe System 5 10-07-87 Operation |
| | *RE-ST.ZZ-001(Q) Core Thermal Limits Evaluation 2 07-30-87 Process Computer Method RE-ST.BF-001(Q) Control Rod Drive Scram Time 1 07-16-86 Determination RE-ST.SE-001(Q) APRM Setpoint Surveillance 5 09-23-87 |
| | *RE-ST.SE-002(Q) APRM Calibration Surveillance 3 11-26-86 |
| | *RE-ST.SE-003(Q) LPRM Calibration 5 01-08-87 RE-ST.ZZ-005(Q) Reactivity Anamoly Check 2 12-15-86 |
| | *RE-ST.ZZ-007(Q) Shutdown Margin Demonstration 4 06-25-86 IC-CC.SE-029(Q) Channel Calibration Nuclear 6 09-10-87 Instrumentation System LPRM Gain Calibration |
| | "Used in test result evaluatio ', . . ' ', |
| | Attachment B Review of QA Surveillance Reports Q/A Sur Completion Report No. , Surveillance Activity Date 88-276 Verification of Fuel Location 3-20-88 88-275 I&C Channel Calibration 3-20-88 Redundant Reactivity Control System, Div 1 Channel B, ATWS Recire. Pump Trip 88-273 Reactor Engineering / Core and Spent Fuel 3-20-88 Pool Mapping 88-218 TS Surveillance of LPRMs 3-15-88 (TS 4.7.6.1 and 4.7.6.2c) |
| | 88-223 Control Rod Removal and Installation 3-04-88 88-24/ Functional Test Nuclear Instr. System 3-13-88 Channel A Source Range Monitor TS Surveillances 88-246 Functional Test Nuclear Boiler DIV 2 3-12-88 Channel B21-N691F Reactor Vessel level (trips 1, 2, 8 - CS, RHR, ADS, RCIC) |
| | 88-264 Time Response Test for Transmitter 3-15-88 1 BBPT-N0780-B21 88-270 Time Res;ense Test for PIdsh- 3-17-88 686D-821 88-093 Fuel Pandling, Off Load of Core 2-25-88 88-242 Fuel Movement, Shuffle and Reload 3-18-88 i ._ |
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| | Attachment C Acronyms |
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| | APRM Average Power Range Monitor BASE CRIT CODE LPRM strings which may require new data accumulated by TIP System (shown on P-1 printout) |
| | BWR Boiling Water Reactor CMPF Peaking factor at core MFLPD |
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| | CPR Critical Power Ratio GAF Gain Adjustment Factor |
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| | LPRM Local Power Range Monitor MAPRAT Maximum Fraction of Limiting Average Planar Linear Heat Generation Rate MFLCPR or Maximum Fraction of Limiting MFLCP Critical Power Ratio MFLPD Maximum Fraction of Limiting Power Density |
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| | NSS Nuclear Steam System 00 On Demand (Programmatic Output of PMS) |
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| | PMS Performance Monitoring System |
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| | RPS Reactor Protection System |
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| | SDM Shut Down Margin |
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| | TIP Traversing Incore Probe ak/k Reactivity, fractional change in neutron population per neutron generatio * |
| | Also defined in NUREG-0544, rev. 2. |
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Category:INSPECTION REPORT
MONTHYEARIR 05000354/19990051999-10-0101 October 1999 Insp Rept 50-354/99-05 on 990711-0829.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs.Major Areas Inspected:Mitigating Sys,Barrier Integrity & Performance Indicator Verification IR 05000354/19990041999-08-11011 August 1999 Insp Rept 50-354/99-04 on 990530-0711.No Violations Noted. Major Areas inspected:cornerstone-mitigating Sys,Pi Verification IR 05000354/19990031999-06-21021 June 1999 Insp Rept 50-354/99-03 on 990419-0529.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19990021999-05-14014 May 1999 Insp Rept 50-354/99-02 on 990308-0418.Non-cited Violation Identified.Major Areas Inspected:Operations,Maint & Plant Support IR 05000354/19990011999-04-19019 April 1999 Insp Rept 50-354/99-01 on 990124-0307.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000354/19980111998-12-22022 December 1998 Insp Rept 50-354/98-11 on 981101-1212.No Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support IR 05000354/19980101998-11-23023 November 1998 Insp Rept 50-354/98-10 on 980920-1031.Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000354/19980081998-10-0909 October 1998 Insp Rept 50-354/98-08 on 980809-1019.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19980091998-10-0202 October 1998 Insp Rept 50-354/98-09 on 980817-26 & 0908.No Violations Noted.Major Areas Inspected:Maint & Engineering IR 05000354/19980071998-08-25025 August 1998 Insp Rept 50-354/98-07 on 980628-0808.Violation Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19980061998-07-21021 July 1998 Insp Rept 50-354/98-06 on 980517-0627.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000272/19982021998-07-0909 July 1998 Partially Deleted Insp Repts 50-272/98-202,50-311/98-202 & 50-354/98-202 on 980420-23.No Violations Noted.Major Areas Inspected:Conduct of Security & Safeguards Activities IR 05000354/19980801998-06-10010 June 1998 Insp Rept 50-354/98-80 on 980223-0319 & 0427-30.Violations Noted.Major Areas Inspected:Maint & Engineering IR 05000354/19980051998-06-0404 June 1998 Insp Rept 50-354/98-05 on 980405-0516.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19980021998-04-23023 April 1998 Insp Rept 50-354/98-02 on 980222-0404.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint,Plant Support & Effectiveness of Fire Protection Program IR 05000354/19980011998-03-16016 March 1998 Insp Rept 50-354/98-01 on 980104-0221.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20199L5321998-02-0303 February 1998 Insp Rept 50-354/97-10 on 971116-980103.Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20197D2111997-12-10010 December 1997 Insp Rept 50-354/97-09 on 971005-1115.Apparent Violation Being Considered for Escalated Ea.Major Areas Inspected: Licensee Operations,Engineering,Maint,Plant Support & Site Security Programs ML20199D3431997-11-13013 November 1997 Insp Rept 50-354/97-07 on 970824-1004.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support IR 05000354/19970051997-09-15015 September 1997 Insp Rept 50-354/97-05 on 970713-0823.Noncited Violations Identified.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000354/19970061997-09-0404 September 1997 Insp Rept 50-354/97-06 on 961112-970529.Violations Noted. Major Areas Inspected:Engineering ML20210N9131997-08-11011 August 1997 Insp Rept 50-354/97-04 on 970601-0712.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20140J3871997-06-12012 June 1997 Insp Rept 50-354/97-03 on 970429-0531.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20148D2301997-05-23023 May 1997 Insp Rept 50-354/97-02 on 970318-0428.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support.Routine Insp of Physical Protection & Security Program Also Conducted ML20137W7811997-04-14014 April 1997 Insp Rept 50-354/97-01 on 970202-0317.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint, & Plant Support ML20135A3901997-02-21021 February 1997 Insp Rept 50-354/96-11 on 961222-970201.Violation Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000354/19960101997-01-27027 January 1997 Insp Rept 50-354/96-10 on 961110-1221.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering,Plant Support & Security Program Plan IR 05000354/19960091996-12-0505 December 1996 Insp Rept 50-354/96-09 on 960922-1109.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20129D0891996-10-18018 October 1996 Insp Rept 50-354/96-07 on 960804-0921.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19950151996-02-14014 February 1996 Insp Rept 50-354/95-15 on 950905-1109.No Violations Noted. Major Areas inspected:safety-related Reactor Vessel Water Level Mod,Corrective Actons for Digital Feedwater Control Sys & RCIC Jockey Pump Corrective Action Process ML20084L7691995-05-30030 May 1995 Insp Rept 50-354/95-05 on 950406-21.No Violations Noted. Major Areas Inspected:Licensee Actions & Evaluations Associated W/Unplanned Release of Radioactive Matl from Hope Creek South Plant Vent That Occurred on 950405 IR 05000354/19930231993-12-15015 December 1993 Insp Rept 50-354/93-23 on 931004-1103.No Violations Noted. Major Areas Inspected:Review Licensee Corrective Actions of Previously Identified Edsfi Findings IR 05000354/19920191992-12-15015 December 1992 Insp Rept 50-354/92-19 on 921104-10.No Violations Noted. Major Areas Inspected:Licensees C/A for Mechanical Snubbers That Failed Functional Test & to Verify That Failed Snubbers Have Been Replaced or Restored to as-designed Condition IR 05000354/19910131991-06-21021 June 1991 Insp Rept 50-354/91-13 on 910520-24.No Violations Noted. Major Areas Inspected:Review of Several Open Items Remaining from Maint Team Insp 50-354/89-80 & Surveillance Test & Implementation IR 05000354/19900131990-07-26026 July 1990 Insp Rept 50-354/90-13 on 900618-22.No Violations Noted. Major Areas Inspected:Svc Water Intake Structure & Licensee Actions on Previous Insp Findings Re Svc Water Pipe Leak Examined IR 05000354/19900151990-07-19019 July 1990 Insp Rept 50-354/90-15 on 900625-29.No Violations Noted. Major Areas Inspected:Organization & Staffing,Training & Qualifications of Personnel,Procedures,Audits & Assessments, External & Internal Exposure Controls ML20246C4001989-08-15015 August 1989 Partially Deleted Insp Repts 50-272/89-19,50-311/89-17 & 50-354/89-15 on 890710-14 (Ref 10CFR73.21).Major Areas Inspected:Followup on Actions Taken in Response to Regulatory Effectiveness Review on 890410-14 IR 05000354/19890131989-07-20020 July 1989 Insp Rept 50-354/89-13 on 890626-30.No Violations Noted. Major Areas Inspected:Licensee Compliance to 10CFR50.62 ATWS Rule Pertaining to Alternate Rod Injection Sys IR 05000354/19890111989-07-10010 July 1989 Safety Insp Rept 50-354/89-11 on 890501-0619.No Violations Noted.Major Areas Inspected:Operations,Radiological Controls,Maint & Surveillance Testing,Emergency Preparedness,Security & LER & Open Item Followup IR 05000354/19890091989-05-10010 May 1989 Safety Insp Rept 50-354/89-09 on 890314-0430.No Violations Noted.Major Areas Inspected:Operations,Radiological Controls,Maint & Surveillance Testing,Emergency Preparedness,Security & LER Followup ML20247B6651989-05-0909 May 1989 Mgt Meeting Rept on 890307 & 0413.Major Areas Discussed: Status of Plant,Training & Safety Programs & Self Assessment Programs IR 05000354/19890021989-03-31031 March 1989 Safety Insp Rept 50-354/89-02 on 890124-0313.Violation Noted.Major Areas Inspected:Operations,Radiological Controls Maint & Surveillance Testing,Emergency Preparedness,Security & Engineering/Technical Support IR 05000354/19890061989-03-29029 March 1989 Insp Rept 50-354/89-06 on 890227-0303.No Violations Noted. Major Areas Inspected:Adequacy & Implementation of Licensees Fire Protection Program,Combustible Matl Control, Housekeeping Conditons & Fire Brigade Training IR 05000354/19890051989-03-23023 March 1989 Insp Rept 50-354/89-05 on 890227-0303.No Violations Noted. Major Areas Inspected:Adequacy,Implementation & Effectiveness of Radiological Controls Program During mid-cycle Outage,Organization,Training & Staffing IR 05000354/19890031989-02-28028 February 1989 Insp Rept 50-354/89-03 on 890206-10.No Violations Noted. Major Areas Inspected:Licensee Inservice Insp Activities to Ascertain That Inservice Insp Activities Conducted Per ASME Code & Regulatory Requirements IR 05000354/19880231988-11-0101 November 1988 Safety Insp Rept 50-354/88-23 on 880830-1011.Major Areas Inspected:Operations,Radiological Controls,Surveillance Testing,Maint,Emergency Preparedness,Security,Ler & Engineering/Technical Support IR 05000354/19880201988-10-24024 October 1988 IR 50-354/88-20 on 880906-16.No Violations Noted. Major Areas Inspected:Verification That Emergency Operating Procedures Technically Adequate IR 05000354/19880221988-09-15015 September 1988 Insp Rept 50-354/88-22 on 880712-0829.Violation Noted.Major Areas Inspected:Operations,Radiological Controls, Surveillance Testing,Maint,Emergency Preparedness,Security, Engineering/Technical Support & LER & Open Item Followup IR 05000298/19880191988-08-0303 August 1988 Insp Rept 50-298/88-19 on 880613-17.No Violations or Deviations Noted.Major Areas Inspected:Nonlicensed Staff Training,Qa Annual Review (Procurement,Receipt Insp & Audits) & Licensee Actions on Previous Concerns IR 05000354/19880181988-07-26026 July 1988 Insp Rept 50-354/88-18 on 880601-0711.No Violations Noted. Major Areas Inspected:Operational Safety Verification, Surveillance Testing,Maint Activities,Ler Followup & Assurance of Quality 1999-08-11
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000354/19990051999-10-0101 October 1999 Insp Rept 50-354/99-05 on 990711-0829.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs.Major Areas Inspected:Mitigating Sys,Barrier Integrity & Performance Indicator Verification IR 05000354/19990041999-08-11011 August 1999 Insp Rept 50-354/99-04 on 990530-0711.No Violations Noted. Major Areas inspected:cornerstone-mitigating Sys,Pi Verification IR 05000354/19990031999-06-21021 June 1999 Insp Rept 50-354/99-03 on 990419-0529.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19990021999-05-14014 May 1999 Insp Rept 50-354/99-02 on 990308-0418.Non-cited Violation Identified.Major Areas Inspected:Operations,Maint & Plant Support IR 05000354/19990011999-04-19019 April 1999 Insp Rept 50-354/99-01 on 990124-0307.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000354/19980111998-12-22022 December 1998 Insp Rept 50-354/98-11 on 981101-1212.No Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support IR 05000354/19980101998-11-23023 November 1998 Insp Rept 50-354/98-10 on 980920-1031.Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000354/19980081998-10-0909 October 1998 Insp Rept 50-354/98-08 on 980809-1019.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19980091998-10-0202 October 1998 Insp Rept 50-354/98-09 on 980817-26 & 0908.No Violations Noted.Major Areas Inspected:Maint & Engineering IR 05000354/19980071998-08-25025 August 1998 Insp Rept 50-354/98-07 on 980628-0808.Violation Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19980061998-07-21021 July 1998 Insp Rept 50-354/98-06 on 980517-0627.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000272/19982021998-07-0909 July 1998 Partially Deleted Insp Repts 50-272/98-202,50-311/98-202 & 50-354/98-202 on 980420-23.No Violations Noted.Major Areas Inspected:Conduct of Security & Safeguards Activities IR 05000354/19980801998-06-10010 June 1998 Insp Rept 50-354/98-80 on 980223-0319 & 0427-30.Violations Noted.Major Areas Inspected:Maint & Engineering IR 05000354/19980051998-06-0404 June 1998 Insp Rept 50-354/98-05 on 980405-0516.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19980021998-04-23023 April 1998 Insp Rept 50-354/98-02 on 980222-0404.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint,Plant Support & Effectiveness of Fire Protection Program IR 05000354/19980011998-03-16016 March 1998 Insp Rept 50-354/98-01 on 980104-0221.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20199L5321998-02-0303 February 1998 Insp Rept 50-354/97-10 on 971116-980103.Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20197D2111997-12-10010 December 1997 Insp Rept 50-354/97-09 on 971005-1115.Apparent Violation Being Considered for Escalated Ea.Major Areas Inspected: Licensee Operations,Engineering,Maint,Plant Support & Site Security Programs ML20199D3431997-11-13013 November 1997 Insp Rept 50-354/97-07 on 970824-1004.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support IR 05000354/19970051997-09-15015 September 1997 Insp Rept 50-354/97-05 on 970713-0823.Noncited Violations Identified.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000354/19970061997-09-0404 September 1997 Insp Rept 50-354/97-06 on 961112-970529.Violations Noted. Major Areas Inspected:Engineering ML20210N9131997-08-11011 August 1997 Insp Rept 50-354/97-04 on 970601-0712.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20140J3871997-06-12012 June 1997 Insp Rept 50-354/97-03 on 970429-0531.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20148D2301997-05-23023 May 1997 Insp Rept 50-354/97-02 on 970318-0428.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support.Routine Insp of Physical Protection & Security Program Also Conducted ML20137W7811997-04-14014 April 1997 Insp Rept 50-354/97-01 on 970202-0317.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint, & Plant Support ML20135A3901997-02-21021 February 1997 Insp Rept 50-354/96-11 on 961222-970201.Violation Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000354/19960101997-01-27027 January 1997 Insp Rept 50-354/96-10 on 961110-1221.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering,Plant Support & Security Program Plan IR 05000354/19960091996-12-0505 December 1996 Insp Rept 50-354/96-09 on 960922-1109.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20129D0891996-10-18018 October 1996 Insp Rept 50-354/96-07 on 960804-0921.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19950151996-02-14014 February 1996 Insp Rept 50-354/95-15 on 950905-1109.No Violations Noted. Major Areas inspected:safety-related Reactor Vessel Water Level Mod,Corrective Actons for Digital Feedwater Control Sys & RCIC Jockey Pump Corrective Action Process ML20084L7691995-05-30030 May 1995 Insp Rept 50-354/95-05 on 950406-21.No Violations Noted. Major Areas Inspected:Licensee Actions & Evaluations Associated W/Unplanned Release of Radioactive Matl from Hope Creek South Plant Vent That Occurred on 950405 IR 05000354/19930231993-12-15015 December 1993 Insp Rept 50-354/93-23 on 931004-1103.No Violations Noted. Major Areas Inspected:Review Licensee Corrective Actions of Previously Identified Edsfi Findings IR 05000354/19920191992-12-15015 December 1992 Insp Rept 50-354/92-19 on 921104-10.No Violations Noted. Major Areas Inspected:Licensees C/A for Mechanical Snubbers That Failed Functional Test & to Verify That Failed Snubbers Have Been Replaced or Restored to as-designed Condition IR 05000354/19910131991-06-21021 June 1991 Insp Rept 50-354/91-13 on 910520-24.No Violations Noted. Major Areas Inspected:Review of Several Open Items Remaining from Maint Team Insp 50-354/89-80 & Surveillance Test & Implementation IR 05000354/19900131990-07-26026 July 1990 Insp Rept 50-354/90-13 on 900618-22.No Violations Noted. Major Areas Inspected:Svc Water Intake Structure & Licensee Actions on Previous Insp Findings Re Svc Water Pipe Leak Examined IR 05000354/19900151990-07-19019 July 1990 Insp Rept 50-354/90-15 on 900625-29.No Violations Noted. Major Areas Inspected:Organization & Staffing,Training & Qualifications of Personnel,Procedures,Audits & Assessments, External & Internal Exposure Controls ML20246C4001989-08-15015 August 1989 Partially Deleted Insp Repts 50-272/89-19,50-311/89-17 & 50-354/89-15 on 890710-14 (Ref 10CFR73.21).Major Areas Inspected:Followup on Actions Taken in Response to Regulatory Effectiveness Review on 890410-14 IR 05000354/19890131989-07-20020 July 1989 Insp Rept 50-354/89-13 on 890626-30.No Violations Noted. Major Areas Inspected:Licensee Compliance to 10CFR50.62 ATWS Rule Pertaining to Alternate Rod Injection Sys IR 05000354/19890111989-07-10010 July 1989 Safety Insp Rept 50-354/89-11 on 890501-0619.No Violations Noted.Major Areas Inspected:Operations,Radiological Controls,Maint & Surveillance Testing,Emergency Preparedness,Security & LER & Open Item Followup IR 05000354/19890091989-05-10010 May 1989 Safety Insp Rept 50-354/89-09 on 890314-0430.No Violations Noted.Major Areas Inspected:Operations,Radiological Controls,Maint & Surveillance Testing,Emergency Preparedness,Security & LER Followup ML20247B6651989-05-0909 May 1989 Mgt Meeting Rept on 890307 & 0413.Major Areas Discussed: Status of Plant,Training & Safety Programs & Self Assessment Programs IR 05000354/19890021989-03-31031 March 1989 Safety Insp Rept 50-354/89-02 on 890124-0313.Violation Noted.Major Areas Inspected:Operations,Radiological Controls Maint & Surveillance Testing,Emergency Preparedness,Security & Engineering/Technical Support IR 05000354/19890061989-03-29029 March 1989 Insp Rept 50-354/89-06 on 890227-0303.No Violations Noted. Major Areas Inspected:Adequacy & Implementation of Licensees Fire Protection Program,Combustible Matl Control, Housekeeping Conditons & Fire Brigade Training IR 05000354/19890051989-03-23023 March 1989 Insp Rept 50-354/89-05 on 890227-0303.No Violations Noted. Major Areas Inspected:Adequacy,Implementation & Effectiveness of Radiological Controls Program During mid-cycle Outage,Organization,Training & Staffing IR 05000354/19890031989-02-28028 February 1989 Insp Rept 50-354/89-03 on 890206-10.No Violations Noted. Major Areas Inspected:Licensee Inservice Insp Activities to Ascertain That Inservice Insp Activities Conducted Per ASME Code & Regulatory Requirements IR 05000354/19880231988-11-0101 November 1988 Safety Insp Rept 50-354/88-23 on 880830-1011.Major Areas Inspected:Operations,Radiological Controls,Surveillance Testing,Maint,Emergency Preparedness,Security,Ler & Engineering/Technical Support IR 05000354/19880201988-10-24024 October 1988 IR 50-354/88-20 on 880906-16.No Violations Noted. Major Areas Inspected:Verification That Emergency Operating Procedures Technically Adequate IR 05000354/19880221988-09-15015 September 1988 Insp Rept 50-354/88-22 on 880712-0829.Violation Noted.Major Areas Inspected:Operations,Radiological Controls, Surveillance Testing,Maint,Emergency Preparedness,Security, Engineering/Technical Support & LER & Open Item Followup IR 05000298/19880191988-08-0303 August 1988 Insp Rept 50-298/88-19 on 880613-17.No Violations or Deviations Noted.Major Areas Inspected:Nonlicensed Staff Training,Qa Annual Review (Procurement,Receipt Insp & Audits) & Licensee Actions on Previous Concerns IR 05000354/19880181988-07-26026 July 1988 Insp Rept 50-354/88-18 on 880601-0711.No Violations Noted. Major Areas Inspected:Operational Safety Verification, Surveillance Testing,Maint Activities,Ler Followup & Assurance of Quality 1999-08-11
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000354/19990051999-10-0101 October 1999 Insp Rept 50-354/99-05 on 990711-0829.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs.Major Areas Inspected:Mitigating Sys,Barrier Integrity & Performance Indicator Verification IR 05000354/19990041999-08-11011 August 1999 Insp Rept 50-354/99-04 on 990530-0711.No Violations Noted. Major Areas inspected:cornerstone-mitigating Sys,Pi Verification IR 05000354/19990031999-06-21021 June 1999 Insp Rept 50-354/99-03 on 990419-0529.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19990021999-05-14014 May 1999 Insp Rept 50-354/99-02 on 990308-0418.Non-cited Violation Identified.Major Areas Inspected:Operations,Maint & Plant Support IR 05000354/19990011999-04-19019 April 1999 Insp Rept 50-354/99-01 on 990124-0307.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000354/19980111998-12-22022 December 1998 Insp Rept 50-354/98-11 on 981101-1212.No Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support IR 05000354/19980101998-11-23023 November 1998 Insp Rept 50-354/98-10 on 980920-1031.Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000354/19980081998-10-0909 October 1998 Insp Rept 50-354/98-08 on 980809-1019.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19980091998-10-0202 October 1998 Insp Rept 50-354/98-09 on 980817-26 & 0908.No Violations Noted.Major Areas Inspected:Maint & Engineering IR 05000354/19980071998-08-25025 August 1998 Insp Rept 50-354/98-07 on 980628-0808.Violation Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19980061998-07-21021 July 1998 Insp Rept 50-354/98-06 on 980517-0627.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000272/19982021998-07-0909 July 1998 Partially Deleted Insp Repts 50-272/98-202,50-311/98-202 & 50-354/98-202 on 980420-23.No Violations Noted.Major Areas Inspected:Conduct of Security & Safeguards Activities IR 05000354/19980801998-06-10010 June 1998 Insp Rept 50-354/98-80 on 980223-0319 & 0427-30.Violations Noted.Major Areas Inspected:Maint & Engineering IR 05000354/19980051998-06-0404 June 1998 Insp Rept 50-354/98-05 on 980405-0516.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19980021998-04-23023 April 1998 Insp Rept 50-354/98-02 on 980222-0404.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint,Plant Support & Effectiveness of Fire Protection Program IR 05000354/19980011998-03-16016 March 1998 Insp Rept 50-354/98-01 on 980104-0221.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20199L5321998-02-0303 February 1998 Insp Rept 50-354/97-10 on 971116-980103.Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20197D2111997-12-10010 December 1997 Insp Rept 50-354/97-09 on 971005-1115.Apparent Violation Being Considered for Escalated Ea.Major Areas Inspected: Licensee Operations,Engineering,Maint,Plant Support & Site Security Programs ML20199D3431997-11-13013 November 1997 Insp Rept 50-354/97-07 on 970824-1004.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support IR 05000354/19970051997-09-15015 September 1997 Insp Rept 50-354/97-05 on 970713-0823.Noncited Violations Identified.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000354/19970061997-09-0404 September 1997 Insp Rept 50-354/97-06 on 961112-970529.Violations Noted. Major Areas Inspected:Engineering ML20210N9131997-08-11011 August 1997 Insp Rept 50-354/97-04 on 970601-0712.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20140J3871997-06-12012 June 1997 Insp Rept 50-354/97-03 on 970429-0531.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20148D2301997-05-23023 May 1997 Insp Rept 50-354/97-02 on 970318-0428.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support.Routine Insp of Physical Protection & Security Program Also Conducted ML20137W7811997-04-14014 April 1997 Insp Rept 50-354/97-01 on 970202-0317.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint, & Plant Support ML20135A3901997-02-21021 February 1997 Insp Rept 50-354/96-11 on 961222-970201.Violation Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000354/19960101997-01-27027 January 1997 Insp Rept 50-354/96-10 on 961110-1221.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering,Plant Support & Security Program Plan IR 05000354/19960091996-12-0505 December 1996 Insp Rept 50-354/96-09 on 960922-1109.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20129D0891996-10-18018 October 1996 Insp Rept 50-354/96-07 on 960804-0921.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19950151996-02-14014 February 1996 Insp Rept 50-354/95-15 on 950905-1109.No Violations Noted. Major Areas inspected:safety-related Reactor Vessel Water Level Mod,Corrective Actons for Digital Feedwater Control Sys & RCIC Jockey Pump Corrective Action Process ML20084L7691995-05-30030 May 1995 Insp Rept 50-354/95-05 on 950406-21.No Violations Noted. Major Areas Inspected:Licensee Actions & Evaluations Associated W/Unplanned Release of Radioactive Matl from Hope Creek South Plant Vent That Occurred on 950405 IR 05000354/19930231993-12-15015 December 1993 Insp Rept 50-354/93-23 on 931004-1103.No Violations Noted. Major Areas Inspected:Review Licensee Corrective Actions of Previously Identified Edsfi Findings IR 05000354/19920191992-12-15015 December 1992 Insp Rept 50-354/92-19 on 921104-10.No Violations Noted. Major Areas Inspected:Licensees C/A for Mechanical Snubbers That Failed Functional Test & to Verify That Failed Snubbers Have Been Replaced or Restored to as-designed Condition IR 05000354/19910131991-06-21021 June 1991 Insp Rept 50-354/91-13 on 910520-24.No Violations Noted. Major Areas Inspected:Review of Several Open Items Remaining from Maint Team Insp 50-354/89-80 & Surveillance Test & Implementation IR 05000354/19900131990-07-26026 July 1990 Insp Rept 50-354/90-13 on 900618-22.No Violations Noted. Major Areas Inspected:Svc Water Intake Structure & Licensee Actions on Previous Insp Findings Re Svc Water Pipe Leak Examined IR 05000354/19900151990-07-19019 July 1990 Insp Rept 50-354/90-15 on 900625-29.No Violations Noted. Major Areas Inspected:Organization & Staffing,Training & Qualifications of Personnel,Procedures,Audits & Assessments, External & Internal Exposure Controls ML20246C4001989-08-15015 August 1989 Partially Deleted Insp Repts 50-272/89-19,50-311/89-17 & 50-354/89-15 on 890710-14 (Ref 10CFR73.21).Major Areas Inspected:Followup on Actions Taken in Response to Regulatory Effectiveness Review on 890410-14 IR 05000354/19890131989-07-20020 July 1989 Insp Rept 50-354/89-13 on 890626-30.No Violations Noted. Major Areas Inspected:Licensee Compliance to 10CFR50.62 ATWS Rule Pertaining to Alternate Rod Injection Sys IR 05000354/19890111989-07-10010 July 1989 Safety Insp Rept 50-354/89-11 on 890501-0619.No Violations Noted.Major Areas Inspected:Operations,Radiological Controls,Maint & Surveillance Testing,Emergency Preparedness,Security & LER & Open Item Followup IR 05000354/19890091989-05-10010 May 1989 Safety Insp Rept 50-354/89-09 on 890314-0430.No Violations Noted.Major Areas Inspected:Operations,Radiological Controls,Maint & Surveillance Testing,Emergency Preparedness,Security & LER Followup ML20247B6651989-05-0909 May 1989 Mgt Meeting Rept on 890307 & 0413.Major Areas Discussed: Status of Plant,Training & Safety Programs & Self Assessment Programs IR 05000354/19890021989-03-31031 March 1989 Safety Insp Rept 50-354/89-02 on 890124-0313.Violation Noted.Major Areas Inspected:Operations,Radiological Controls Maint & Surveillance Testing,Emergency Preparedness,Security & Engineering/Technical Support IR 05000354/19890061989-03-29029 March 1989 Insp Rept 50-354/89-06 on 890227-0303.No Violations Noted. Major Areas Inspected:Adequacy & Implementation of Licensees Fire Protection Program,Combustible Matl Control, Housekeeping Conditons & Fire Brigade Training IR 05000354/19890051989-03-23023 March 1989 Insp Rept 50-354/89-05 on 890227-0303.No Violations Noted. Major Areas Inspected:Adequacy,Implementation & Effectiveness of Radiological Controls Program During mid-cycle Outage,Organization,Training & Staffing IR 05000354/19890031989-02-28028 February 1989 Insp Rept 50-354/89-03 on 890206-10.No Violations Noted. Major Areas Inspected:Licensee Inservice Insp Activities to Ascertain That Inservice Insp Activities Conducted Per ASME Code & Regulatory Requirements IR 05000354/19880231988-11-0101 November 1988 Safety Insp Rept 50-354/88-23 on 880830-1011.Major Areas Inspected:Operations,Radiological Controls,Surveillance Testing,Maint,Emergency Preparedness,Security,Ler & Engineering/Technical Support IR 05000354/19880201988-10-24024 October 1988 IR 50-354/88-20 on 880906-16.No Violations Noted. Major Areas Inspected:Verification That Emergency Operating Procedures Technically Adequate IR 05000354/19880221988-09-15015 September 1988 Insp Rept 50-354/88-22 on 880712-0829.Violation Noted.Major Areas Inspected:Operations,Radiological Controls, Surveillance Testing,Maint,Emergency Preparedness,Security, Engineering/Technical Support & LER & Open Item Followup IR 05000298/19880191988-08-0303 August 1988 Insp Rept 50-298/88-19 on 880613-17.No Violations or Deviations Noted.Major Areas Inspected:Nonlicensed Staff Training,Qa Annual Review (Procurement,Receipt Insp & Audits) & Licensee Actions on Previous Concerns IR 05000354/19880181988-07-26026 July 1988 Insp Rept 50-354/88-18 on 880601-0711.No Violations Noted. Major Areas Inspected:Operational Safety Verification, Surveillance Testing,Maint Activities,Ler Followup & Assurance of Quality 1999-08-11
[Table view] Category:UTILITY
MONTHYEARIR 05000354/19900131990-07-26026 July 1990 Insp Rept 50-354/90-13 on 900618-22.No Violations Noted. Major Areas Inspected:Svc Water Intake Structure & Licensee Actions on Previous Insp Findings Re Svc Water Pipe Leak Examined IR 05000354/19900151990-07-19019 July 1990 Insp Rept 50-354/90-15 on 900625-29.No Violations Noted. Major Areas Inspected:Organization & Staffing,Training & Qualifications of Personnel,Procedures,Audits & Assessments, External & Internal Exposure Controls ML20246C4001989-08-15015 August 1989 Partially Deleted Insp Repts 50-272/89-19,50-311/89-17 & 50-354/89-15 on 890710-14 (Ref 10CFR73.21).Major Areas Inspected:Followup on Actions Taken in Response to Regulatory Effectiveness Review on 890410-14 IR 05000354/19890131989-07-20020 July 1989 Insp Rept 50-354/89-13 on 890626-30.No Violations Noted. Major Areas Inspected:Licensee Compliance to 10CFR50.62 ATWS Rule Pertaining to Alternate Rod Injection Sys IR 05000354/19890111989-07-10010 July 1989 Safety Insp Rept 50-354/89-11 on 890501-0619.No Violations Noted.Major Areas Inspected:Operations,Radiological Controls,Maint & Surveillance Testing,Emergency Preparedness,Security & LER & Open Item Followup IR 05000354/19890091989-05-10010 May 1989 Safety Insp Rept 50-354/89-09 on 890314-0430.No Violations Noted.Major Areas Inspected:Operations,Radiological Controls,Maint & Surveillance Testing,Emergency Preparedness,Security & LER Followup ML20247B6651989-05-0909 May 1989 Mgt Meeting Rept on 890307 & 0413.Major Areas Discussed: Status of Plant,Training & Safety Programs & Self Assessment Programs IR 05000354/19890021989-03-31031 March 1989 Safety Insp Rept 50-354/89-02 on 890124-0313.Violation Noted.Major Areas Inspected:Operations,Radiological Controls Maint & Surveillance Testing,Emergency Preparedness,Security & Engineering/Technical Support IR 05000354/19890061989-03-29029 March 1989 Insp Rept 50-354/89-06 on 890227-0303.No Violations Noted. Major Areas Inspected:Adequacy & Implementation of Licensees Fire Protection Program,Combustible Matl Control, Housekeeping Conditons & Fire Brigade Training IR 05000354/19890051989-03-23023 March 1989 Insp Rept 50-354/89-05 on 890227-0303.No Violations Noted. Major Areas Inspected:Adequacy,Implementation & Effectiveness of Radiological Controls Program During mid-cycle Outage,Organization,Training & Staffing IR 05000354/19890031989-02-28028 February 1989 Insp Rept 50-354/89-03 on 890206-10.No Violations Noted. Major Areas Inspected:Licensee Inservice Insp Activities to Ascertain That Inservice Insp Activities Conducted Per ASME Code & Regulatory Requirements IR 05000354/19880231988-11-0101 November 1988 Safety Insp Rept 50-354/88-23 on 880830-1011.Major Areas Inspected:Operations,Radiological Controls,Surveillance Testing,Maint,Emergency Preparedness,Security,Ler & Engineering/Technical Support IR 05000354/19880221988-09-15015 September 1988 Insp Rept 50-354/88-22 on 880712-0829.Violation Noted.Major Areas Inspected:Operations,Radiological Controls, Surveillance Testing,Maint,Emergency Preparedness,Security, Engineering/Technical Support & LER & Open Item Followup IR 05000298/19880191988-08-0303 August 1988 Insp Rept 50-298/88-19 on 880613-17.No Violations or Deviations Noted.Major Areas Inspected:Nonlicensed Staff Training,Qa Annual Review (Procurement,Receipt Insp & Audits) & Licensee Actions on Previous Concerns IR 05000354/19880181988-07-26026 July 1988 Insp Rept 50-354/88-18 on 880601-0711.No Violations Noted. Major Areas Inspected:Operational Safety Verification, Surveillance Testing,Maint Activities,Ler Followup & Assurance of Quality IR 05000354/19880161988-07-0606 July 1988 Insp Rept 50-354/88-16 on 880426-0531.No Violations Noted. Major Areas Inspected:Operational Safety Verification, Surveillance Testing,Maint Activities,Esf Sys Walkdown,Ler Followup,Emergency Preparedness & Assurance of Quality IR 05000354/19880101988-06-21021 June 1988 Insp Rept 50-354/88-10 on 880404-08.No Violations Noted. Major Areas Inspected:Review of Previously Identified Unresolved Items & Maint Outage Mgt That Encompassed Observations of Limitorque Valve Operator Insp IR 05000354/19880141988-06-20020 June 1988 Insp Rept 50-354/88-14 on 880418-22.No Violations or Deviations Noted.Major Areas Inspected:Solid Radwaste Processing,Preparation,Packaging & Shipping Program, Including Previously Identified Items ML20196J0671988-06-17017 June 1988 Enforcement Conference Rept 50-354/88-20 on 880609.Major Areas Inspected:Dept of Labor Determination That Contractor Bogan Discriminated Against Employee for Raising Safety Concerns.Agenda & Supporting Info Encl IR 05000354/19880171988-06-0202 June 1988 Insp Rept 50-354/88-17 on 880509-13.No Violations Noted. Major Areas Inspected:Licensee Effluent Controls,Liquid Effluent,Gaseous Effluent,Effluent Monitor Calibr, Ventilation Sys & Offsite Dose Calculation Manual IR 05000354/19880151988-06-0202 June 1988 Insp Rept 50-354/88-15 on 880418-22.No Violations or Deviations Noted.Major Areas Inspected:Startup Test Program Following First Refueling,Including Review of Startup Test Procedures & Test Results Evaluation IR 05000354/19880091988-05-24024 May 1988 Insp Rept 50-354/88-09 on 880322-0425.No Violations Noted. Major Areas Inspected:Operational Safety Verification, Surveillance Testing,Maint Activities,Review of Maint Program,Esf Sys Walkdown & Assurance of Quality ML20197E2951988-05-19019 May 1988 Insp Rept 50-354/88-11 on 880321-25.No Violations or Deviations Noted.Major Areas Inspected:Review of Licensee Action in Response to Mark I Containment Mod Requirements of NUREG-0661 IR 05000354/19880081988-04-20020 April 1988 Insp Rept 50-354/88-08 on 880314-18.No Violations or Deviations Noted.Major Areas Inspected:Local Leak Rate Testing of Containment Isolation Boundaries & Implementation of Inservice Test Program for Pumps & Valves IR 05000354/19880061988-04-20020 April 1988 Insp Rept 50-354/88-06 on 880229-0303.No Violations Noted. Major Areas Inspected:Licensee Actions on Previous Findings, Organization & Staffing,Communications,Audits,Alara & High Radiation Area Access Control IR 05000354/19880131988-04-14014 April 1988 Insp Rept 50-354/88-13 on 880328-29.No Violations Noted. Major Areas Inspected:Inservice Insp Activities to Ascertain Whether Licensee Activities Conducted in Compliance W/ Applicable ASME Code & Regulatory Requirements ML20151W1711988-04-0909 April 1988 Insp Rept 50-354/88-03 on 880126-29.Violation Noted.Major Areas Inspected:Licensee Environ Qualification Program & Licensee Response & Resolutions to Equipment Concerns Identified in SER IR 05000354/19880051988-04-0404 April 1988 Onsite Resident Insp Rept 50-354/88-05 on 880209-0321. Violation Noted.Major Areas Inspected:Operational Safety Verification,Surveillance Testing,Maint Activities,Reactor Coolant Spill in Torus Basement & Assurance of Quality IR 05000272/19880061988-03-18018 March 1988 Partially Withheld Physical Security Insp Repts 50-272/88-06,50-311/88-06 & 50-354/88-04 on 880201-05 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected: Procedures,Security Organization & Mgt Effectiveness IR 05000354/19880011988-03-0404 March 1988 Insp Rept 50-354/88-01 on 880105-0208.Violation Noted.Major Areas Inspected:Followup of Outstanding Insp Items, Operational Safety Verification,Surveillance Testing,Maint Activities,Esf Sys Walkdown,Lers & Design Change Packages IR 05000354/19870271987-12-31031 December 1987 Radiological Controls Insp Rept 50-354/87-27 on 871116-18 & 20.No Violations Noted.Major Areas Inspected:Process & Area Radiation Monitor Surveillance Testing,Sealed Sources, Radiological Controls for New Fuel Receipt & Insp & ALARA IR 05000354/19870281987-12-21021 December 1987 Insp Rept 50-354/87-28 on 871116-20.No Violation Noted.Major Areas Inspected:Radiochemical Measurements Program, Confirmatory Measurements,Audits & Boron Analysis IR 05000354/19870251987-11-25025 November 1987 Insp Rept 50-354/87-25 on 870921-25.No Violations Noted. Major Areas Inspected:Organization & Staffing,Mgt Oversight, Training & Qualification,External Exposure Controls,Alara, Internal Exposure Controls & High Radiation Area Controls IR 05000354/19870201987-11-0303 November 1987 Emergency Preparedness Insp Rept 50-354/87-20 on 870908-10. No Violations Noted.Major Areas Inspected:Observation of Licensee Full Participation,Emergency Exercise Conducted on 870909 & Insp of Training Records ML20235T8501987-10-0101 October 1987 Insp Rept 50-354/87-17 on 870714-0817.Violation Noted.Major Areas Inspected:Followup on Outstanding Insp Items,Maint Activities,Operational Safety Verification,Surveillance Testing,Esf Sys Walkdown & Instrument Calibr Data Cards IR 05000354/19870191987-10-0101 October 1987 Insp Rept 50-354/87-19 on 870727-30.No Violations Noted. Major Areas Inspected:Licensee Action on Previous NRC Findings,Organization & Staffing,Audits & External Exposure Control IR 05000354/19870211987-09-0404 September 1987 Insp Rept 50-354/87-21 on 870817-21.No Violations or Deviations Noted.Major Areas Inspected:Licensee Program for Resolving QA Action Requests IR 05000354/19870161987-07-20020 July 1987 Insp Rept 50-354/87-16 on 870609-0713.Violations Noted. Major Areas Inspected:Followup on Outstanding Insp Items, Operational Safety Verification,Surveillance Testing,Maint Activities,Esf Sys Walkdown & LER Followup IR 05000354/19870141987-07-0606 July 1987 Insp Rept 50-354/87-14 on 870512-0608.Deviation Noted.Major Areas Inspected:Outstanding Insp Items,Operational Safety Verification,Surveillance Testing,Maint Activities,Esf Sys Walkdown & LER Followup IR 05000354/19870131987-06-0101 June 1987 Insp Rept 50-354/87-13 on 870504-06 & 12.No Violations Noted.Major Areas Inspected:Licensee Activities in Areas of Surveillance Testing,Procedures & Records IR 05000354/19870111987-05-28028 May 1987 Insp Rept 50-354/87-11 on 870414-0511.Major Areas Inspected: Followup on Outstanding Insp Items,Operational Safety Verification & Security Insp.Addl Mgt Attention Needed in Housekeeping Area to Ensure Cleanliness Stds Maintained IR 05000354/19870101987-04-0707 April 1987 Insp Rept 50-354/87-10 on 870316-20.No Violations Noted. Major Areas inspected:post-accident Monitoring Sys Conformance W/Rev 2 to Reg Guide 1.97.Open Item Identified Re Identification of Category 2 Equipment IR 05000354/19870071987-04-0303 April 1987 Insp Rept 50-354/87-07 on 870309-13.Unresolved Items Re Evaluation of Offgas Delay Time & Determination of Dose & Dose Commitments & Continuing Problems W/Licensee Process & Effluent Monitors Noted IR 05000354/19870061987-03-23023 March 1987 Insp Rept 50-354/87-06 on 870224-26.No Violations Noted. Major Areas Inspected:Power Ascension Test Program,Plateau Review,Test Results Evaluation,Outstanding Results Deficiencies,Qa Interface & Independent Measurements IR 05000354/19870031987-03-23023 March 1987 Insp Rept 50-354/87-03 on 870209-13.No Violations,Deviations or Unresolved Items Noted.Major Areas Inspected:Emergency Preparedness Program IR 05000354/19870051987-03-20020 March 1987 Insp Rept 50-354/87-05 on 870210-0309.Violation Noted: Failure to Obtain & Analyze Grab Samples of Cooling Tower Blowdown Line.Unresolved Item Noted Re Environ Qualification of MSIV Terminal Boxes IR 05000354/19870011987-03-0404 March 1987 Insp Rept 50-354/87-01 on 870101-0209.Violation Noted: Failure to Obtain & Analyze Grab Samples Per Drywell Leak Detection Action Statement IR 05000354/19870041987-03-0404 March 1987 Insp Rept 50-354/87-04 on 870127-30.No Violations Noted. Major Areas Inspected:Nonradiological Chemistry Program, Including Measurement Control & Analytical Procedure Evaluations IR 05000354/19870021987-02-0606 February 1987 Safety Insp Rept 50-354/87-02 on 870112-16.Violations Noted: Failure to Properly Identify & Quantify Fe-59 & Zr-95 in Shipment 86-04,Details 6.1 & 6.4 & Incorrect Certification for Shipment 86-04,Detail 6.1 IR 05000354/19860601987-02-0505 February 1987 Physical Security Insp Rept 50-354/86-60 on 861230.No Violation Noted.Major Areas Inspected:Review of Licensee Program for Conducting Contingency Drills to Evaluate Effectiveness & Impact of Drills During Security Activities 1990-07-26
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000354/19983021999-10-13013 October 1999 Suppl NRC Operator Licensing Exam Rept 50-354/98-302 on 991025-29 (NRC Onsite Review),Mgt Meeting on 990322, in-office Reviews on 990429-30 & 0617-18 & Telephone Call on Appeal Results on 990720 IR 05000354/19990051999-10-0101 October 1999 Insp Rept 50-354/99-05 on 990711-0829.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs.Major Areas Inspected:Mitigating Sys,Barrier Integrity & Performance Indicator Verification PNO-I-99-043, on 990916,Hurricane Floyd Was Approaching Ccnpp,Sgs,Hcgs & Ocnpp.Hurricane Was Centered at Latitude 36.0 North & Longitude 76.6 West & Moving north-northeast at Approx 25 Mph.Plants Remain at Power1999-09-16016 September 1999 PNO-I-99-043:on 990916,Hurricane Floyd Was Approaching Ccnpp,Sgs,Hcgs & Ocnpp.Hurricane Was Centered at Latitude 36.0 North & Longitude 76.6 West & Moving north-northeast at Approx 25 Mph.Plants Remain at Power IR 05000354/19990041999-08-11011 August 1999 Insp Rept 50-354/99-04 on 990530-0711.No Violations Noted. Major Areas inspected:cornerstone-mitigating Sys,Pi Verification IR 05000354/19990031999-06-21021 June 1999 Insp Rept 50-354/99-03 on 990419-0529.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19990021999-05-14014 May 1999 Insp Rept 50-354/99-02 on 990308-0418.Non-cited Violation Identified.Major Areas Inspected:Operations,Maint & Plant Support IR 05000354/19990011999-04-19019 April 1999 Insp Rept 50-354/99-01 on 990124-0307.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000354/19980111998-12-22022 December 1998 Insp Rept 50-354/98-11 on 981101-1212.No Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support ML20196D0911998-11-23023 November 1998 Notice of Violation from Insp on 980920-1031.Violation Noted:On 981001,electricians Placed Single Degraded Cell Associated with Operable 1E Battery Bank on Single Cell Charge IR 05000354/19980101998-11-23023 November 1998 Insp Rept 50-354/98-10 on 980920-1031.Violations Noted. Major Areas Inspected:Operations,Maint & Engineering PNO-I-98-053, on 981115,plant Experienced Turbine Trip While Operating at 95% Power Due to High Level Condition on One of Two Moisture Separators.Reactor Automatically Shut Down.Util Evaluating Incorrect Sys Drawing.States of Nj & DE Notifie1998-11-16016 November 1998 PNO-I-98-053:on 981115,plant Experienced Turbine Trip While Operating at 95% Power Due to High Level Condition on One of Two Moisture Separators.Reactor Automatically Shut Down.Util Evaluating Incorrect Sys Drawing.States of Nj & DE Notifie ML20154Q7381998-10-16016 October 1998 Second Suppl to NRC Exam Rept 50-354/98-03OL for Tests Administered on 980304-12,0519-21,22-28 & 0629.Five of Five Reactor Operator Applicants & Four of Five Senior Reactor Applicants Passed Exams ML20154J8611998-10-0909 October 1998 Notice of Violation from Insp on 980809-0919.Violation Noted:On 980831,licensee Did Not Promptly Correct Condition Adverse to Quality in That 'C' Residual Heat Removal Pump Rendered Inoperable IR 05000354/19980081998-10-0909 October 1998 Insp Rept 50-354/98-08 on 980809-1019.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19980091998-10-0202 October 1998 Insp Rept 50-354/98-09 on 980817-26 & 0908.No Violations Noted.Major Areas Inspected:Maint & Engineering IR 05000354/19983011998-09-0404 September 1998 Exam Rept 50-354/98-301OL Conducted on 980810-12.Exam Results:Four SRO Candidates Performed Well on Both Written & Operating Portions of Exam.All Four Were Issued Licenses ML20237E4981998-08-25025 August 1998 Notice of Violation from Insp on 980628-0808.Violation Noted:As of 980810,util Had Not Corrected Known Deficiency in Verifying MSIV Full Closed During Springs Only Full Stroke Closing Tests IR 05000354/19980071998-08-25025 August 1998 Insp Rept 50-354/98-07 on 980628-0808.Violation Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19980061998-07-21021 July 1998 Insp Rept 50-354/98-06 on 980517-0627.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20236T1601998-07-21021 July 1998 Notice of Violation from Insp on 980517-0627.Violation Noted:As of Oct 1997,chemistry Technicians Did Not Sample & Analyze Diesel Fuel Oil Deliveries for Particulates & Did Not Report Results by Written Notification within 14 Days IR 05000272/19982021998-07-0909 July 1998 Partially Deleted Insp Repts 50-272/98-202,50-311/98-202 & 50-354/98-202 on 980420-23.No Violations Noted.Major Areas Inspected:Conduct of Security & Safeguards Activities IR 05000354/19980031998-06-16016 June 1998 Suppl to NRC Licensing Exam Rept 50-354/98-03OL (Including Completed & Graded Tests) for Tests Administered on 980223- 0304 IR 05000354/19980801998-06-10010 June 1998 Insp Rept 50-354/98-80 on 980223-0319 & 0427-30.Violations Noted.Major Areas Inspected:Maint & Engineering ML20249A2031998-06-10010 June 1998 Notice of Violation from Insp on 980223-0319 & 0427-30. Violation Noted:Conditions Adverse to Quality Were Not Promptly Identified & Corrected IR 05000354/19980991998-06-0808 June 1998 SALP Rept 50-354/98-99 for Period of 961110-980516 ML20249A1071998-06-0404 June 1998 Notice of Violation from Insp on 980405-0516.Violation Noted:During Refueling Outage RF03 in Dec 1990 Licensee Did Not Maintain RHR Sys in Operation IR 05000354/19980051998-06-0404 June 1998 Insp Rept 50-354/98-05 on 980405-0516.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20217M0491998-04-28028 April 1998 NRC Operator Licensing Exam Rept 50-354/98-03OL,(including Completed & Graded Tests) for Tests Administered on 980223-0304 ML20217N6221998-04-24024 April 1998 Notice of Violation from Investigation Conducted by Oi. Violation Noted:Safeguard Event Log,Required to Be Maintained by Licensee,Was Not Complete & Accurate in All Matl Aspects IR 05000354/19980021998-04-23023 April 1998 Insp Rept 50-354/98-02 on 980222-0404.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint,Plant Support & Effectiveness of Fire Protection Program ML20217H8051998-04-23023 April 1998 Notice of Violation from Insp on 980222-0404.Violation Noted:Three Examples of Inadequate Accomplishment of Procedure Control Associated W/Temporary Equipment Installed in Plant Svc Water Intake Structure ML20217C6711998-03-20020 March 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:On 971112,while Reactor Was in Cold Shutdown W/Rv Head Removed,Operators Did Not Verify That CR Position Did Not Change During Withdrawal ML20217D8291998-03-17017 March 1998 EN-98-013:informs That NOV & Proposed Imposition of Civil Penalty in Amount of $55,000 Will Be Issued on or About 980330 to Pse&G.Civil Penalty Based on Violation Involving Failure by Operating Crew to Follow Procedures IR 05000354/19980011998-03-16016 March 1998 Insp Rept 50-354/98-01 on 980104-0221.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20199L4791998-02-0303 February 1998 Notice of Violation from Insp on 971126-980103.Violation Noted:On 971124,maint Technicians Failed to Follow HC.IC-DC.ZZ-0140(Q),Rev 3, Device/Equipment Calibration Masonleilan Pressure & Temperature Controllers ML20199L5321998-02-0303 February 1998 Insp Rept 50-354/97-10 on 971116-980103.Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20197D2111997-12-10010 December 1997 Insp Rept 50-354/97-09 on 971005-1115.Apparent Violation Being Considered for Escalated Ea.Major Areas Inspected: Licensee Operations,Engineering,Maint,Plant Support & Site Security Programs ML20199D3431997-11-13013 November 1997 Insp Rept 50-354/97-07 on 970824-1004.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support ML20199D3171997-11-12012 November 1997 Notice of Violation from Insp on 970824-1004.Violation Noted:On 970914,electric motor-driven Fire Pump Supply Breaker Opened During Electrical Bus Swap Which Rendered Pump Inoperable ML20196J6531997-10-20020 October 1997 Notice of Violation from Insp on 970202 & 0317.Violation Noted:In Apr 1994,licensee Made Changes to Facility That Involved USQ Without Prior Commission Approval ML20198L9531997-10-15015 October 1997 NRC Operator Licensing Exam Rept 50-354/97-08OL for Tests Administered on 970929-1002.Exam Results:Four Candidates Passed All Portions of License Exam.One Candidate Failed Written Exam IR 05000354/19970051997-09-15015 September 1997 Insp Rept 50-354/97-05 on 970713-0823.Noncited Violations Identified.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000354/19970061997-09-0404 September 1997 Insp Rept 50-354/97-06 on 961112-970529.Violations Noted. Major Areas Inspected:Engineering ML20210N9061997-08-11011 August 1997 Notice of Violation from Insp on 970601-0712.Violation Noted:Inoperable HPCI Sys Injection Valve Was Not Promptly Identified ML20210N9131997-08-11011 August 1997 Insp Rept 50-354/97-04 on 970601-0712.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20217E7851997-07-25025 July 1997 Investigation Rept 1-96-024 on 970725.No Noncompliance Noted.Major Areas Investigated:Allegations Re Failure to Make 10CFR73.71 Notification by Station Security Dept ML20140J3811997-06-12012 June 1997 Notice of Violation from Insp on 970429-0531.Violation Noted:Failing to Adhere to Established Procedural Guidance for safety-related Activities Were Identified,Significant Condition Adverse to Quality ML20140J3871997-06-12012 June 1997 Insp Rept 50-354/97-03 on 970429-0531.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20148D2301997-05-23023 May 1997 Insp Rept 50-354/97-02 on 970318-0428.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support.Routine Insp of Physical Protection & Security Program Also Conducted ML20148D2011997-05-23023 May 1997 Notice of Violation from Insp on 970318-0428.Violation Noted:On 970423,operators Failed to Shut Six of Twelve Cylinder Indicator Test Cocks Following Completion of C Emergency Diesel Generator pre-start Checks 1999-09-16
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U.S. NUCLEAR REGULATORY COMMISSION REGION I .
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Report N /88-15 Docket N License No. NPF-57 Licensee: Public Service Electric & Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038 Facility Name: Hope Creek-Nuclear Generating Station Inspection At: -Hancock Bridge, New Jersey Inspection Conducted: Apri.1 18-22, 1988
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Inspector: du bDN
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Henri F. van Kessel, Reactor Engineer date Approved by: h, K , k dw G[4!87 Dr. P. K. Eapen, Chidf Special Test da t'e Programs Section, EB, DRS Inspection Summary: Inspection on April 18-22, 1988 (Inspection Number 50-354/88-15)
Areas Inspected: Routine Unannounced Inspection of the startup test program following the first refueling, including the review of startup test procedures and test results evaluation, an independent calculation of the core thermal power balance, and the review of activities in the QA/QC interface with the afore said startup test program.
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M ection Results: No violations or deviations were identifie See Attachment C for acronyms used in this report.
8806160164 880608 PDR ADOCK 05000354 o DCD L
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J 1.0 Persons Contacted Public Service Electric and Gas (PSE&G)-
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- R. W. Beckwith, Station Licensing Engineer it T. Brown, Nuclear Technical Engineer
- J. DeFebo, Quality Assurance Engineer J..M. Haun, Senior Nuclear Supervisor
- S. L. Funsten, Maintenance Controls Engineer 1
- R. T. Griffith, Sr. , Principal QA Engineer ;
- S. LaBruna, General Manager Hope Creek Operations
- LaVecchia, Princ'ipal QA Engineer
- J. E. Metro, Reactor Staff Engineer
- J. Nichols, Technical Manager HC0 >
J. O'Brien,-Reactor Engineer i R. J. Schmidt, Technical Engineer C. Vondra, Operations Manager U.S. Nuclear Regulatory Commission
- W. Meyer, Senior Resident Inspector
- Denotes those present during exit meeting held on April 22, 1988 2.0 Startup Test Program (72700)
2.1 Startup-Test Procedure Review The startup test procedures as listed in Attachment A were reviewed
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- Management review and approval
- Clarity of stated objectives
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- Environmental conditions ,
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- Acceptance criteria and their sources
- References l * Initial conditions ,
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- Attainment of test objectives
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- Test performance documentation and verification a Degree of detail for test instructions
Restoration of system to normal after testing
- Identification of test personnel
Evaluation of test data
Independent verification of critical steps or parameters
- Quality control and assurance involvement Findings No noncompliances were identified by the inspector within the scope of this inspectio .2 Test Result Evaluation The test procedures listed in Attachment A (with asterisk) were reviewed to verify that adequate testing was accomplished in order to satisfy regulatory guidance and licensee commitments and to ascertain whether uniform criteria were being applied for evaluating completed preoperational tests in order to assure their technical and administrative adequac The test results were reviewed for:
- Recording of conduct of test
- System restoration to normal
- Independent verification of critical steps or parameters
- Identification of test personnel
Verification that the test results have been approved
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The following observations were made for the procedures within the scope of this inspection:
Core Power Distribution Limits: RE-ST.ZZ-001
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(1) The plant was operated within the licensed power distribution limits. A P-1, the periodic NSS Core Performance Log, had been -
printed out from the process computer every hour. In all of these cases, the MFLCPR, MFLPD, and MAPRAT were smaller than unity indi-cating that the corresponding values in the Technical Specification for the Critical Power Ratio, the Linear Heat Generation Rate and the '
Maximum Average Planar Linear Heat Generation Rate, respectively, had not been exceede (2) The means used to confirm operation within the limits mentioned under (1) above consisted of the standard General Electric Company (GE) computer software as supplied for BWRs 4/5 and, as such, had been reviewed by NRR some time ag (3) The licensee is preparing a backup software program. A 10 CFR 50.59' type evaluation will be made for this backup program upon completio (4) An 00-1 program, "Whole Core LPRM Calibration and Base Distributions," had been run at the 75% and the 100% power plateau.
1 The TIP machine normalization factors were obtained by traversing each probe, one at a time, through the common calibration tub There are 5 TIP machines and 43 channels. A flux chart was produced for each channel at 100% power on April 17, 1988. The normalization of the TIP readings is done by the OD-1 software program. These data were used for APRM calibration. When the LPRM goes out of calibration, Base Crit Code will be printed on the P-1 printou (5) The APRM set points did not have to be adjusted for CMPF peaking factor at core max fraction of limiting power density greater than
. design value because they could stay within the time limit (6 hrs.)
by changing control rod patter (6) APRM gain adjustments were made at 98.8% power on April ;
17, 1988. An 00-3, "Core Thermal Power and APRM Calibration," was
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made to provide new Gain Adjustment Factors (GAFs). This was done
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at the 100, 89, 63, and 24 percent power levels.
i (7) TIP traces were made after adjustments to observe the impact on CMPF values at the 75% and 100% power plateau In each case proper APRM calibration was obtained as indicated by the absence of Base r Crit Codes on the P-1 printou !
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(8) Although the process computer has not malfunctioned to date, a f
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GE document (NE00 25443) can be used to ascertain that the plant is
' operating within licensed limits when the process computer is dow The GE document (NEDO-25443)* was reviewed by NRR. The licensee is preparing an independent software program which car be used on >
another available computer. This program will be essentially the
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same as the GE plant monitoring program but can be run on another compute t
- NE00 25443, "P-1 Backup (PIB), a manual method for core performance .i evaluation and LPRM calibration," by G. R. Parkos, November 1981, General Electri (9) An 00-1 was made just before LPRM gain changes at 100*4 powe Gain adjustments were made. A new 00-1 was produced after these gain adjustments'. All final GAF values were within the Tech. Spec.
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LPRM Calibration: RE-ST.SE-003
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(1) LPRM calibration had been performed at the different power h levels in accordance with the procerkr (2) APRMs had been recalibrated following LPRM gain adjustments in accordance with step 5.1.16 in the procedure. (See, for example, *
APRM calibration calculation / data sheet, dated 4-17-88, attachment 1 i
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of RE-ST.SE-002), t (3) The identification of LPRM calibrations is tracked by the data ,
. on Attachment 1 of the procedur These data are used to detect loss of sensitivity of the sensors. A program is being written in ,
- the Fuel Group to do this on the computer. At present, this work is done manually.
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i (4) LPRM readings were obtained at core conditions existing prior to r
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i amslifier gain adjustments. (See "as foJnd" values on Attachment
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1). The performance of a full core flux map, by means of the TIP .
syst en., was obtained prior to making amplifier gain changes as can ;
be seen in the 00-1 edit. A P-1 calculation was performed after the ;
full core flux map for the calibrated APRM readings (See P-1 dated 4-17-88,0256).
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1 (5) Calculations were made for the new input calibration currents to
- be applied to the respective LPRM amplifiers (See Attachment 1).
!- These calculated input currents were applied to make the proper LPRM '
calibration adjustment ,
(6) Each APRM channel was by passed during its espective LPRM group -
adjustments in accordance with paragraphs 5,1.7 Ond 5.1.8 of l IC-CC.SE-029, "channel calibration nuclear instrut'entation system - '
l LPRM gain calibration." ;
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(7) Reviews were made of the Full Core Flux Map and a P-1 af ter the LPRM calibration adjustments. All of the GAFs were verified to be within the established limit (8) An 0D-3 was made following the LPRM calibrations to assure that APRM settings were within Tech. Spec. Limits (see for example the 00-3 made on April 17, 1988)
APRM Calibration: RE-ST.SE-002 (1) The APRM system was properly calibrated to the Core Thermal Power as can be seen, for instance, in Attachment 1 of the procedure, dated April 17, 198 (2) As a prerequisite (2.3 paragraph), the core was maintained at steady state operating conditions at the desired power level and recirculation flow rate during the calibratio (3) Only one APRM channel, per RPS bus, was bypassed at a tim Since there is only one switch per RPS bus, there is no physical possibility for this to happe (4) The APRMs were adjusted to read calculated % of rated power ar (videnced, for example, by the calculation of Attachment 1 of the procedure, dated April 21, 1988. The same reference also shows the
"as left" APRM readings versus !; thermal powe Core Thermal Power Evaluation: RE-RA.ZZ-001 (1) The power range nuclear instruments were properly adjusted to agree with the heat balance results as evidenced by Attachment 1 of the procedure for the 98.7?; power level during startu (2) An independent hand calculation was made by the inspector using the licensee's procedure (RE-RA.ZZ-001). The results are discussed in this report under Section (3) The results of this procedure were reviewed and approved by the licensee's designees in accordance with Administrative Procedure AP.12. Approvals were made by the Senior Reactor Superviso Determination of Reactor Shutdown Margin (SDM): RE-ST.ZZ-007 (1) Changes to SDM, due to inoperative control rods, were not experienced during this startu (2) The SDM af ter startup was in agreement with the Technical Specifications as evidenced by the completed attachments of this procedure, dated April 10, 1988, soon after criticalit . .
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(3) The reactor went critical on 2152 notche The demonstrated SDM=1.983% Ak/k as shown in Attachment 3 of the procedur The SDM is required to be greater than .769% ak/ (4) The licensee reviewed the data supplied by the vendor (GE) and amongst others used it in their own SOM determination. The data were presented by GE in their Document No. 23A5879, rev. O, "Hope Creek Cycle 2, Cycle Management Report", by H. H. Yeager. , dated March 25, 1988. PSE&Gs fuel department produced, independently, a document by the same title i .e., NFU-0092, dated March 29, 1988. The latter document, however, does not contain any reference to the GE-document, raising the impression that the GE data were not used in the preparation of same or for comparison of results. This item was discussed with the representatives of the nuclear fuel departmen They concurred that the reference should be made because the compari-son of the data of the two reports was made and, in the case of the SDM, the pSE&G data were more conservative. The GE document will be added to the reference listing of the pSE&G repor (5) No stuck out rod problems were experienced and, therefore, no special SDM determination had to be mad . 0A/QC Interface The participation of Station QA in test witnessing of the post refueling startup tests was evaluated by the inspector. The Station QA Surveillance Reports as listed in Attachment B were reviewe The inspector observed that none of the QA Surveillance reports contained any unsatisfactory finding. The check lists appeared to cover all of the important acceptance criteria and none of these criteria were violated during the test Station QA Surveillance Report No.88-246, however, found that testing was performed while the system (in test) was legitimately being worked on under work order 880303065 and had relay E21-K14B missing (in plastic bag)
from the system. This finding was not identified as an unsatisfactory item. The inspector discussed this item with the QA personnel responsible for the surveillance. The QA personnel provided the following statement
e an explanation:
l "There was a lack of communications between the supervisors in the I&C Department, which permitted IC-FT-BB-004 to be run; however, the Operations Department had declared this system INOPERABLE prior to performance of IC-FT-BB-004. Since we were in a refuel outage, this system was not required to be operable in Mode 5 with cavity flooded.
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[ When a. system is not required for a particular operating condision or is in an outage declared IN0 PERATIVE by operations, it is a normal ,
acceptable practice for multiple Station departments to perform several '
maintenance functions in parallel. Upon completion of the maintenance, a-channel calibration / functional--test is performed prior to declaring the *
-system operable."
In the case noted above, the I&C miscommunication resulted in an attempt to run the Functional Test prior to completion of maintenance wor The requirements of the Station retest program and the fact that the system had previously been declared inoperable provide the necessary insurance that return to operable status would bt achieved."
The inspector found the above explanation to be adequat No discrepancies or unacceptable conditions, other than the one mentioned
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above, were noted in the review of the QA Surveillance report :
' Independent Effort The inspector, independently, calculated the thermal power balance for the
core in accordance with instructions contained in procedure RE-RA.ZZ-001 and for the data of April 16, 198 Discrepancies were found fo.-
formulae line items [6] and [7] where the formulae include a factor of 32 i
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to be subtracted from the mV reading in each case. This factor no longer
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exists because the transmitter range was changed to (0-166mV). The i results for the April 16 data were not affected because an alternate method was used to calculate the pertinent value Another discrepancy involved line items [4] and [5] on page 2 of
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Attachment The mV values versus temperature on the table of page S '
were misread causing the calculated temperatures to be higher for the correct readings. The impact of the latter discrepancy was that the j calculated core thermal power wcs 2 Kdth, higher than the actual.
l The licensee issued rev. 3 of procedure RE-RA.ZZ-001 containing the
- corrections to lines A203 and A204 for the new transmitter range
(0-160mV). Plant Tours ,
. The inspector made tours of the plant including the control room, the control building, turbine building, and the reactor building to observe
! housekeeping, testing activities and cleanlines .
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- The inspector, noted that APRM A and B are in one compartment of panel l 10-C608. Both channels have to be bypassed at the same time to avoid the ,
- ' possibility of inadvertent reactor scrams. A warning to this effect is posted on the cabinet door. This design feature is common for BWR 4/5 designs and has been reviewed by the NRC in the past.
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6. Exit Interview At the conclusion of the site inspection, on March 22, 1988, an exit interview was conducted 'vith the licensee's senior site representatives (denoted in Section 1). The findings were identified and previous inspection items were discusse i At no time during this inspection was written material provided to the licensee by the inspector. Based on the NRC Region I review of this report and discussions held with licensee representatives during this inspection, it was determined that this report does not contain information subject 10 CFR 2.790 restriction _ _ _ - - - - - - - - - _ _ _ _ _ _
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Attachment A Procedure Review Proc. N Title Rev. No. Approval Date RE-FR.ZZ-008fQ) Verification of Fuel Location 2 02-18-88 RE-RA.BB-001(Q) Recirculation Flow Determination 1 05-12-86 RE-RA.BB-002(Q) Core Flow Determination 1 09-23-86
- RE-RA.ZZ-001(Q) Core Thermal Power Evaluation 1 09-02-86 RE-RA.ZZ-005(Q) Reactor Period Measurement 1 03-10-86 RE-RA.ZZ-005(Q) Reactor Period Measurement 1 03-10-86 RE-SO.RJ-003(Q) NSS Computer Reinitialization 1 11-21-86 and 00-15 program operation RE-SO.SE-001(Q) Traversing Incore Probe System 5 10-07-87 Operation
- RE-ST.ZZ-001(Q) Core Thermal Limits Evaluation 2 07-30-87 Process Computer Method RE-ST.BF-001(Q) Control Rod Drive Scram Time 1 07-16-86 Determination RE-ST.SE-001(Q) APRM Setpoint Surveillance 5 09-23-87
- RE-ST.SE-002(Q) APRM Calibration Surveillance 3 11-26-86
- RE-ST.SE-003(Q) LPRM Calibration 5 01-08-87 RE-ST.ZZ-005(Q) Reactivity Anamoly Check 2 12-15-86
- RE-ST.ZZ-007(Q) Shutdown Margin Demonstration 4 06-25-86 IC-CC.SE-029(Q) Channel Calibration Nuclear 6 09-10-87 Instrumentation System LPRM Gain Calibration
"Used in test result evaluatio ', . . ' ',
Attachment B Review of QA Surveillance Reports Q/A Sur Completion Report No. , Surveillance Activity Date 88-276 Verification of Fuel Location 3-20-88 88-275 I&C Channel Calibration 3-20-88 Redundant Reactivity Control System, Div 1 Channel B, ATWS Recire. Pump Trip 88-273 Reactor Engineering / Core and Spent Fuel 3-20-88 Pool Mapping 88-218 TS Surveillance of LPRMs 3-15-88 (TS 4.7.6.1 and 4.7.6.2c)88-223 Control Rod Removal and Installation 3-04-88 88-24/ Functional Test Nuclear Instr. System 3-13-88 Channel A Source Range Monitor TS Surveillances88-246 Functional Test Nuclear Boiler DIV 2 3-12-88 Channel B21-N691F Reactor Vessel level (trips 1, 2, 8 - CS, RHR, ADS, RCIC)88-264 Time Response Test for Transmitter 3-15-88 1 BBPT-N0780-B21 88-270 Time Res;ense Test for PIdsh- 3-17-88 686D-821 88-093 Fuel Pandling, Off Load of Core 2-25-88 88-242 Fuel Movement, Shuffle and Reload 3-18-88 i ._
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Attachment C Acronyms
APRM Average Power Range Monitor BASE CRIT CODE LPRM strings which may require new data accumulated by TIP System (shown on P-1 printout)
BWR Boiling Water Reactor CMPF Peaking factor at core MFLPD
CPR Critical Power Ratio GAF Gain Adjustment Factor
LPRM Local Power Range Monitor MAPRAT Maximum Fraction of Limiting Average Planar Linear Heat Generation Rate MFLCPR or Maximum Fraction of Limiting MFLCP Critical Power Ratio MFLPD Maximum Fraction of Limiting Power Density
NSS Nuclear Steam System 00 On Demand (Programmatic Output of PMS)
PMS Performance Monitoring System
RPS Reactor Protection System
SDM Shut Down Margin
TIP Traversing Incore Probe ak/k Reactivity, fractional change in neutron population per neutron generatio *
Also defined in NUREG-0544, rev. 2.
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