Text

Monthly Performance Monitoring Audit QSL-PM-96-08, May/June 1996. Encl Partially Deleted
	ML20148E888
Person / Time
Site:	Saint Lucie
Issue date:	05/21/1997
From:	; STATE, DEPT. OF
To:	;
Shared Package
ML20148E886	List: ML20148E881; ML20148E888;
References
	FOIA-96-485 OSL-PM-96-08, OSL-PM-96-8, NUDOCS 9706030298
	Download: ML20148E888 (200)
	v • d • e

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FPL Nuclear Division ppt-Quality Assurance Audit Report i

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MONTHLY PERFORMANCE MONITORING AUDIT i

QSL-PM-96-08 May/ June 1996 l

Audit Team:

L. Bearror J. Hannah L. Panessa P. Roach l

l J. Walls J. Lowery l

J. Voorhees 9706030298 970521 PDR FOIA BINDER 96-485 PDR

AUDIT REPORT QSL-PM-96-08 p

Page 2 of 28 Audit Location:

St. Lucie Plant Date of Audit:

May/ June 1996 Audit Scope:

St. Lucie Plant Performance Monitoring Audit Executive Summary:

Performance Monitoring summaries for QA evaluations completed during the May/ June time frame are included in this report.

The results of these evaluations indicate that the QA Program continues to be implemented at a minimally acceptable level.

Quality Assurance audits and surveillances continue to identify violations of QA Program requirements as noted in Findings 1-3 and the Condition Reports mentioned in this report. The issues identified during this time frame demonstrate continuing weaknesses in St. Lucie programs / procedures and adherence to procedural requirements.. Quality Assurance audits continue to identify discrepancies between St. Lucie procedures and the PSL Final Safety Analysis Report as noted in Finding 1. A random sample of personnel compliance with overtime guidelines indicated that potentially 12% of the plant population were in violation of the overtime guidelines set forth in the Technical Specifications, Nuclear Policy 306 and PSL Administrative Procedures. Quality Surveillances identified a number of examples of inadequate work controls for Maintenance activities conducted during the outage.

Operations Results Periodic reviews of the conduct of operations were conducted including selected technical specification surveillances, Unit I fuel reload, and portions of a Unit 2 cooldown for AFW repairs and a downpower for feedwater regulating valve troubleshooting. Satisfactory performance was noted during these reviews. Conservative decision making and management oversight were noted during several of these evolutions.

Condition Reports - The following Condition Reports issued by Q A during this time period demonstrate weaknesses in maintenance work controls and design control.

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AUDrr REPORT QSlePM-96-08 p

Page 3 of 28 Maintenance Work Controls CR96-Mi34 Calibration of the Emergency Diesel Generator fuel pump input pressure gage was noted as being performed without a procedure in the wbrk package or at the work location.

96-1085 I&C procedures did not specify proper handling and minimum bend radius for storage of incore instruments,(ICIs). ICIs were noted as being stored improperly.

96-1159 The PWO for recoating of the Condensate Storage Tank contained five specific de6ciencies regarding requirements of AP 0010432 Control of Plant Work Orders.

96-1142 The cleanliness level requirements applicable to work being performed on the main electrical generator were unclear.

Desien Control 96-997 Requirements for chemistry sampling contained in a Safety Evaluation for underwater repair of the reactor flange 0-ring surface were not translated into the Letter ofInstruction for the same activity.

96-1434 Several examples of failure to provide correct design inputs for PC/M 009-195 "RPS NI Drawer Replacement" were noted during QA review.

Findings - Three QA Audit Findings are contained in this report.

1.

Inadequate Procedures for Resin Transfer (See Pg.16)

A.

The procedure and methods in use do not implement the system operating description for Blowdown Building resin discharge as found in the FSAR.

B.

The procedures used to changeout typically non-radioactive resins do not provide adequate radiological controls when the resins are radioactive.

C, The procedures in use during a Blowdown Building resin transfer were not being completely followed in that several radiological controls were not in place.

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Page 4 of 28 2

Procedure Non-compliances with Requirements for Control of Breathing Air Stations (See Pg. 20)

Contrary to requirements, HP Techs provided bubble hood respiratory

protection with air supply pressures that exceeded procedure limits. Neither procedure HP-61 or a usable Table 1 of that procedure were available. B A station BB 029 calibration data posted with the machine was not complete. Other stations (BB003 and BB004) were found with expired calibration stickers and incomplete calibration sheets.

3.

Violation of Overtime Guidelines (See Pg. 24)

A.

During the period 5 through 18 May 96,12% of the sampled population exceeded one or more of the overtime guidelines.

B.

Overtime deviation requests are not being filled out and forwarded to the vault as required.

C.

Management reviews of overtime guideline adherence are ineffective O

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AUDIT REPORT QSL-PM-96-08 Page 5 of 28 Operations:

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PMON 96-031.was performed as a follow up to a recent industry event that occurred at Salem Plant.

The subject event identified lack of adequate material control inventories for Special Nbclear Material (SNM) A copy ofthe latest PSL SNM inventory, dated 2/22/96, was compared against the files of receipts and transfer of SNM for the last 10 years to verify that the current inventory is accurate.

SNM rtorage areas were recently inspected during audit QSL-OPS-95-22. Based on the results of these two reviews the inventory in use appears to be accurate. No deficiencies were noted during this

review, Performance Monitor: J. Walls PMON 96-037 was conducted to observe and document activities associated with the performance ofOperating Procedure 2-0110050," Control Element Assembly Periodic Exercise." This procedure satisfies the quarterly Technical Specification surveillance requirements of Tech Specs 4.1.3.1.2 and 4.1.3.1.3. A pre-evolution briefing was conducted by the Unit Two ANPS. Present for this briefing were two RCOs who would be performing the surveillance, the I&C Department Head an I&C Supervisor and two Joumeymen to provide support, the NPS and STA. Also present were oversight personnel who would be witnessing the surveillance activities. It was noted that a third RCO was utilized to perform this surveillance, therefore leaving the board RCO free to focus on his responsibilities.

The pre-evolution briefing was conducted in accordance with Operations Policy OPS-502. All guidelines listed in the policy were sufficiently reviewed by the ANPS. Expected plant annunciators were discussed. Contingency actions to be taken as well as test termination criteria and immediate operator actions contained in Off-Normal Operating Procedure 2-0110030 were covered. Included in the discussion were the various Tech Spec action requirements that could be encountered as a result ofmisaligned or inoperable CEAs. 'Ihe importance of the self verification policy was stressed.

Prior to starting the surveillance procedure, precautions and limits were reviewed.

The procedure permits CEA testing in any order. To accommodate I&C's need to obtain traces of selected CEAs, a group of 29 CEAs was completed first. This data gathering process is accomplished on approximately one third of the CEAs each time the procedure is completed. It was determined that since there was a time gap between work completion and this PMT that an operability concern existed. CR 96-894 and IHE 96-040 were written to address this issue. The surveillance was completed with satisfactory results.

Performance Monitor: L. Bearror PMON 96-025 ivas initiated to evaluate the preparation and conduct of the Ultimate Heat Sink Valve surveillance test. This test is required to be conducted at six month intervals to satisfy PSL Technical

AUDIT REPORT QSL-PM-96-08 p

Page 6 of 28 Specification, Section 4.7.5 for both Units. Procedure OP 0360050, Rev 13 (Emergency Cooling Water Canal-Periodic Test) was the ' governing document for test conduct. The Operations Support Testing Group,'was assigned the responsibility to coordinate and accomplish the activity. QA conducted a review of this procedure with the test engineer to clarify test boundaries, interfacing department responsibilities, and sequencing steps and verification requirements. The extensive j

interface activity of this test prompted a tailboard in the Unit 2 Control Room, for confirmation of j

available personnel and establishment of necessary prerequisites. The ANPS questioned the availability of the Stop Logs and placement equipment for contingency measures. The availability of these items could not be determined at that time. Although this contingency setup is discussed in the body of the testing sequence, it is not presented as a prerequisite in the procedure. This resulted in

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re-scheduling the test for a later date. The test was conducted two weeks later with available contingency equipment on hand, and successful manipulations of the UHS valves. Several recommendations were presented to the Test Engineer for future procedure revision, to lend clarity to the test sequence and denote specifics for signatures of test participants. A procedure revision is expected prior to the next scheduled UHS Barrier valves test in October.

Performance Monitor: L. Panessa Maintenance:

i PMON 96-045 examined dewatering activities for resins oflow activity. Tours of the Radiation Controlled Area (RCA) were conducted to verify compliance with Health Physics Procedures. Liners i

were observed being de-watered on the north side cithe Steam Generator Blowdown Treatment Facility (SGBTF). The process being used did not resemble the equipment and configuration normally used to de-water radioactive resin. Further investigation found that the process being used at the SGBTF was not the responsibility of HP personnel, but was the responsibility of the Maintenance department. The activity was being conducted utilizing procedure MMP-44.0lRev.1, " Steam Generator Blowdown Treatrnent Facility Resin Bed Changeout". Review of other site procedures associated with resin handling and of valid requirements contained in 10 CFR 20,10 CFR 50.59 and the FSAR determined that the movement of radioactive resin in this area was not in compliance with these requirements and that site procedures are not adequate to meet FPL's commitments. See Finding 1.

Performance Monitor: J. J. Walls PMON 96-038 was initiated to monitor and evaluate the conduct of maintenance and testing of the 125VDC Battery Units I A and IB during the Unit 1 Outage. The first part of this monitored activity was the preparation and conduct of the Safety Related Battery Emergency Load Profile Test for Battery Unit I A per MP 0960075. Several Procedure Change Requests and Temporary Procedure Changes were required to be generated to successfully complete the test. QA initiated a PCR to

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f address editorial corrections during the next procedura! update. The load profile test was l

accomplished in a satisfactory manner and reflected a quality efrort by thejourneymen.

The second part of this monitoring activity included observation and evaluation of the replacement i

of a major portion of Battery Unit IB cells, and subsequent testing operations. Three NPWOs were initiated by EM to provide the necessary guidance to conduct this activity. The initial NPWO to replace 41 of the 60 cells, that comprise the Unit IB Battery, required several rewrites before actual I

NPS approval to start was obtained. This was due to inputs by EM Tech Support and SCE after the initial preparation by planning, and difficulties with the transport method of the new cells to the j

battery room. The disassembly of the battery and selection of cells to be replaced was monitored by QA to confirm proper storage of all hardware and identification of the 19 original cells to be re-used during battery re-assembly. The installation of the'60 cells and re-assembly of the seismic racks was accomplished by procedure using controlled and calibrated M&TE. Battery Unit IB was electrically re-assembled and all testing activities were conducted per the applicable NPWOs and governing procedures. All procedures reviewed at the work location were properly stamped and verified to be the latest available revision.

In anticipation ofrestoration of the B side electrical systems, QA conducted a walkdown of the Unit IB Battery following completion of re-assembly and testing activities. It was discovered that five of the cells had the individual cell equalizer (ICE) device installed incorrectly. The method of attaching these devices to the battery intercell connectors was not as required by the manufacturers guidance in the tech manual. This condition was discussed and visually confirmed with the JPN Engineer 1

assisting the EM Group for this project. In addition, a check was conducted of the l A Battery unit for similar conditions and this check revealed that one cell on Battery Unit I A.had the ICE device installed improperly. Condition Report CR96-1231 was initiated to identify the specific cells and prompt immediate review and correction. The ICE devices were corrected on Battery Unit IB, under the original NPWO for Battery re-assembly. PMAI96-06-120 was initiated to correct the ICE device on cell #32 of Unit I A Battery, at the next available opportunity. PMAI96-06-127 was initiated to i

consider procedural guidance to prevent recurrence.

Performance Monitor: L. Panessa i

PMON 96-041 assessed outage activities associated with replacement ofincore instruments (ICIs).

Issues prompting this QA assessment include the unexplained high failure rate (15 of 43 ICIs on Unit I and currently,17 of 56 on Unit 2), high costs for replacement, and potential to result in plant shutdown if a minimum number ofICIs are not available to perform core Technical Specification surveillances.

Outage activities reviewed included receiving and unpacking ICIs, receipt inspection, handling and storage ofiCIs and ICI hub replacement. Three condition reports were generated to address discrepant conditions requiring corrective action. Discrepant conditions identified included the

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Page 8 of 28 potential " ". age new ICIs during handling, and or e for tack welds of unknown origin on the Class 1 ICI hubs. Corrective actions initiated include improved labeling of shipping containers for safety related mateRaldvith precautions for unpacking and handling to prevent damage. JPN. evaluated the j

tack welds on the ICI hubs without identifiable records as acceptable. JPN's evaluation was reviewed and supplemented through QA efforts to include documented technicaljustifications.

QA witnessed HP, RE and I&C activities in Unit I containment during installation of 16 new incore instruments (ICIs) into guide tube cluster assemblies (stalks) in the upper guide stmeture (UGS).

Identified were potential safety concerns, possible causes ofICI failures, and discrepancies associated with the use of breathing air (B A) stations. The work was properly controlled as a hot particlejob with bubble hood respiratory and personnel contamination protection. HP support and job coverage using rotating crews was excellent. QA questioned issues regarding the breathing air (BA) station J

used to support the evolution. Issues involved the BA station (BAB 029) operating procedure availability and noncompliance, and questionable calibration data. These issues were discussed with HP supervision and are addressed by Finding 2.

A follow up of this activity was conducted by QA,7 available filter boxes (not tagged out of service) i were examined for current calibration. The results of the exam found that 2 of the 7 filter box gages were out of calibration. The serial numbers of the boxes were BB003 and BB004. These boxes were 1

locked by chain to preclude use but were not tagged. This does not comply with HP-64, which requires these filters to be tagged out of service. A review of the monthly check of the fdters indicates that the inspection was conducted on June 5,1996 with the gages expiring on June 19.

. These filters were subsequently tagged out of service. This is documented in Finding 2.

An inordinate amount of effort is required to in tall ICIs. The work is extremely difficult and poses a potential for personnelinjury with the current UGS lifting rig platform design. However, workers used caution and absorbed the physical burden to complete ICI work without an injury. In spite of exhausting and awkward work conditions, four I&C crews were able to install all but one ICI, R-4 on Flange 7. Reasonable, cost-effective solutions should be pursued to ease installation, prevent ICI damage, improve ICI reliability, work conditions and ALARA, and lower overall costs. Potential solutions are noted below and were discussed with I&C and RE supervision.

High insertion forces are required to install ICis due to friction forces in thimble tubes with short bend radii, inherent to the design. The following issues and questionable conditions were observed:

Work on the UGS lifting rig platform, located in a partially filled refueling water cavity, requires strenuous labor in awkward body positions. Laying on their side, workers in bubble hoods have to extend their upper torso over the platform edge, using one hand under the platform and one above to apply insertion forces. The platform edge has a 3 inch metallip that sticks-up into a workers rib cage in the under arm area. The worker's head is extended to the side under a handrail looking down and neck strain is possible. The required body

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AUDIT REPORT QSL-PM-96-08 Page 9 of 28 positions reduce leverage to apply forces, that can exceed the available upp-body and arm strength, pushing endurance levels beyorJ reasonable limits, with back strain possible.

During,, work, QA noted a gloved hand and a bubble hood partially enter the. cavity water.

Overall, ICI work presents potential safety concerns, is not human factored; is exhausting, time consuming, and usually outage schedule critical path. A Safety Memorandum Form 1880A was submitted by QA to the Safety Committee to address these safety concerns.

The inadequate size of the deckplate opening over flange locations, and insufficient vertical clearance between flanges and the platform'undeiside, prevents use of the jacking tool to grip an ICI and apply the required force without undue flexure.

j Damage to 2 new ICIs (N-15 and N-17, on Flange 2), due to excessive fler.cre, may have occurred which could degrade their future reliability. Bending ICIs to less than a six inch radius can result in rhodium detector wire damage and premature ICI failut e, a possible root cause for current high failure rates. The first I&C crew worked hard to unsuccessfully install N-15. N-15 was removed for another crew to install later, but appeared kinked in the region where insenion stopped just above the flange. During insertion of the next ICI, N-17, the crew appeared exhausted and mentally fatigued which resultedin N-17 flexing out from under the deckplate, when it hit a high friction point during insertion. The resulting three bends exceeded the CE design limit (a nunimum 6 inch bend radius) specified to prevent damage to the rhodium wire detectors within the pendaflex sheath.

QA noted to I&C personnel the need to slow down and use caution to prevent ICI damage.

Proper caution was evident during insertion of the next ICI by the first crew. The fourth crew, starting thejob fresh, was able to install N-15.

I&C was unable to install ICI R-4 after multiple attempts. ICI R-4 appeared to have an inflexible tip preventing insertion through the curved thimble tube below the stalk on Flange

7. ICI R-4 is a Westinghouse Parssel non depleting detector which is a new design supplied as I of 2 lead demonstration ICIs being considered for future replacements.

When the bullet nose extension was removed from Flange 4, ICI B-IS we found with the dust cap removed and water in the connector. Water / contamination can degrade ICI reliability and better verification ofdustcap installation is needed to prevent recurrence. The connector was tamp dned with a cloth and requires cleaning and drying per the Tech Manual i

8770-8575, Rev. 3. I&C plans to clean and dry the B-15 connector prior to ICI reconnection.

Based on observations, potential reasonable solutions and factors to consider include:

Currently, shielding has to be pulle'd back to gain better access to the plate mounted on the bullet nose locking rod which holds ICIs by the seal plugs to the locking rod. The current

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UGS platform deckplate opening is small and impedes inserting ICI seal plugs below the plate j

for securing to the rod, taking additional time, worker effort and results in a higher dose.

Provide a design change evaluation and documentation to authorize cutting the deckplate, yielding a 2 foot square access cover over each flange location. Provide supporting hardware and fasteners to maintain the structural integrity of the platform and hold the covers in place when not removed. This work can be completed with the UGS lift rig removed and located in a safe low dose rate area.

Open access holes will make work more efficient and safe, and allow use of the jacking tool, but requires temporary removal of lead shielding. General area dose rates to workers will I

temporarily increase from a minimum of 60 mR/hr to a mrximum of 300 mR/Hr on contact, based on the most recent HP area survey. However, based on the current platform design and evolutions observed, workers are potentially getting the same or more dose because of the i

time and effort required to complete the job.

j The costs ofnew ICIs is $30-40K each. Based on the currently high unexplained failure rate at PSL (15 of45-Unit I and 17 of 56-Unit 2), ICI replacement costs, lost critical path time, j

and impact to plant personnel and radiological resources, a design change should be readily justified as cost effective and improving plant safety.

The following positive observations were noted:

I&C personnel are commended for their work and can-do attitude, which exceed reasonable expectations to accomplish such ajob in less than adequate conditions.

Good FME controls were used on the UGS platform. Tools were lanyarded, bullet nose extensions were tied-off cut tie-wraps and tags removed were immediately placed in a trash bag. Tools and materials were placed in a plastic bag when not in use.

I&C Procedure 1400023, Rev. 8, was repeatedly referred to by I&C personnel when checking the flange position for the next ICI to be installed. Checks compared information on the ICI identification tag to the flange number and thimble position against the procedure table.

Good FME controls were applied during cavity monitoring and logging of material movement into and out of the cavity area.

HP surveys and floor swabbing was noted for reducing the size of the hot parb.le boundary area. This increased access for Q4 and RE personnel to better observe evolutions.

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p Page 11 of 28 Good intra-departmental communications and teamwork between I&C, HP, RE and good interaction and timely response to QA questions.

Performance Monitors: P. A. Roach, J. Hannah, J. J. Walls PMON 96-042 was initiated to monitor and evaluate the activities associated with 2C AFW Pump over speed trip investigation and subsequent repair / modification. Condition Report CR96-1300 was prompt assessment and corrective action. Nuclear Problem Report (SCE 96-027) clearly described the conditions and sequence of the event and presented 'a logical fault tree anslysis for determination of probable root cause. Specific corrective measures were implemented to prevent recurrence. PC/M 96-099 was developed to move the warmup line supply to the low point areas upstream of the steam supply valves. PMAls# PM 96-147 and 96-148 were initiated to track follow up test data acquisition.

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QA monitored the work activities for the installation of the pre-fab piping sections for PC/M 96-099, (2C AFW Pump Turbine Warmup Line Modification). Clearance Order 2-96-06-050 was in place.

NPWOs 62/7029 and 62/7030 were reviewed at the work site to assure current work status and appropriate welding documentation was on hand. Observed the welding activities for confirmation

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ofweld rod control, adherence to welding standards WPS 089003 for the carbon steel portions and WPS 068003 for the dissimilar portion. Certification of welders was confirmed for the specifications being used. Cleanliness controls for piping internah were adequate to assure that the proper level of cleanliness was maintained throughout component installation. Monitored the NDE inspection activities conducted by QC to approved procedure (TS 9.5, PT-1 Method 2). QC certification was confirmed for the inspector using this NDE technique. QA requested JPN confirmation that the use of a 3/4" threaded mechanicaljoint was allowed by ASME Code for this application, within the modification. Review of the ASM Code for Class 2 threaded connections does allow this type of assembly termination up to 1500# high energy systems.

Following completion of piping modifications to the warmup lines, QA conducted a walkdown of the work areas to confirm preparations for the upcoming Post Maintenance Testing activity, upon availability of secondary steam. Both newly installed valves were properly locked open and uniquely identified as per PC/M. QA observed an unsatisfactory condition of the electrical seal flex for SE 2 (warm up valve for S/G 2A to AFW Pump 2C). The seal flex was pulled out of the connector at the condulet and required repair. With the assistance ofI&C Supervision, W/R 96010244 was initiated and a PWO tag was hung to identify the condition. W/O 96015312 was issued and this condition was corrected prior to any PMT activity.

The in service leak test of the installed warmup piping was successfully accomplished allowing l

preparations for Post Maintenance Testing to commence. QA monitored the implementation of OP j

l 2-070050 rev 41, recently revised including TC 2-96-100. The conduct of the PMT, per Data Sheet C, was accom'plished per procedure with good communications between the local Operation personnel and the Control Room Operator. Valve alignment and independent verification was

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Page 12 of 28 observed 4 : S onducted per established procedural guide:ines. Upon satisfactory completion of the PMT per Data Sheet C, QA monitored the performance of the flow tests of the 2C AFW Pump and its valves per Data Sheet D. Activities were accomplished per procedure with satisfactory results.

Performance Monitor: L. Panessa Services /Engineerine/Other PMON 96-033 was initiated to insure Plant compliance with overtime controls specified in Technical Specifications 6.2.2.f and Administrative Procedure AP0010119, Rev.14. This evaluation was conducted by reviewing security gate log entries and exits from the protected area for a random sampling of personnel currently badged at the St. Lucie site. Selected personnel were drawn from a population of 16 plant departments and eight different contractor companies all of which have the potential to perform safety related work activities. Individuals examined were selected using a random number generator.

Interviews were conducted with management personnel to examine consistency in understanding and implementation of overtime guidelines. Records of overtime deviation requests were reviewed.

Interviews conducted indicate that managers and direct reports are reviewing time sheets each pay period to ensure compliance with overtime guidelines. In addition, personnel have been instructed to report in advance any anticipated overtime that would exceed the guidelines. Management interviews revealed a consistent interpretation of the overtime limits. As currently implemented the overtime policy allows turnover time of 30 minutes before and after each shift in addition to the i

maximum limits stated in the technical specifications. This understanding is contained in a maintenance memorandum dated 20 April ;992.

Other than this Mechanical Maintenance memorandum, other plant wide guidance defining shift turnover time was not located during this audit. Consistent implementation of shift turnover time was not found when time records were reviewed.

The target population contained 1,572 badged personnel. A sample size of 100,6.4% of the population, was randomly selected. Security gatelogs were obtained for the period, 5 through 18 May 96, inclusive. Allowing 30 minutes for a lunch break and applying the previously discussed definition of shift turnover to the criteria in AP0010119, the following maximum thresholds for l

allowed hours on site were established:

1.

No more than 17.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months in 24 1.

No more than 27 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months in 48 1.

No more than 82.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months in 7 days 1.

An 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months break exists between work periods (including shift turnover).

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AUDIT REPORT Q!iL-PM-96-08 Page 13 of 28 No violations were identified concerning item number (1) above. There were no substetial violations ofitem (4)._There were numerous violations ofitems (2) and (3). Specifically,12% of the sample population exce6ded the criteria at least once, while 8% exceeded the criteria at leas twice and in some cases throughout the sample period. Additional discussion related to this problem is provided in Finding 3.

Performance Monitor: B. Lowery Summary of Ouality SurveIdance Results: The following Quality Surveillance Reports were completed as part of the augmented QA effort during the PSL-1 outage. No QA Findings were noted during these reviews.

QR Nos.

Surveillance Subjects Results96-022 Review Completed PC/Ms to determine if Satisfactory Procedures affected have been revised 96-030 Refueling Verification Satisfactory 96-038 Surveillance ofTarget Rock Solenoid Valve Unsatisfactory CR96-1139

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Testing 96-056 Surveillance of the IB Turbine Cooling Pump Satisfactory 96-057 Calibration of the Diesel Generator Fuel Pump Unsatisfactory CR96-1034 In-put Pressure Gage 96-058 QA Surveillance of Scaffolding in the Unit 1 Satisfactory Turbine Building 96-059 Surveillance of Freeze Seal for LPSI Headers Satisfactory 1A2 & IB2 96-060 Surveillance of EDG Indicating Light Unsatisfactory CR96-1073 Modification Replacement Part Adequacy 96-061 QA Surveillance of Safety and Fire Protection Satisfactory Issues on May 24,1996 96-062 Conduct ofInfrequent Evolution, Repack of Satisfactory Class 1 RCS Boundary Valve V1234 on the Backseat. Task accomplistied 5/22/96 dayshift m

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Page 14 of 28 96-063 Wyle Laboratories Site Services for Snubber Satisfactory Testing

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96-064 Disassembly, repair and installation of Motor Satisfactory Operated Valves, MV 07-1 A & IB for RWT Feed to LPSI, HPSI & Containment Spray Pmps96-065 ACV 3657 Satisfactory 96-066 V3652 Satisfactory 96-067 Surveillance ofIn-Plant Clearance Controls Satisfactory 96-06b Accomplishment of 72 Hour Period to Fuel Satisfactory Handling Checks of the Refueling Machine 96-069 FME Controls ofReactor Cavity Unsatisfactory - Open Finding QSL-PM-96-06 F.

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Findine No.l.

Inadequate Procedures for Resin Transfer Findine: " M.

The procedure and methods in use during blowdown building. resin transfer did not implement the system operating description for Blov/down Building resin discharge as found in the FSAR.

B.

The procedures used to changeout typically non-radioactive resins do not provide adequate radiological controls when the resins are radioactive.

C.

The procedures in use during a Blowdown Building resin transfer were not being completely followed in that several radiological controls were not in place.

Criteria :

10 CFR 50.59 " Changes, tests and experiments,"

"(a)(1) The holder of a license authorizing operation of a production or utilization facility may (I) make changes in the facility as described in the safety analysis report, (ii) make changes in the procedures as described in the safety analysis report, (iii) conduct tests or experiments not described in the safety analysis report, without prior Commission approval, unless the proposed change, test or experiment involves a change in the Technical Specifications incorporated in the license or an unreviewed safety question. (2) A proposed change, test, or experiment shall be deemed to involve an unreviewed safety question (I) if the probability ofoccurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or (ii) if a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or (iii) if the margin of safety as defined in the basis for any technical specification is reduced."

Technical Specifications Paragraph 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33,

,i Revision 2, February 1978, and those required for implementing the requirements of NUREG 0737.

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QSlePM-96-08

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Rey;'"ary Guide 1.33

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R.' Procedures for the Control of Radioactivity

b. Solid Waste System (1) Spent Resins and Filter Sludge Handling i

I 10 CFR 50 Appendix B V.

Instructions, Procedures and Drawings Activities affecting quality shall be prescribed by documented instructions, procedures or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instmetions, procedures and drawings. Instructions, procedures and drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.

Discussion:

During Radiation Controlled Area tours it was noticed that seven radioactive material shipment liners were located adjacent to the north side of the Steam Generator Blowdown Treatment Facility. The liners contained resin from the blowdown ion exchangers and were in the process of being de-watered for eventual shipment offsite as low level radwaste. The condition of the area was not what is usually observed during de-watering of radioactive resins. Discussions with HP personnel faund that Mechanical Maintenance was responsible for this evolution.

The FSAR was consulted for the description of the system and it was found that the system is not being operated as described in the FSAR. The FSAR states on page 10.3-8, Am.10-7/91, paragraph 10.4.7.2 "... Spent ion exchange resins are gravity fed to a spent resin storage tank for temporary storage prior to disposal as a solid waste..." At present the procedure does not utilize the spent resin tank. The procedure uses temporary hoses and pumps to transport the resin through the Blowdown Building to liners setting on the ground or on wooden pallets.

The procedure in use during resin handling was MMP-44.0lRev.1, " Steam Generator Blowdown Treatment Facility Resin Bed Changeout." This procedure and PWO 96012711 that initiated the procedure were reviewed. The following discrepancies were identined:

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AUDIT REPORT Q5fePM-96-08 Page 17 of 28 1.

Paragraph 5.2 " Resins will be disposed ofin accordance with HP inste-tions" MMP

_ 44.01 was the only procedure in the work area. No HP instructions were in the work g,ackage.

2.

Paragraph 5.3 "All resins will be treated as radioactive." - The precautions for normal radioactive resin transfer were not observed at the work area. Portable curbing was not in place for the liner to contain any spills, leak testing is not conducted on the portable equipment and containment mechanisms were not in place on hose connections. None of the components in'use were marked indicating that radioactive mate:ials were being handled except the discharge of the hose and the liner itself. A Rad. Material Tag was put on the pump after the problem was discussed with HP.

3.

MMP 44.01 lacks many of the precautions for handling potentially highly radioactive material. The pump and associated flexible hoses are not checked for integrity. The procedure does not require containments to be installed around the connections to prevent leakage from contaminating the area.

Although the resin radiation levels in this case were not high, the potential exists for the resin to be at the same levels of activity as the resin in the RAB. The controls for handling resin should be consistent. At present there is resin on the ground near this area. Discussions with Health Physics indicates the resin is not radioactive, but the presence of the resin dues not indicate adequate housekeeping.

PWO documentation for other recent resin transfers from the Blowdown Building were reviewed. (6/2/95,11/9/95 and 11/15/95) with similar results. In addition, it was noted that additional details of this evolution are not described in MMP 44.01 such as pumping the resin into 55 gallon drums and transporting them to the RAB to be dumped into the Waste Ion Exchangers. These steps were also not included in the PWO work instructions to ensure that the requirements of transporting ofitems in the RCA would be met.

Further review of PSL resin handling was conducted. Procedure OP 0700026 Rev.12

" Condensate Polisher Filter Demineralizer - Normal Operation" was reviewed for considerations of radioactivity in the condensate system during normal or abnormal operations. This procedure contains only a precaution in paragraph 4.8 that upon detection ofradio nuclides in the condensate system to open the by pass valve and isolate the system.

j No other radiological instmetions are contained in this procedure. Condensate polisher resins typically exhibit minute traces of radioactivity and are disposed of as radioactive material. A Health Physics Hold Point to sample the resin prior to any operations is not prescribed in the procedures. This step would direc,t personnel in the proper methods of disposal depending on the r6sults of the sample.

AUDIT REPORT QSL-PM-96-08 p

Page 18 of 28 1

l A Condition Report ( 96-1283 ) was issued immediately upon discovery of this Finding to facilitate immediate corrective action. The Health Physics Supervisor stopped the work at the Blowddn Building when notified by QA of the conditions identified.

This issue represents an example ofPSL procedures being executed in a manner not described in the St. Lucie Safety Analysis without benefit of a 50.59 review. In addition, it provdes an example of non-conservative approach to handling of potentially radioactive materials.

Recommendntions: This Finding must be resporided to in the manner described in the cover letter.

The following recommendations are made for your censideration:

A.

Review current methods of resin transfer and compare to the FSAR. Provide a safety analysis, adequate facilities as designed. and or procedure revision to bring these i

processes into compliance with the FSAR. Check other activity in the Blowdown Building for compliance with the FSAR and other design documents.

B.

Clean up the Blowdown Building area.

C.

Provide an HP Hold Point in all site resin transfer procedures before the resin is moved to determine the need for extra precautions due to radioactivity.

l D.

Revise the procedures and provide the needed precautions to preclude contamination of personnel and property. Consider the level of prevention used in the HP procedures for resin handling at the RAB.

E.

Provide training for those personnel that will utilize the new procedure.

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AUDIT REPORT QSL-PM-96-08 ppg.

Page 19 of 28 Findine No. 2 Procedure Non-compliances with Requirements for Control of Breathing Air Stations Findine:

Contrary to requirements, HP Techs provided bubble hood respiratory protection with air supply pressures that exceeded procedure limits. Neither procedure HP-61 or a usable Table 1 of that procedure were available. B A station BB 029 calibration data posted with the machine was not complete. Other stations (BB003 and DB004) were found with expired calibration stickers and incomplete calibration sheets.

Criteria:

1.

JNO-HP-2.0," Radiation Protection Manual," Revision 3 Paranraoh 4.5.3.3 Respiratory protection equipment shall be used under a respiratory protection program which includes the following provisions: d. Written procedures regarding selection,... and testing of respirators, including testing for operability immediately prior to each use;..."

2.

Health Physics Proc.-61, "Use or Respiratory Protective Equipment," Rev. 3 Paracraoh 514 "All pressure gages used for breathing air applications shall be calibrated at a frequency not to exceed 18 months."

Paragraoh 5.16 (Annotated as a non-regulatoly commitment per a Respiratory Flow Determinatior) Study, R. B. Somers, October 10,1985)

"The air manifold pressure settings and corresponding hose lengths must comply with the manufacturer's recommendations. These recommended settings and lengths are summarized in Table 1 Supplied Air Respiratory Protection Equipment Hose Length and Requirements."

Paracraoh 5.17

" Prior to using a breathing air respirator or hood, HP shall verify that service air is monitored for carbon monoxide."

3.

HPP-64, Rev. 3," Operation of Breathing Air Purification Systems"

AUDIT REPORT QYL-PM-96-08 j

p Page 20 of 28 Paragraoh 7 5-4

_ Verify calibration due dates on all gages (Fig.1: 10, 15, 16) and CO monitor.

,Any unit that will be exceeding the calibration due date shall be. tagged OOS prior to the date of expiration.

4.

Instniment and Control Procedure 1220056, " Calibration of Carbon Monoxide Monitors," Revision 2 Paracranh 9.3.11

" Attach a copy of the completed data sheet to the unit being tested."

5.

QI 12-PR/PSL-2 Rev. 20, " Control and Calibration of Measuring and Test Equipment" Parazraph 5 3 Control and use ofM&TE "1. Tagging:

A. Calibration Status - a Calibration Sticker is attached to each item of M&TE..."

Discussion:

QA reviewed use of the breathing air (B A) stations used to support ICI installation activities on the UGS lifting rig. Issues were identified involving B A station (BB 029) operating procedure availability and noncompliance, and incomplete CO monitor calibration data sheets. Each issue was discussed with the peak shift HPSS, Sr. HP Tech responsible for B A station maintenance and certification, and the HP Department Head.

The following deficiencies were observed:

It was observed that HP Techs incorrectly established 60 psig air supply settings for the first 3 ICI crews supplied with bubble hoods. The correct 45 psig setting was establithed for the i

last crew after obtaining a new copy of Table 1. An adhesive label depicting HP-61, Table l

1, posted on the station (BB 029) inside cover, was torn in half so that the relation of hose l

length to air pressure setting for the hose lengths in use was missing. A copy of procedure i

HPP-61 was not available.

Calibration stickers within BB 029 were nonstandard FPL stickers. A blank sticker on the CO monitor was inscribed with the unit serial number and a date (9/96), but no entry for the cal due date. Another sticker on the inside cover indicated last date calibrated for the station

t AUDIT REPORT QSlePM-96-08 b.

Page 21 of 28 as 10/27/94. The air pressure gauges were posted with a valid FPL stZ.er and current calib, ration data.

\\

A signed original, stamped COPY, Data Sheet C ofI&C calibration procedur# 1220056, Rev.

2 was placed in the BA station. This data sheet was incomplete but indicated that a CO monitor calibration was performed on 5/15/96. The data sheet was not signed as " Reviewed l

l By", did not identify the ppm of the Calibration gas used or the location. Step 9.3.8 requires l

that I&C place "a copy of the comoteted data sheet" with the unit being tested.

l A follow up of this activity was conducted on June 25,1996 by QA. 7 available filter boxes ( not tagged out of service ) were examined for current calibration. The results of the exam found that 2 of the 7 filter boxes were out of calibration. The serial numbers of l

the boxes were BB003 and BB004 (6/19 &20/95 date of calibration). These boxes were i

locked by controlled lock and key to preclude use but were not tagged out of service. This does not comply with HP-64, which requires filters out of calibration to be tagged out of service. The calibration sheet for the CO monitor was found to be incomplete. The sheet did not have the Reviewed by and Date blanks completed.

It should be noted that the gage calibrations are conducted annually, more frequently than the i

18 months period required, but the procedure requirements do not acknowledge this I

conservatism.

I In support of continuing the ICI work, a Sr.HP Tech provided a record of calibration due dates for j

all BA stations; BB 029 was listed as calibrated on 5/15/96. Calibration data inconsistencies were discussed with the Sr.HP Tech, who has the responsibility for BA station maintenance and certification. It was indicated that the filters are stored locked and upon release they are checked out by the HP procedure HP-64. This procedure is included in the boxes but does not include the information provided in HP-61 for pressure setting based on hose length.

These instances represent examples of failure to follow procedures in the manner expected at St.

l Lucie. In addition, these issues represent a lack of attention to detail regarding HP practices and industrial safety.

Recommendations: This Finding must be responded to in the manner described in the cover letter.

The following recommendations are offered for your consideration:

1.

Emphasize procedural compliance expectations to HP personnel.

l 2.

Review procedures HP-61 and JIP-64 and consolidate the valid requirements. These proceddres could be combined.

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AUDIT REPORT QSI FM-96-08 ppg -

Page 22 of 28 i

I 3.

Provide. training for all of those personnel that are part of this process. This training should l

include I&C, HP and the respirator users.

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AUDIT REPORT QSL-PM-96-08 p

Page 23 of 28 Findine No. 3 Violation of Overtime Guidelines Findine:

A.

During the period 5 through 18 May 96,12% 6f the sampled population exceeded one or more of the ovenime guidelines.

B.

Ovenime deviation requests are not being filled out and forwarded to the vault as required.

C.

Management reviews ofovertime guideline adherence are ineffective.

Criteria:

PSL % Technical specifications 6.2.2.f Paragraoh 2. In Part

".......In the event that unforeseen problems require substantial amounts of ovenime to be used, or dunng major plant modification, on a temporary basis the following guidelines shall be followed:

1.

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

i 2.

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, j

nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding shift turnover time.

3.

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift turnover time.

j

. Any deviation from the above guidelines shall be authorized by the Plant, General Manager or his deputy, or higher levels of management...... Controls shall be included in the procedures such that i

individual overtime shall be reviewed monthly by the Plant General Manager or his designee to assure that excessive hours have not been assigned."

Note: These same restrictions are put fonh in Nuclear Division Policy NP-306.

AP0010119 " Overtime Limits for Plant Personnel" Rev.14 Para.8.2 "Ihe nuclear plant personnel in all departments shall be l

covered by these instructions."

1 l

AU,DIT REPORT QSL-FM-96-08 b.

Page 24 of 28

)

Para.8.4 " Deviation froni the ovenime guidelines shall be approved by the Vice President-St. Lucie Plant, Plant General Manager, Services Manager."

Para. 8.5 "Each department head is responsible to perform a review that will ensure (on a monthly basis) that excessive overtime hours have not been assigned."

Discussion:

A sample population of 100 plant personnel was selected from a total target population of 1,572 badged personnel from 16 plant depanments and 8 contractor organizations. Individuals selected for review were identified using a random number generator and represented 6.4% of the target population.

Gatelogs were requested for the period of May 5-18,1996. Daily time was totaled and entered into an Excel Database.

Allowing 30 minutes for a lunch break and applying the established allowance for shift turnover to the critcria in AP0010119, the following maximum thresholds for allowed hours on site were established:

1.

No more than 17.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months in 24 2.

No more than 27 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months in 48 3.

No more than 82.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months in 7 days 4.

An 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months break exists between work periods (including shift turnover).

No violations were identified concerning item number (1) above. There were no substantial violations ofitem number (4). There were numerous violations ofitems (2) and (3 ). A total of 9 personnel exceeded the limit ofl82.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months within 7 days. In addition 4 personnel exceeded the 26 hour3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months within a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months limit. Specifically,12% of the selected population exceeded the criteria at least once, while 8% exceeded the criteria at least twice and in some cases throughout the sample period. If extrapolated to the entire plant population, these violations potentially represent a significant number of personnel on site exceeding the ovenime guidelines.

Payroll time sheets / cards were reviewed for individuals noted in exuss of the ovenime limits via the gate log review. It was noted that in some cases time sheets did not reflect the hours spent on site. In other cases,2 to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months a day were annotated as. shift turnover on the time repons.

AUDIT REPORT Q5L-PM-96-08 p

Page 25 0f 28 l

AP0010119 Rev 14, requires that a form entitled " Request To Deviate From Ovenime Guidelines" be filled out for all individuals exceeding the ovenime i

f guidelines. There were no forms on file in the vault specific tq the period of

~

May 5-18,1996.

I Management personnel from several departments were interviewed to determine how the monthly review of overtime required by the technical specifications and AP0010119 are conducted. Typically these reviews consist of a review of hours reported to payroll. Based on violations identified above,

~

this method of conducting overtime reviews is not effective at identifying individuals who exceed the guidelines Exceeding the overtime guidelines in this manner exhibits disregard for the requirements of the Technical Specifications and increases the probability of errors and accidents due to fatigue.

Recommendation:

Your response must address the finding in the manner described in the cover letter. The following recommendations are offered for your consideration:

1.

Enforce the technical specification requirements as outlined in Administrative Procedures 0010119, Nuclear Policy 306 and St. Lucie Policy 202.

2.

Develop an alternative method for conducing the periodic i

management reviews of adherence to the overtime guidelines.

3.

Ensure that overtime requests are completed, authorized and i

. forwarded to the vault as required.

4.

Establish standard site wide policy for the utilization and recording of shift turnover time.

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Page 26 of 28 1

Audit

Participants:

Name Department / Group PMON No.

M. Wachtel EM 96-038 M. Migliaro JPN 96-038 B. Griner EM 96-038 R. Coleman EM 96-038 R. Pitts EM 96-038 R. Baker EM 96-038 R. Poner EM 96-038 J. Marchese Maintenance 96-041, 042 R. Olson I&C 96-041 F. Huber ICM 96-041 E. Ordway I&C 96-041 R. Holdren I&C 96-041 T. Beebee I&C 96-041 R. Raborn I&C 96-041 L. Albright I&C 96-041 j

H. Buchanan HP 96-041 V. Munne HP 96-041 B. Sexton HP 96-041 R. Ellis I&C 96-041 j

C. O'Farrill Engineering 96-041 R. Klein RE 96-041 i

W. Mead RE 96-041 J. Hoge PE

'96-041 D. Banks PE 96-041 D. Quality Stores96-041 M. Ullman Stores96-041 D. Komstadt Stores96-041 A. DeGrasse CE 96-041 D. Denver Engineering 96-041 J.Zudans Engineering 96-041 T. Skiba Engineering 96-041 M. MacLeod SGRP 96-041 W. Bladow QA 96-041 J. Priola JPN,96-042 l

AUDIT REPORT Q3L-FM-96-08 Page 27 of 28 l

Audit Participants. Con'd:

l Name,'

Department / Group PMON No.

i 1

o B. Green SCE 96-042 L. Neely ICM 96-042 M. McCardel OPS96-042 I

D.Jacobs MM 96-042

)

R. Steel QC 96-042 R. Miller QC 96-042 C. Burton Facilities96-042 i

H. Buchanan HP 96-042 C. Wood S&C Eng.96-042 B. White Stores96-042 l

G. Bailey Security 96-042 P. Fulford OPS S&T 96-042 1

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AUDIT REPORT QSL-FM-96-08 i

@b.

Page 28 of 28 Pre-Audit 'E:*5crition:

^

Location:

St. Lucie Plant Date:

. May 1,1996 Post-Audit Conference:

Location:

St. Lucie Plant Date:

July 8,1996 Summary of Post-Audit Conference:

The results ofthe Performance Monitoring activities inclusive of the findings and recommendations were discussed with the attendees. Plant personnel agreed that the Findings were valid and that J

corrective action would be taken to correct the noted deficiencies. The Site-Vice President reiterated his expectations for procedural compliance and personal accountability.

Personnel in attendance were: A. Stall, K. Metzger, J. Walls, J. Lowery, J. Scarola, R. Ball, R.

McCullers, J. Voorhees, E. Weinkam, W. Bladow, T. Johnson (USNRC)

Location of Audit:

St. Lucie Plant Accompanvine Auditors:

L. Bearror, J. Hannah, L. Panessa, P. Roach, J. Walls, J. Lowery, J. Voorhees 4

4 Principal 1

2','c':ld u, as 7letu Voorhees date Supervisor - PSL

[

Findine No.1 A. During the period 5 through I8 May 96,13% of the sampled population exceeded one or more of the overtime guidelines.

l l

B. Overtime deviation requests are not being filled out and fonvarded to the vault as required.

+

C. Management reviews of overtime guideline adherance are e

ineffective.

Criteria:

PSL 1/2 Technical specifications 6.2.2.f Paranraoh 2. In Part

".......In the event that unforeseen problems require substantial amounts of overtime to be used, or during major plant modification, on a temporary basis the following guidelines shall be followed:

1. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more thari 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding shift turnover time.

3. A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift tumover time.

Any deviation from the above guidelines shall be authorized by the Plant, General Manager or his deputy, or higher levels of management,...... Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant General Manager or his designee to assure that excessive hours j

have not been assigned."

AP0010119 " Overtime Limits for Plant Personnel" Rev.14 Para.8.2 "The nuclear plant personnel in all departments shall be covered by these instructions."

' Para.8.4 " Deviation from the overtime guidelines shall be approved by the Vice President-St. L,ucie Plant, Plant General Manager, Services Manager."

Para. 8.5 "Each department head is responsible to perform a review that will ensure (on a monthly basis) that excessive overtime hours have not been assigned."

i

Discussion:

A sample population of 100 plant personnel was selected from a total target population of 1,572 badged personnel from 16 plant departments and 8 cc. mctor organizations. Individuals selected for review were identified taing a random number generator and represented 6.4% of the target population. Gatelogs were requested for the period of May 5-18,1996. Daily time was totaled and entered into an Excel Database.

Allowing 30 minutes for a lunch break and applying the established allowance for shift tumover to the criteria in AP0010119, the following maximum thresholds for allowed hours on site were established:

1.

No more than 17.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months in 24 2.

No more than 27 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months in 48 3.

No more than 82.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months in 7 days 4.

An 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months break exists between work periods (including shift tumover).

No violations were identified concerning item number (1) above. There were no substantial violations ofitem number (4). There were riumerous violations ofitems (2) and (3 ). A total of 9 personnel exceeded 82.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months within 7 days, with 4 individuals exceeding the limit more than twice. 'ln addition 4 personnel exceeded the 26 hour3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months within a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months limit. Specifically,13% of the population exceeded the criteria at least once, while 8% exceeded the criteria at least twice and in some cases throughout the sample period. If extrapolated to the entire target population these violations represent a significant raber of personnel on site exceeding the overtime guidelines.

i AP0010119 Rev 14, requires that a form entitled " Request To Deviate From Overtime Guidelines" be filled out for all individuals exceeding the overtinie guidelines. There were no forms on file in the vault specific to the period of May5-18,19 96.

Management personnel from several departments were interviewed to determine how the monthly review of overtime required by the technical specifications and AP0010119 are conducted. Typically these reviews consist of a review of hours reported to payroll. Based on violations identified above, this method of conducting overtime reviews is not effective at identifying individuals who exceed the guidelines.

Recommendation:

Your response must address the finding in the manner described in the cover letter. The following recommendations are offered for your consideration:

-.. -. ~. -.

I f

1 I

i l

i 1.

Enforce the technical specification requirements as outlined in

]

Administrative Procedures 0010119, Nuclear Policy 306 and St.

i Lucie Policy 202.

j i

1 2.

Develop an alternative method for conducting the periodic l,~

management reviews of adherance to the overtime guidelines.

l

_ s' 3.

Ensure that overtime requests are completed, authorifed and j

forwarded to the vault as required.

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ST. LUCIE Pl. ANT AD5tlNISTRATIVE PROCEDURE NO. 0010119, REVISION il OVERTIME LIMITATIONS FOR PLANT PERSONNEL FIGURE 1 REQUEST TO DEVIATE FROM OVERTIME GUIDELINES 1

TO: Vice President - St. Lucie Plant / Plant General Mgr/ Services Mgr.

+

5!.Bo!9f, FROM:

R C.OLsoM DA

SUBJECT:

DEVIATION FROM OVERTIME GUIDELINES FOR (NAMES):

/R14 ORIGINATOR Request the below listed individuals to exceed the following overtime guidelines Greater than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight Greater than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period Greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period Y

Greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day period A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (including shift turnover time) 1 SCOPE OF WORK, I

BASIS FOR DEVIATION O Personnel have unique qualification / training O Sufficient rest will be provided O Turnover of petsonnel would leopardize quality of work

@ Excessive lost time would occur and sufficient testing will ensure quality of actMty S Other L s are Pe.et-e micrm u Saw=evissa DETAILED EXPLANATION OF BASIS FOR DEVIATION o f-Mst At1 ATimaa Am.an "rEEc. r rase. OF L)B.1) MOC.Leme. h3e rsbJmga.) rMyraii UpG 2Ab c UIA PerA bo9 ' 19c EEs='en o wns bE:tAtL tb 111ATIEde17&MC.

fEsw d. A AkD mar 4AGEtHEe.6* Ot)A:P Wtaf+1-APPROVAL Approved by St. Lucie Plant / Plant Gen. Mgr. / Seewees Mgr. (cirds one)

V ROUTING Original to Nuclear Records Vault.

}

j P:g) 5 of 5 1

1 ST. LUCIE PLANT

~

ADMINISTRATIVE PROCEDURE NO. 0010119, REVISION ~14 i

OVERTIME LIMITATIONS FOR PLANT PERSONNEL

/

FIGURE 1 REQUEST TO DEVIATE FROM OVERTIME GUIDELINES TO: Vice Pre,sident - St. Lucie Plant / Plant General Mgr/ Services Mgr.

FROM:

2. C 04SCAJ DATE 6 - /3'- %

L

/R14

SUBJECT:

D lATION FROM O -

MEGI NE FOR NAM

/R14 ORIGINATOR Request the below listed individuals to exceed the following overtime guidelines

' Greater than 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months straight Greater than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period I

Greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months penod N

Greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day period A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (including shift turnover tirne)

SCOPE OF WORK

~ '

BASIS FOR DEVIATION O Personnel have unique qualification / training-O Sufficient rest wis be provided O ' Tumover of personnel would jeopardtze quality of work 3 Excessive lost time would occur and sufficient testing will ensure quality of actMty 0 Other DETAll.ED EXPLANATION OF BASIS FOR DEVIATION

. soepeer-Ihr I-tue,ar4e h m e w descue

-3 iluir z - s.co tr u - / r -tr r o.

EE/4# e I A,w cE6mcs, fEcostssamnds APPROVAt.

Approved by uns Q oeng../ somees ugr. teme one) vlee ROUTING Original to uclear Records Vauft.

l inter-Offica Cerresp nd:nco

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FPL To:

Department Heads Date:

June 19,1996 From?

J. Scarola Department: Plant Mar}aser

Subject:

OVERTIME LIMITS It has come to my attention that there have been recent violations of the plant's policy on overtime.

St. Lucie Plant has adminetrative and regulatory limitations on the use of overtime, both during refueling outages and during normal operations. The plant's Technical Specification, FPL Nuclear Division Nuclear Policy (NP-306), and St. Lucie Plant i

Policy (PSL-202), state:

4 1.

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

2.

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, til excluding shift turiover time.

3.

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work. periods, including shift turnover time.

For St. Lucie Plant, variations from the overtime limits can be authorized on a case-by-case basis, in advance, by the Plant General Manager or the Services Manager.

Violations of the overtime limits will not be tolerated and are subject to disciplinary action. We personally need to be aware of overtime worked, both with respect to our own working hours and those of the people who work for us, to ensure that we do not violate these limits.

Piem share this memorandum with your direct reports.

Copies:

L. W. Bladow C. L. Burton l

R. E. Dawson l

D. J. Denver l-C. A. Pell J. A. Stall E. J. Weinkam Form 1006 (Stocked) Rev. 2/89

i

~ DISTRIBUTION i

i L

PLANT VICE-PRESIDENT, MANAGERS, DEPARTMENT HEADS '

i L

'I J. A. Stall Plant Vice-President J. Scarola

. Plant General Manager L. W. Bladow Quality Manager C. L. Burton Services Manager i'

R E. Dawson Business Manager D. J. Denver.

JPN Site Manager

)

H. H. Johnson Operations Manager i

J. Marchese Maintenance Manager C. A. Pell Outage Manager R. Sipos SGRP Manager l

E. J. Weinkam Plant Licensing Manager-C. H. Wood.

System & Component Eng. Mgr.

l 1

l M. Allen -

Training Manager j

R. E. Ball Maint. Outage Supervisor L. J. Bossinger.

Stationary Supervisor i

G. L. Bouska Imd Utilization Supervisor j

L. C. Bouska Facilities Supervisor i

J. G. Brady Rotating Shift Supervisor H. F. Buchanan Health Physics Supervisor i

D. M. Calabrese Mgmt Info. Systems C. G. Crider Rotating Shift Supervisor.

I D. _G. English Rotating Equipment Supervisor i

H. L. Fagley Maint. Projects Supervisor R. J. Frechette -

Chemistry Supervisor J. P. Fulford Ops Support & Testing Supv.

F. Gigele Rotating Shift Supervisor j

L. K. Heffelfinger Protection Services j

R. W. Heroux Resource Control Supv - Acting J. W. Holt.

Information Services W. J. Korte Electrical Maintenance T. G.- Kreinberg Materials Management.

L. L. Large Rotating Shift Supervisor J. K. Luchka Speakout C. D. Marple Operations Supervisor

. F. M. McGlynn Rotating Shift Supervisor A. G. Menocal Maintenance Programs Supv.

~

L. C. Morgan Human Resources Manager L. N. Motley Valves & Welding Supervisor C. O'Farrill Reactor Engineermg R. C. Olson I&C Section Supervisor j

C. B. Pittman Maint. Budgets Supervisor D. K. Quilty Inventory Control L. A. Rogers DME Project W. G. White Security Supervisor I

l

l l

l Overtime Time Line QA PMON initiated May lith. The audit looked at the period between May 9th and May 18th.

l Several imdmgs'were identified and on June 6th, preliminary results were presented to the PGM.

Preliminary n8ingsindicated:

l A).

That overtime guidelines were being exceeded B)

Overtime deviation requests were not being filled out -

- C).

Management reviews of overtime adherence was ineffective Corrective Actions to Date:

1)

The Site VP and Plant General Manager discussed the problem with staff at the morning meetings to stress the expectation for personal accountability.

1 j

2)

The PGM issued a letter to all department heads on June 19th restating the overtime i

requirements and stressing personal accountability for meeting these requirements. The letter states that violations of the guidelines are subject to disciplinary measures.

1 3)

The site services manager has proposed a monthly surveillance program to spot check high overtime users (from time sheet totals) against gate logs to ensure that time sheets are not being artificially manipulated to avoid scrutiny. As part of this action, a monthly PMAI would be issued to perform the spot check.

t

?

t 06-18-1996 11G8f01 St Lucie Resident OHice 1 40? 461 4622 P.02 ADMINISTRATIVE CONTROLS 6.2 ORGANIZATION (Continued)

~

UNIT STAFF 6.2.2 The unit organization shall be subject to the following:

Each on duty shift shall be composed of at least the minimum shift t

a.

'cr,ew composition shown in Tabis 6.2-1.

-b.

At least one licensed Reactor Operator shall be in the' control room I

when fuel is in the reactor. In addition, while the reactor is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in the control room.

c.

A health physics techniciani shall be on site when fuel is in the reactor.

d.

All CORE ALTERATIONS shall-be observed by a licensed operator and supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation. The SRO in charge of fuel handling norntily supervises from the control room and has the flexi.

bility to directly supervise at either the refueling deck or the spent fuel pool.

e.

DELETED f.

Administrative procedures shall.be developed and implemented to limit the working hours of unit staff who oerform safety-rel n ed functions;.e.g., senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modification, on a temporary basis the following guidelines shall be followed:

t f

The health physics technician may be less than the minimum requirement for a period of. time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected absence,'provided iimmediate action is taken to fill the required positions.

ST. LUCIE - UNIT 2 6-2 Amendment No. 49 55 l

___._.._m

?

, 06-10-1996 11:39Rf1 St Lucie Resident OH ice 1 407 461 4622 P.03 I

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued)

{

a.

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

b.

An individual should not be permitted to work more than

, 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24. hours in any

~

48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7/ day period, all excluding abift turnover time.

I c.

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift turnover time.

d.

Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Plant General Manager or his deputy, or higher levels of management, in accordance 1

with established procedures and with documentation of t w basis for granting the deviation. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant General Manager or l

his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

g.

The Operations Supervisor shall hold a Senior Reactor Operator

I License.

ST. LUCIE - UNIT 2 6-24 Amendment No. M,65

06-10-1996 11:39AM St Lucie Resident OHice 1 407 461 4622 P.04 ttge 1 of 5 l

l FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT l

ADMINISTRATIVE PROCEDURE NO. 0010119 REVISION 14 Pst

1.0 TITLE

I b

8 A

OVERTIME LIMITATIONS FOR PLANT PERSONNEL

i l

2.0 REVIEW AND APPROVAL:

Reviewed by Facility Review Group 10/31 19,80_,

Approved by J. H. Barrow (for)

Plant General Manager -

10/31 1980 Revision 14 Reviewed by F R G 5/5 19,S4_.

Approved by C. L. Burton Plant General Manager 5/5 19.9_4_

4 3.0 _ SCOPE:

3.1 This procedure provides administrative requirements and documentation requirements for plant personnel working.cvertime..on safety..related functions..

FOR INFORMATION ONLY

4.0 PRECAUTIONS

THIS DOCUMENT :S NOI CONIROLLID. BEFORE USE, t

i VERIFY INFOtMATION WiTH A CONTRotLED DOCUMENT, j None n.o' lDA POWER AND uGHT CO. ST. LUCIE PLANT l

R DATE YERIFIED I

/

INrilALS 5.0. RESPONSIBILITIES:

DATE VERIMED

/

f INITIALS j

5.1 The Plant General Manager is responsiRe for ensuring that the use of overtime is minimized.

5.2 Each department head is responsible to provide necessary work schedules without routine heavy use of overtime.

5.3 Each department head is responsible to follow these instructions and ensure documentation of the basis for use of overtime exceeding the guidelines.

5.4 The Administrative Department is responsible for maintaining updated copies of the plant roster in each Control Room.

S_,_ OPS DATE DOCT PROCEDURE-l

. INFORMATION ONLY Lo?"

COMP COMPLETED ITM 14

_~

06-18-1996 ;11240AM St Lucie Resident OH1ce l'407 461 4622 P.05 PIge 2 of 5 i

l.

ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NO. 0010119, REVISION 14 OVERTIME LIMITATIONS FOR PLANT PERSONNEL t

6.0 REFERENCES

-~ e Spec Section 6.2.2.t 6.1 r

6.2 NUREG 0737 Section I.A.1.3 l

6.3 Administrative Procedure 0010518, " Fitness for Duty Call Out and For Cause

. Testing."

6.4 Nuclear Policy NP-306, Overtime.

6.5 St. Lucie Plant Policy, PSL-202, Overtime.

/R14 7.0 ' RECORDS AND NOTIFICATIONS:

{

7.1 Completed Overtime Deviation Requests shall be maintained in the plant files in accordance with Ol 17-PR/PSL-1, " Quality Assurance Records".

I 1

4 i

l INFORMATiON ONI.Y

. - -.-...~.-.-~.-.- ~.. - -

~ 06-10-19 % 11:40AM St Luc se Resident Of fice 1 407 461 4622 P.06 l

Pcge 3 of 5 ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NO. 0010119. REVISION 14

_ OVERTIME LIMITATIONS FOR PLANT PERS_ONNEL

8.0 INSTRUCTIONS

l 1

8.1 Excessive utilization of overtime is counterproductive and is tot.c avoided.

i l

8.2 ' 1he Ituclear plant personnel in all departments shall be covered by these instructions.

/R14

/R14 NOTE Nuclear Division personnel should adhere to these limits. Variations from i

these limits can only be authorized by the Vice President - St. Lucie Plant or i

his designee in accordance with the requirements of Nuclear Policy NP-306, Overtime.

8.3 Overtime Limit Guidelines:

1.

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift tumover time.

2.

An individual should not be permitted to work more than.16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more

. than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period,'all excluding shift tumover time. An acceptable deviation to this guideline is the STA seven consecutive 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months a,hift schedule.

3.

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift tumover time.

4.

Except during extended shutdown periods, the use of overtime should be considered on,an individual basis and not for the entire staff on a shift.

8.4 Deviations from Overtime Limit Guidelines:

1 Deviation from the overtime guidelines shall be approved by the Vice Preeldent - St. Lucie Plant, Plant General Manager, Services Manager.

2.

De senior person on site from their respective department shall complete the overtime deviation request (Figure 1) and obtain the narmanary approval for personnel specifically outlined in section 8.2 of this l

procedure. All St. Lucie Plant personnel shall comply with Nuclear Policy l

Guideline NP-308, Overti,me.

1 l

lNFORMATION ONLY

-I

~.

'06-18-1995 11:40AM St Lucie Resident Office 1 407 461 4622 P.07 PZge 4 of 5 ADMINISTRATIVE PROCEDURE NO. 0010119, REVISION 14 _

l ST. LUCIE PLANT OVERTIME _ LIMITATIONS FOR PLANT PERSONNEL 8.02 INSTRUCTIONS: (continued) t 8.4 :(continued)

~

3.

in' emergency cases, any department head may approve the deviation

<i request provided the Vice President - St. Lucie Plant, Plant deneral Manager or Services Manager is notified the next working day.

l 4.

More than one individual may be included on a specific request.

l 8.5 Periodic Review 1.

Each department head is responsible to perform a review that will ensure (nn a monthly basis) that excessive overtime hours have not been l

assigned. (See Tech Spec 6.2.2.f).

i i

,1 INFORMAT!ON ONt.Y,

w.w........,.~..,..a

-w....e.,._

~ -.. - -

-.. ~.

06-19-1996 11:41AM St Lucie Resident'0Hice 1 407 461 4622 P.09 Page 5 of 5 ADMINISTRATIVE PROCEDURE NO. 0010119, REVISION 14' _

ST. LUCIE PLANT l

OVERTIME LIMITATIONS FOR PLANT PERSONNEL s.

FIGURE 1 l

REQUEST TO DEVIATE FROM OVERTIME GUIDELINES I

TO: Vice President - St. Lucie Plant / Plant General Mgr/ Services Mgr.

l FROM:

DATE t

SUBJECT:

DEVIATION FROM OVERTIME GUIDELINES FOR (NAMES):

/R14 i

i

/R14 ORIGINATOR Roguest the below listed individuals to exceed the following overtime guidelines

{

Greater than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight i

. Greater than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months penod Greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period Greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day period A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (including shift turnover time)

~

SCOPE OF WORK BASIS FOR DEVIATION Personnel have unique quellflombordraining Sufficient rest will be provided -

O Turnover at personnel would Jeopardize quality of work Excessive lost time would occur and sufficient testeg wie ensure quality of activity 0 Oiher DETAILED EXPLANATION OF BASIS FOR DEVIATION APPfMVAL A E-G-j by P

Vee Pmeiseni. St t.uae Mant / Mant Oen Mgr. I Sen4ces Mgr (wow one)

BOUTING

. Original to Nudear Records Vault.

iNFORMATION. ONLY i;

)

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DOING DATE pa_rs antasta csus a varonna tocava cza indt MPUT $0t[fM l DAY lvm tocarm ST Mo any n suo art. cretasto soc 1AL SECUNTY NUMBER

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9 10 11 12 13 14 16 18 17 18 19 20 21 HOURS i

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Of Of0ER ER CO M SEC"N UC LOC'N RAG HOURS f.5 2.0 1.0 AEALA 312 90 000 62 0

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SOOAL_SECUfETY NL4mIOt 9162 1

8 DAY OFF SAT SUN-MON TUE WED THU FRI SAT SUN MON TUE WED THU FRI TOTAL 1

(.

23 l 29 I 30 l 1

2 3

4 5

6 7

HOURS i

l l

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I BAT SUN MON TUE WED THU FRI CTSKALs TUE I WED I THU l FRI SAT SUN MON TEMP. f4ELEVlho I

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DAY OFF SAT SUN MON WED THU FRI SAT SUN MON TUE WED THU TOTAL 11 12 l 13 l 14 l 15 l 18 l 17 l 18 l 18 l 201 21 I 22 l 23 24IN0uRs TiuE CODES _

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l mammusan DCDG DaH m.s ansume muu ese u.

av

.e o.,

-==

.ocm euuinv

-u

[

ese 1

05 24 96'

=

o.y or vie van un man ano truo l rua l (t>eo rua esan mee one truo nw:n tr>en m

TOTAL ran exxas 11 12 13 14 l 15 l 15 17 iP 19 20 21 22 23 24 HOURS r ea-ot 8.0 8.0 l 8.0 l 8.0 8.0 8.0 0.0 8.0 64.0 l

l

=

c2 l

l 1

os

==

04 b

l l

8.0 8.0

-16.0

--u, l

I I

I i

i 4.

I 1

nw l

l 21 1

l l

n-t l

i l

22 I

l 34 10.0 102 1.2 2.2 l 1.2 1.0 13.2 9.0 3.0 1.0 1.2 1.0 66.0,

((

34 1.0 1.0 1.0 1.0 l 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 12.0 es su u

su u

u se 148.0 O

lu wei. me,oma su iu u

in l

ovauso cone 1

1 1 l 1

1 5 },== =.-.

e, -

== nausvue (SAT)

(suw) p.w)

(TuE) l (wto)

(neu) gnQ

< SAT)

(SUN)

(MON)

(TUE)

(WED)

(THU)

FRQ l

l causeicum ce N -.

g r

mema-im n

t-l 1

1 I

.a== owiae tocarm dm waarm eeneum s2s um

-m - on w,

Account Description e, ann suar c-man.

or amoan en caert escw ue toes isouns u

u

====

emaa 8442 70 000 02 0

929 64.0 Regular 8442 70 002 02 0

929 Holday 8442 70 003 02 0

929-Vacation 8442 70 004 02 0

929 100 Eir+tra IHness Other - deserte =>

8442 70 000 02 0

839 NON4UTAG OTU1 2502 90 000 02 0

915 NON4UTAGE OT U2 2602 90 000 02 0

910 NONOUTAGE OT COMMON 2602 90 000 02 0

929 U1 RPS HIS UPGRADE 8834 70 322 00 0

915 0312 91 000 02 0

915 68.0 U1 OUTAGE OT SL1-14 JA.

ri TOTALS 80.0 68.0 MWN N A8 RDAARKS PREPARED RY APPROVED BY rasu s=

l 10T w GEM 9tetgis Timo R: port No ion PAmoamum

" m tw. eve scam.

NO EXCEPDONS (K) l l vama,==

pepeG DAM mvu 6 m

.oca ecu=ry - a we.

==

sr

.ao nav a

[

sion 1

06 07 96-am i

, e.

o. c.

,o.--

oavorTw wten run estaa pKne truo amen (non m

raan estec exue trut) run (non m

TOTAL voas er==

25 26 27 28 29 30 31 01 02 03 04 05 06 07 HOURS ae=

01 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 72.0 02

[

veceu "

03 "a="

04 f

e 42 8.0 8.0 4

0 J

is l

==

21 I

1

~

e._

22 34 11.0 11.0 11.0 4.0 4.0 5.0 8.0 3.0 3.0 3.0 2.0 2.0 67.0 f

r 34 1.0 1.0 1.0 1.0 1.0 1.0 1.2 1.2 1.0 1.0 1.0 1.0 1.0 14.0

((

ncu senc rotum us is o it s it s it s is e is se no us it s in n is's 161.0 "O

oratu amcaos

~

er - -

w. naurvoso (SAT)

(SUN)

(MON)

(TUE)

(WED)

(THU)

(FRI)

(SAT)

(SUM (MON)

(TUE)

(WED)

(THU)

(FRQ p

.uscicanou co

[sames cast.edPnaos

[m cascauPTian l

l I

I

.n=== cenae Locm e gras *een ah VAmaYtDN SCREEN 829 J

aeca =vi som an owsmresa ~==

Account Description 0am eu cr caanse sea av i

ma enier sec=

ue

.new moum.

u na

-e unus 5442 70 000 02 0

929 72.0 Regular 4

Hohday 8442 70 002 02 0

929 s

Vsestion 8442 70 003 02 0

929 Ernployee lilness i

8442 70 004 02 0

929 Other - desertje =>

5442 70 009 02 0

929 NON4UTAG OTU1 2502 90 000 02 0

915 4

NON4UTAGE OT U2 2502 90 000 02 0

910 NON4UTAGE OT COMMON 2502 90 000 02 0

929 5834 70 322 00 0

916 20.0 U1 RPS NIS UPGRADE 0312 91 000 02 0

916 C7.0 U1 OUTAGE OT SL1-14 8755 91 000 02 0

910 4.0 U2 S.N O W.

I TOTALS 72.0 i 81.0 d

TECH S!'EC WORK HOUR TIME LIMITS HAVE BEEN EXCEEDEDA8 ALL OF THE tercutaa BCHEDULED step 0mTEo A8 8 pr**gtKG Worked 5/27 Roguest Hohday in 97 PREPARED BY i

APPROVED BY ruAst e,.on

,on no

..=.-.

~.... -. _. -

s

'87

==ome acus m.i.

Time Report wo.

u===

,WU Taar erUf acRMN NO EXCEPDONS (X) l l Terme m m u mTE oAw e unno j

--socm sacuntry maamen muar umm si nao oav vn

.=>..

.r,_..

og.mau n=========

= mal in DAY W THE WW.ZK (EAD (RD4 Se:M l fruQ l enEDI ffMA N

fEAD (ED4 MP4 ffuQ (WaEDI m

m TOTAL ruascoots 08 09 10 l 11 l 12 13 14 15 16 17 18 19 20 21 HOURS 8.0 l 8.0 l 8.0 8.0 8.0 8.0 8.0 8.0

, 8.0 8.0 80.0 w

os l

l 02 l

l

[

v====

0s l

l u

l l

I I

I l

I i

21 l

l I

i 1

I I

22 I

I l

l u

12.0 12.0 3.2 l 2.2 l 3.0 4.2 14.0 1.0 3.2 2.2 1.0 4.0 3.0 66.2

[',""

34 1.2 1.2 1.0 l 1.0 l 1.0 1.2 1.2 1.0 1.2 1.0 1.0 1.0 E0 17.2 in es

i. e is su in se su

'um 164.0 "l"'"

i liu l us neu ene mru, u.

no in l

l ev ne-- coon l

l 0l=,.

or usus

w. naummo (SAT)

($UN (MON)l (TUD l(WED)

(THU)

(FRI)

(SAT)

($UN)

(MON)

(TUE)

(WED)

(THU)

(FRQ l

l

.nsricArm co 3a cascarnon 3

y==

cencar==

l I

I I

I sanaat cesanoe Locanau wa le *.avu unauecneen s2s account ma ca ovenvasa -

Account Description wonn musci cuanse neo.

or onosa sa consrr seen ue toen woune u

u

====v unas 8442 70 000 02 0

929 Regular 8442 70 002 02 0

929 Holsday 8442 70 003 02 0

929 Vacation 8442 70 004 02 0

929 Emriloyee Inness Other - describe =>

8442 70 009 02 0

929 NONOUTAG OT U1 2502 90 000 02 0

915 NONOUTAGE OT U2 2502 90 000 02 0

910 NON OUTAGE OT COMMON 2502 90 000 02 0

929 8834 70 322 00 0

915 80.0 84.0 U1 RPS NIS UPGRADE Af i

'4 U1 OUTAGE 01 SL1-14 0312 91 000 02 0

915 TOTALS 80.0 84.0 TECH SPEC WORK HOUR TIME LIMITS HAVE BEEN EXCEEDED ut w vm neauten REPORTED A4 $Uf'ER p* *

wtKs PREPARED BY APPROVED BY J

m 9,_.a

4 O

I P

l 0

l R

2

. j..

..j......_...

1.

1' NAME..

...i.

.j._ _

3 DATE....._.......}.DaHy.. Total.. j.Z.. Day Total..!2. Day..Ipta!.

4 5 /.13 / 9 6...

_i

- ~

5 5 /1.4 / 9 6.._

..t...

11.681.. _...

4..

..i..

11.68 6

5 /1. 5 /.9 6..

.j..

13.4 Sj..

25.13 5 /16/9.6.... [.

f q.6 7h..,_.

24,12

. 7

.m.

8 5/17/96

.,1 1.38 5j..

._22.52 9

5!18196...

.i... >.... 12.3.2{..

.. j............ 2 4.1 7 e

10 5 !19 / 9 6...

..i.

11 8 3j...

11 5./2.0/96

11. 67j

....ZL8pi...._..... 2 4 15 3

.83.477 2.3 50 12 5.../. 2..1.../. 9... 6...

1 1. 8. 2....'_..

8.. 3. 6. 0....

2.3.48 13 5/22/96

.j 12.22,...._. 8 2,8 7L.....

..24,53 14 5 / 2A / 9.6.. _..j....... _._,..13,Z 3g 85.93 26 45 3

15 5/24]96 12.37 86.45.'

26.'.10 16 5 / 2 51.9 6.,.....;.

.1.2.55 8 6. 6_8.......

24.9.2 17 5/2_6/96 1 1. 5 Sj...

.. _.8 6. 4 0j........... 2 4.1 0 18 5 / 2.Zf 9 6..

_.j.

11 121.

.8 5,8 5.;...

,.22,67 3

19 5 /. 2. 8 / 9. 6..

l

..1. 0.7. 2.!..

84. 75.I.

...21.. 8.3 20 5/.29196.,

...:..........1 1. 4 51.

._8.3.4.8

..22.17 21 5 / 3 0 / 9 6.......

.11.9 5}.

.81.70;

..23 40 i

22 5../..3..1..../_9. 6. -.....i...

........ 8.. 0 0.. i.......

7...7. 3.. 3 !

1.9... 9.. 5...

7 7

23

6. /1. / 9 6..

.i..

,_ 0. 00].

,. 64 7Ci 8.00 24 6/2/9.6...

.. 0. 0 0...

53.23 0.00

...1..1..3 3. 7..

5 3... 4. 5..!.....

...1..1..3_3 25 6./._3../. 9..._6...

I h $

.k.h..............k.Yh.b.U El.....

. #VALUE!.,;,_.. #VALU.El..

27 6 / 5 / 9.6...

j

.. 12 88,,

. #VALUE!..

VALU EI.._..

28 6 / 6 / 9.6 -

i 13.20}.....#jfALUE!

i

._... 2 6,0 8

,6 /7f 9 6

]..

11 98l,_.#VALUEl....j 25.1.8 29

... 1.. 2... 2. 0..q.....#...V...A...L.U...E.. !....!...-....-.... 2. 4...

1_8..

.. 1 i

30

6.../.. 8.../. 9... 6.......... 4...

1 32 6f 1 0] 9 6.....

.1 LO 5'......

... f e.

.. a

.VALUE!...j 22.73 33 6!1.1 !.9 6..

....i 13:02 86,02t 24.07 34 6/12/96 12.42

'85.55 25.43 35 6.../.1..3.. / 9 6

VALUEl l ~

VALUEl

V.._AL.. U_E...I.......

.7................_...7........................

36

.4 4

i 37 i

t i

i S

9 p,

E N si. Bass gre.e

= =

Time Report w

osma oan

==- -

v

.,vr---

o amanas oo l

1 -m -

suma totamm si eso DAT e

men ne g es. arums sanne amana erz,wy esasssa etes 1

06 24 we

{

- = =

DAT tF TSE WM SAD M

98mG M

N M

M MD M

N N

N M

M MM ins cones 11 12 13 14 1s is 17 18 18 20 21 22 23 24 Houns aw =

01 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 80.0 a

M*v 02 l

w =*==

os

e n=

04 42 k

g mi to m

imm una 21 as.

l mm t

samu s"*8 22 9.0 9.0 2.0 2.0 2.0 2.0 2.0 9.0 9.0 2.0 2.0 2.0 2.0 2.0 66.0 s4 24 3.0 3.0 2.0 2.0 2.0 2.0 3.0 34 2.0 2.0 2.0 3.0 2.0 31.0 ma,,,a mma u

u u

u ma m

na na ss as m

u us ms 167.0 er - - e 1

1 1

131....

m.

new.munem isAn seuie emoso tvun twupi rnas mu esAt1 soum tu m me twuni rusa amn

_.ans em p

3 p

emscumums

,I I

I I

1 unmana menmes unarmes wm

_-,unantom -

tas hapetAR b em

.._ esenSB e

Account Desonption mast emmes aus.

e, essai e

__7 enru ass taois asums sa na s==.sv amma 8442 to 000 70 0

829 80.0 RW sta si coo as O

sis s7.o Hasday W Eneas Oeier.d estb =

l i

J/l/

w TOTAAA SOD 87A m er as===== ma MMAfKs PfEPAND BY n.. -.

m,,ow0 v 44

~

/

l resumes M

ist

- a- -

-u -=

Time Report u

m mment me -

,_, m.

ve..uv s---

mo numo. m i

1 _ -

w-maan sawum si nao est n

euau maservsaamma T [_

- __GWEf__w

___1_!!!-_af__t!L oav w we uma man ause esome rnso l ennu l rose ese man suas estne rna fuum enes yes TOTAL Tearcours 24 25 28 27 l 2e l 2e 30 31 of 02 03 04 06 os Houns 34 l so l so am s.o s.o en s.o s.o 72.0' '

of

*

or s.oo l

l 6.0 l

l 1

=

I I

o.

I I

4:

l l

t-is l

l l

l 2i I

1 I

1 1

I l

l u

I I

~~

l l

34 9.0 9.0 0.0 2.0l2.0l2.0 24 2.0 2.0 2.0 2.0 43.0

"'* [*"

34 2.0 2A 34 1.0 l 14 l 1.0 2.0 2.0 2.0 2.0 2.0 20.0 u

me me m

m em 143.0

l=l

.,w,.va.

u as ce l

l 1 ---- eam 1

1 1

1 l 1 l 1 1

1 1

11}=m e

.v emms mer. samvens taATI teuse rasose (Tuo l (wEnt l (naA tme taAT) tous embote (TUE)

(WED)

(THUt (Me l

l

, _ - =-=

M I

I I

smeteu DenAM LOCAftDEI i

-- f eIS We aCCImmff WastArm01 SE2W8 orammas.

Account Deeotiption a

o ames us imes unas u

se e-ma amma R*euhr j

e442 to 004 70 0

828 80 0 312 si coo es o

ets a3.0 11 Header Veceaan Employee Ensee oei.r. 6.amese m.

A

,aTus een esa 11n ;

y M&

NLtRAMS PMPAMD SY AMROVED BY nznan man 7

=

. ~.,.

n, au.a.

Time it:p;rt us.

ea.we mm.,a w.

,e.c==

.e exan=s m I

l a.c.e 61 680 DAT vm

'.ev en mm.

socau obcuuty..

.,u i

os mi

=

I 7

i nAvor ne wara saan tuue esame i rne l fwen (net sPue esan tause esame rne rare (nee paa TOTAL

)

Tas costa 08 Os 10 l 11 l 12 12 14 15 18 17 18 19 20 21 HOURS s.ols.ols.o s.o a.o 8.0 s.o s.o s.o a.o 80.0 i

01 l

l

=

02 l

l o.

J 02 l

l 04 l

l I

I 1

I i

16 l

l m..

i I

si I

I I

l I

I I

I

="

22 I

I 1

I 34 s.o s.o 1.0l1.oi1.0 1.0 s.o 1.0 1.0 2.0 2.0 2.0 38.0

"'C'""

s4 2.2 2.2 2.2 l 2.2 l 2.2 1.0 2.2 2.2 3.0 3.0 1.0 25.2 u

u u

u na iu me 143.2

",L"'

lu l

.ee w m.

u u

u l

l na - an 1

1 1 l 1 l 1 1

1 1

1

'1' 10l......a..

.s saus taw.suurm a (SAT)

(suse tuose l (Tuo l fv4DI (neu)

IPsen taAn (SUN)

(W006 (TUE)

(WEDI (THU)

(FUtn l

l

.=r

-. aus as r-l

- o as mi-s29 w33 s.Ma WAMTENs a-

= m. en owsmium.amse Account Description woma sumi esmans sma.

er ammen e

esert amrs em toes amas u

as evases.:

amms 8442 SO 000 70 0

829 90.0 R*:9 312 91 000 85 0

915 63.2 10 Hoedsy vacanim Err Aa- - mneas co,.descrew =>

.s. 7 e r, TOTALA 80.0 632 10.0 ma se vis

a

slEP'emW 68 IERSAflES PfEPAPED 5 APPROVED BY nJass essa f

h

o l

P l

0 l

F1 1

.N AME. _._...

2 y.

3 D ATE.,

! Daily. Total

[ 7. Day.. Total..[2. Day. Total 4

5/13/96..

...[..

10,.65!

l 5

5/14/96.....j..

. 8.60.

19.25 6

5 /.15 / 9.6..

..]...

11 12 [......,

.. j.

.18.72 7

5 /16 / 9.6..

10.80i 20.92 8

5 /1 7 / 9 6.,

..10.2 0)

.21.0.0

........ 0. 0. 0..,!.

1.. 0... 2 0..

g 9

5.../..1.. 8.../. 9... 6...

10 5./19/96 9 73j...,,.....6 0.10

.9.73 11 5/2O!96 14.15 5}.._..... 6 4 :0 0,.

..24 28 12 5 / 21!.9 6..,.._...j....

..12:0 0j.

._..,. 6 7.14 0......._.. 2 6. 5 5 3

5 /.2 2 / 9 6..,.....[.

_10.85

. 68,,13j 22.85 13 14 5/23!96.

.. 9,9.8..

6 7.t3 2...

.20,83 15 5 /2,4 / 9 6..

10.70j 67.82,

..2 0'. 6 8 16 5 / 2 5 / 9.6...

0. 0 0.!

6 7. 8 2!...

.10.70 17 5 / 2 6 / 9 6....._.j...

9 88}...

6L 97.i..

9.88 11.17!..

6 4. 5 8j.....

..21.05 18 5/27/96.

19 5 / 2.8 / 9.6..... j.

....... 8.f 8,.

_61.3 7j..,

._...19.9 5 20 5/29/96.

.....1 1 :13

.. 61.6 5]_.

..19 92 21 5/30/96._ !......

_9.57

.61.23[

.20.70 5 / 3,. ] 9 6...

..9. 8 5...

60.38[

19.42 22 1

23 6 /1.f.9.6......

.[.

0. 0 0..

. 6.0,.3 8[........

9.85 4

I 24

6..../. 2.../. 9. 6..........

.. 8.. 6. 5. 9...

5. 9.._.1. 5.....

,. 8.. 6... 5..

25 6 / 3 /.9 6....

..,......... _1 1.2 3!... _

..59.22

_19.8.8 26 6 / 4 /.9 6...

.. j..

12.1.7l 62.60..

...2 3. 4 0 27 6..../. 5..../. 9.. 6......

1. 0.. 6.. 5..,i...

6. 2... 1.. 2...!.

2 2 8. 2...

28 6 / 6 / 9 6..

14.8 8}..

._6 7. 4 3[....,_,_ 2 5,5 3 j

72.43}.

2 9. 7 3.

29 6 / 7 / 9 6..._...j.

14.85...

_ 8 4,4.8}...

....2 6.9 0.

30 6!8 /.9 6...

12.05, 31 619./96.,

13,.10l 88 93[

.._. 2 5.1.5 32 Gli 0 /.9 6._...

..._.10.5 0[..._..

8 8.,2 0!

23.60 33 6L1 1 /.9 6... _...!..,

11.73!

87 77!

22.23 34 6 /12 / 9 6...

7. 6 3!......... 8 4.7 5

.. _.19.3 7 35 6 /.13 /.9 6..

0.0 0!....._., 6 9.8 7,.

.. 7. 6 3 l

36 37 j

l l

l e

4

.

_ _ ~ _ - _.

Ftntop N

3 E 84 M86 *mtzhata Fil] TIM INPUT SCREEN l# EMCEPUM iXI TDW50RARY LOCATION ENDioe LA!!

cart Etirasn t!acLE ceg Locarice.

st ace act:ete nces,.

--__sc,

._sacas secuntrv 9tf7 0 6 z L 9. C, ex

<xt axl a,------__

ISATI ( St.H I IMONI (TUEI I ND I ITHRll IFRIl i stN I

( MON I I TUE I IMED I I THR I I FRI,

toim. eevns NW 1 :na s r:= mocs oe q

to it l t't l t1 l (4

('r i k i4 W

l1 t,o.,, 21, el si 6

%I lt i lt l !

I SI Si 8!

tl %i yo f

)

y y

y i

g I

I Il l

l I

I 2

=

.a s

1

.r wl Gx p-ll l

l r

w m

e s..yyy z g

<m.. y.

p.

L. y

.h clf p q;;. p 21 l

l l

U

.k n,

g.

.:a.+u+

,4

}

.m s..a.,.. n.,.,.,

M 2l%_ +.

q.

x,, e, l.

e

.. m x..;

+

n..

m l

l l

k U

l t

pp5 g

ag: x% gtypgg3

pggy w g.%

y /.g.y ;

y

=

~

ll l

l O[

V

(" Qd

' J.[. ; *,. <n$l

..d t

$,I ',

[T, 4.

6 N.. "..l 4_

N

~

..c a

I I

l l

l 5

s ;g L u pg a g p p

ggc; y g

1:

i l P $

@ph g

_p zog y,.

3 6

M i 4 E h C 3

'Z i 6l-71 3 -l Z.

ll0 llIb

$ $4-6 l

j;

[.

g3 1 +

or ac u o,. ceae s.

1 i l l 2-pm i

i i

c.

n->pmipmis,o n.An i-i-io, im, ilo, i=> imi ion i-i i-TEMPORMW

,N, E e l

l l

TOTAL ALL HOURS-CLAS$

SEEalp rJ4pe E

cws DL&CALPf!G8 CLAi$

DESCA 1Pittee NORMM. CHARGE LOCATI@4 MACC0tRT VARIATION SCREEN OwEntng noyRs FIW 6 MN 6 AccoWMt tag. OR C>ud PRIM M

,9 gg "d'8 SAT sw e TW e M Pal uf m aos fu e M ref

'80'"'

Pld "Db8'8 1.5 Le ETuleptf

8E8l 8

Cop **f asc*u uC

*h N.N

[ EYd

'h" Y CY N

D

~

$'l Y

' +.,

.a-

.>s_.-

1..

s 3lt 95 9

0 iLI ED

.I s.

4% y n*% W.Ag

{@%W b ja q dQ 5%@

w g,

40 4

50 SI 015 f> l '..iti

~

m

.t i

g

,P 3

(*

p 2" p

)-

4,

'.1$

I il M

N O $10 T

+

.a K HT

':h U V %9 l W.% in. W ii U 2% 5 ;

l p.3

.,w3 3p

. =. ya y w a e

3 I

l

,w.

l m.

SQ a w

s s q hwi y P e :&

m I

h f. %?

l ; vg af ge.9 i.,_ ^ t.Q. g y

'Q'

'a sat sum man tw e ne att sat m non tur e he

.est

=

-,u===

t ruinoG1 igIO W d t)hliff

% fdwaul

"'*"2 e.cP a co ev

~

j

(

h $O*O *

,,. w.n.,

u

.uas sus

Ed~d"[-~

j

**'2 Na

-a

===mi,t

. * ~

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i St. Lucie Nuclear Plant l

Un't 1 Spring 96

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Outage Guide 4

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" Team Work" "This document is available electronically on the PSL bulletin board"

t Site Vice President's Comtnents The spring '%firefueling outage for St. Lucie Unit I contains some interesting projects and some tough challenges to the permanent plant start, the temporary workers, and the contractors who will be undertaking this work. Repairs to the main generator have defined the critical path, the first time in recent memory that the balance of plant work has been the primary critical path for return to power. On the primary side, we have the ten-year reactor vessel in-service inspection plus a visual inspection of the core barrel repairs made in 1984. We will install the Taprogge mod on Unit 1 -

hopefully, we have seen the end of downpowers forcondenser cleamng at St. Lucie.

With these challenges set forth, let me remind you of the really important things:

First, we want no one associated with this site to be injured on the job. Thmk personal safety as you plan and perform the work.

Second, we do not want to challenge nuclear safety by either planned or unplanned work.

We need to respect our rules and procedures goveming decay heat removal, notjust during the vitally critical times while in mid-loop, but also during work on systems connected to

)

the primary systems and the associated electrical work.

Third, we expect to do the work right the fust time. Neither our schedule nor our budget recognizes rework and we must ensure that as we plan, perform and close out work, that it has been done to the best of our abilities.

Finally, paper close out is part of the work. St. Lucie will not retum to power with a long list of mods and work orders not closed out. This will be a significant effort, but we recognize that the best plants do it, and so can we.

We have made many changes in 1996 and more are to come. Despite these changes, our goals are to have a controlled outage with respect to quality, cost, and schedule with a smooth, predictable retum.to power. I believe that we have the capability and the desire to achieve these goals. I ask for your helpin achieving them.

e

/

Ir 1 Bohlke f

[. St. Lucie Site Vice President vpps!012-96

I t

l

[

TO:

All Site Personnel.

Date:

4/10/g6 FROM:

Ash Pell Department: Outage Management

Subject:

Outage Safety n

f j

During this refueling outage, we will inspect the reactor vessel, perform needed repairs to our main ciectncal generatordeplace the pressurizer code safeties, install a condenser tube cleaning system j

end perform necessary power plant maintenance. The scope of this outage is large and requires a high level of teamwork and communication in order to be successful. This outage will complete our i

{

efforts to correct equipment problems and will result in much improved performance in Unit 1.

' The outage schedule is designed and built to ensure that shutdown risks are minimized and that j

multiple success paths are available for all safety'func' ions. It is absolutely essential that all the work t

j you perform during the outage is reflected in the schedule where it has received the necessary review by Operations and Outage Management. Work scope additions or logic changes should be submitted 2

l for inclusion as far in. advance as possible. Under no circumstances should you perform work or 1

t:; sting or operate equipment for which you do not clearly have specific permission or clearances. We must protect the operability of the equipment which is required to be functional through each plant mode.

l As we progress through the outage, the status of safety functions will be eva'uated according to the plant configuration and available equipment and reflected as a color-green yellow, orange or red.

i The most restrictive safety function status will be considered the " Plant Condition" for that period and will be publicized across the plant site. The Shift Technical Advisors will assess plant conditions and c

icsue these results daily.

1 L

if y6u or your crew is assigned the responsibility for a contingency plan, you must ensure that you

. completely understand your part and be confident that you can successfully' implement your actions if 2

required.

The personal safety of plant workers is paramount. Adherence to our safe work practices and j

procedures, proper clearances, 'and safe work habits in the field are essential to ensure the health and safety of your co-worker and yourself. Ensure you work with your supervisor and Plant Safety Department Representative, should you have any questions.

O Nuclear plant safety this outage is assured by following procedures, adhering to the schedule, proper clearances, and error-free personnel performance. The support of each plant worker in assuring j

safety is important for the safety of each employee and that of our community.

i.

We've had less than four months since our last outage. Much has happened during this time. We've j

undergone a major reorganizabon, numerous management changes, and a number of major process j

i ~

changes. We've addressed many commitments in response to an ongoing series of regulatory audits End responses to events. A large number 6f procedure changes were needed as a result. Significant -

1 i

preoutage work was unde taken to prepare for the outage. Much has been improved during the last several months. Now that the refueling outage is here, we'll be able to use these new programs, processes, procedures, organization, and outage preparations to have a successful 49 day outage.

Our teamwork is the key to our success this outage.

3

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s 1

TABLE OF CONTENTS I

t 1996 SPRING OUTAGE GOALS 3

1 4

~~

COMMUNICATIONS gal-TRONICS 4

4 l

PBXM PAX PHONES BEEPERS.

4

(

RADIOS 4

l CONTAINMENT PHONES 5

FIRE PROTECTION 6

l FIRE EMERGENCIES PSL PROCEDURE d

GENERAL EMPLOYEE TRAINING 7

HOUSEKEEPING AND MATERIAL CONDITION -

8 J

RADIATION PROTECTION 9

CONTROL OF OVERTIME 9

l 10 l

SAFETY 11

- SCAFFOLDING USE OF SCAFFOLDING TO SUPPORT LOADS 11 11 SECURITY SECURITY REMINDERS-11 SHIJTDOWN _ SAFETY -

12 13 ABB/CE 13 CHEMISTRY 13 CONTRACTS 14 ELECTRICAL MAINTENANCE 15

. HEALTH PHYSICS 16

- HUMAN RESOURCES 16 INFORMATION SERVICES INSTRUMENT AND CONTROL 16 1

16 l

LAND UTILIZATION l

17 LICENSING '

i MANAGEMENT INFORMATION SYSTEMS 17 n...........

i i

l 1996 SPRING OUTAGE GOALS UNIT 1 1

l l

Personne] S.afety - Lost Time injuries.......................

0 i

i Doctor Case injuries.....................................

s6 N RC Violations.........................................

O l

Outage Duration Days...................................

s49 i

i Personnel Radiation Exposure............................ s316 Personnel Contaminations................................

s10 (Any Contamination Resulting in a Skin Dose)

Contaminated Floor Space Within 14 Days Post Outage........<1,500 ft b

Cubic Feet of Radiological Waste Generation.................<6,300 ft Outage Budget........................................ sS25M Unit Performance - 60 Days Outage Availability........,.....

293%

6 SUCCESS MEANS REACHING OUR GOAL l

i L

i i

CONTAINMENT PHONES DESCRIPTION EXI l

t i

Personnel Safety - Lost Time injuries...........

........ 5480

~

?

EquipmentRamp (Colcl Side)...........

............. 5481 i

Raytheon Ramp Access Shack............................................ 5482 Health Physics 62' Elevation............................................. 5484 t

i' Health Physics 18' Elevation.............................................. 5485 Pressurizer 18' Elevation...................................

........... 5486 Steam Generator 1 A................................................. 5487 i

l Steam Generator 1 B........................

..... 5488 i

Stores 23' Elevation.................,................................. 5489 Tool Room 62' Elevation................................................. 5490 Mulb-Badge Trailer...................................................... 5491 RCA Pre-Job Bnefing Trailer.............................................. 5492 e

RAB Respirator Room................................................... 5493 J

I i

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GENERAL EMPLOYEE TRAINING L

DEPARTMENT HEAD BEEPER E]E ~

j Tom Ware.

2077 4294 i

IIILE NAME Instructor _

Mark Cooper 3440 l

Steve Knapp 3440 Instructor SHIFTTIME

[

'07:30 -16:00 Additional coverage as required by outage schedule..

i N.QIE Call 3440 to make an appointment for Level I or RCAT.

Call 3024 to make an appointment for MMPt.

l t

l Call 3561 to make an appointment for respirator physicals.

i Call 3389 to make an appointment for respirator fit tests.

t l

APRIL 1996 1

PLANT ACCESS TRAINING

?

S 31 M 1 T 2 W 3 TH 4 F S S' 6

8:00 PATandRCAT 8:00 DAY 2. RCAT s to DAY 3. RCAT 820 PATandRCAT 8:00 DAY 2. RCAT 4 00 DAY 3. RCAT

.l' 3 DAY COURSE 3 DAY COURSE l

l-14:00 DAY 2.RCAT 1600 DAY 3.RCAT

. 1820 DAY 3.RCAT f

1920 PAT and RCAT 1820 DAY 24tCAT 3 DAY COURSE 1820 PAT and RCAT S

7 M S T 9 W 10 TH 11 F 12 8 13 820 PATandRCAT 820 DAY 2. RCAT 8:00 DAY 3. RCAT 8:00 RCATREQUAL 020 RCATREQUAL

^ '

3 DAY COURSE is 00 DAY 2.RCAT isso DAY 3.RCAT 18-00 DAY 2.RCAT 1820 DAY 3 RCAT

.r 1420 PAT and RCAT I-3 DAY COURSE 1820 PATand F. CAT I'

S 14 M is T

.is W 17 TH 18 F 19 8 20 8:00 PATand RCAT 020 DAY 2. RCAT 8:00 DAY 3. RCAT 820 PATandRCAT 8:00 DAY 2. RCAT 8:00 DAY 3. RCAT

^

3 DAY COURSE 3 DAY COURSE 1820 DAY 2

RCAT 14:00 DAY 3.RCAT 16:00 DAY 3.RCAT 16:00 PAT and RCAT 18:00 DAY 2.RCAT 3 DAY COURSE 16:00 PAT and RCAT S

21 M 22 T 23 W 34 TH 25 F 26 8 27 820 PATandRCAT 020 DAY 2. RCAT 8:00 DAY 3. RCAT 0:00 RCATREQUAL Sto RCATREQUAL 3 DAYCOURSE j

820 PAT.NTC290 1620 DAY 3 RCAT 4:00 PAT.NTC260 16:00 DAY 3.RCAT

.j i

1820 PAT and RCAT 3 DAY COURSE 1820 DAY 2.RCAT 16:00 PAT ard RCAT 10:00 DAY 2.RCAT I

S 28 M 29 T 30 l

820 PATandRCAT 4.00 DAY 2. RCAT 3 DAY COURSE i

1 i

o.. r n,naw wannemens

..,..---~....

i i

RADIATION PROTECTION Al.ABA

?

During 'W pccming Unit 1 outage, it is important than ever to practice some,of the basic Al. ARA j

tools when approaching work. Reduce your time in the radiation area by having the right tools and '

5 bordinate'yedr work with other departments' work in the same area. Increase your distance from the source of exposure by wortung on the low dose side of the component, waiting in lower dose rate areas, or removing the component to a lower dose rate area. Discuss with Health Physics J

personnel your job, its duration, and the possibility of shielding.

All RWPs require a pre-job briefing. Allow time in yourjob planning for pre-job briefing.

CONTROL OF OVERTIME St. Lucie Plant has administrative and regulatory limitations on the use of overtime, both during refueling outages and during normal operations.

St. Lucie Units 1 and 2 Technical SpecJc.etion 6.2.2.f, FPL Nuclear Division Nuclear Policy 306 (NP-306), Nuclear Policy - Overtime, and St. Lucie Plant Policy PSL-202, Overtime, state:

1.

An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift tumover time.

2.

An individual should not be permitte to wor more than 16 hour1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months s-in any 24-hour d

k

' period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7<iay period, all excluding shift tumover time.

3.

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift tumover time.

Variations from this policy can only be authorized by an officer of the Nuclear Division or his designee.

q Shift tumover time should be documented as " Shift Tumover" on time sheets.

All personnel.are required to be aware of the above overtune Irnstations and to adhere to them to

~ ensure that we do not violate our license or an administrative limit.

Sh&

&O &$&&&

-OM S

'S

I i

SCAFFOLDING i

USE OF SCAFFOLDING TO SUPPORT LOADS Scaffolding built at St. Lucie Plant is required to be built in accordance with AP 0010724, *Use of Scaffolds, Ladders, ooatswain Chairs, and Manbaskets." Scaffolds are built by Projects and Maintenance ' Support Department. If there is a requirement of a scaffold by other departments or

{

~

groups, they>should coordinate this through the daily outage meetings.

Scaffolds with red tags are considered as NOT SAFE and shall not be used. Red tags indicate f

either the scaffold has not been completed or has been found to be unsafe. Scaffolds with yellow i

tags require additional safety actions for safe use. Green tags indicate that the scaffold is safe to use as 's.

}

i L Scaffold components can also be used for rigging support for other work activities. Although a common practice, these types of scaffolding require different design, engineering and procedure requirements. ' All scaffolding used to support loads other than personnel shall be specifically built for that activity using the requirements in AP 0010724, "Use of Scaffolds, Ladders, Boatswain l

Chairs, and Manbaskets."

l 1

Please comply'with the above requirements. Problems encountered or questions regarding scaffolding or scaffolding used for rigging may be directed to the Maintenance Support Shift Supervisor at ext. 3946 or Marvin Goodiel at ext. 4134.

o SECURITY Security is a job in which everyone plays a role. Adherence to the St. Lucie site security plan is the j

I responsibility of FPL personnel, contractors and security officers alike. St. Lucie security, just like l

our operating standards, is part of our commitment to protecting the health and safety of the public.

We take this commitment seriously. Despite increases in plant population and materials handling i

during the outage, we must carefully follow all security procedures. To avoid work delay, security -

considerations must be factored into alljob planning. If you are unsure of the security procedures associated with a job, contact your foreman, supervisor or security.

SECURITY REMINDERS Ensure you have closed and secured all doors you have accessed.

e Security is the responsibility of everyone on the plant site.

e Remember to bring your badge to work, e

Lost badges must be report to secuiity immediately.

e When. escorting a visitor, you have the responsibility to maintain constant surveillance of the e

individual

. Badges must be wom face out between the waist and neck. (if job conditions prevent this, e

check with security to determine the appropriate attemative.)

.. ~. ~ - -

o..,. u omon, u n.a ment

b I

ABB/CE DEPARTMENT HEAD BEEPER M

i 2577 3237 i

Al DeGraSSe i

Home:

I Direct:

j m J

~

OUTAGE COORDINATOR 3

AlDeGrasse -

2577

-3237 i

v TITLE NAME ECT/ Task Manager

. Henry LabienieC j

CHEMISTRY I

DEPARTMENT HEAD BEEPER E

3556

)

Kurt Beichel J,

OUTAGE COORDINATOR 3393 D.H. Faulkner TITLE DAY SHIFT 3291 3101 Shift Superv SOr TITLE PEAK SHIFT 3291 3101 Shift Supervisor CONTRACTS vemSnE ConvRACToR WORK scope SPoN DerT-CONTRACTS PPL 3 TE Sn3vemaR REP '

PH00E AGBfT COORD

.AEPWD RAD -

RX CAV DECON DEALTH PHYSICS J. HEPOURN R.n w auaantS TBA CTRL SP EDERGY SVCS HP REBT.A.

HEALTH PHYSICS E.LOUGMAN R.McCULLERS GREG DAfeELS 3356 GRP TECHS WTERSTATE MOSILEWET HEALTH PHYSICS J. HEPBURN R. McCULLERS TBA NUC WASH

' l, l

SCIENTIFIC EC DRYWASTE RED HiALTH PHYSI 2 E. LOUGHRAN 5.SOMERS TBA GRP l

ABB / C.E S4TURE MAINT PLANNING E. RLJTKOWSKI A. FLOWERS AL DEGRASSE 3237 PLGftEP I'

ALilANCE INC.

NUC DNWG MANr PLANNING J. HEPSURN A. FLOWERS MANNY 1RWIN TBA SvCS PCA ENGR ICNCW BGBPECT MApfT PLAIGGNG J. HEPBURN W.YATES DICKMONTGOMERY WESTW8GHnsH TlftTLVLV/ SEAT MAINT PLANNING J. HEPBURN 5.R. NICHOLS DAN HICMORY 3745 f-FREEZETECH FREEZE SEALS PROJ MAINT J. HEPSURN M.ROBERTSON TERRYL WY 5351 e

MC SuPP NUC ENERGY SG TRIG SUPP PROJ MAINT J. HEPSURN A. FLOWERS J. DESANTI 3566 SVCS SUPP i

J.L. MANTA INC.

PABmNG PROJMAINT J. HEPSURN P. DONOVAN BOBBACHMAN 4505 e

SUPPORT SUPP-j-

NA110NAL CRANE SUPPORT ROTATING EQUIP J. HEPBURN D. ENGUSH TBA l

_l N

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Haa1 *oea n. w.

Pace 13 Outage Management

i l

HEALTH PHYSICS i

l I

MANAGEMENT COVERAGE (Rotating 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts) t i

NAME BEEPER EXI l

~

H.F. Buchanan (Cellular 407-595-2505)

7585, 7300 j

R.M. McCullers '

7613 4242 H.M. Mercer 7590 7302 K.Payne 7261 7304 OUTAGE COORDINATOR Ray McCullers 7613 4242 i

TITLE DAY SHIFT I

ALARA Kenny Payne 7261 7304 l

I ALARA

- Brenda Johnson 6533 7306 Budget Grace Lynch 3386

~ Dosimetry Bart Johnson 7579 4240 Instrumentation Bruce Somers

.7604 7305 Merlin Calibration Lab 3039 Merlins Keith Mouring 7612 7310 instrumentation Keith Mouring 7612 7310 Operations Vince Munne 7591 3508 f

' perations

. AlWeir

.7385 3503 O

Rad Waste Bruce Somers 760(

7305 Rad Waste Doug Haithcox 75G3 3704 TITLE PEAK StilEI ALARA/ Decontamination J.R. Smith 7291 5284 Dosirnetry Pam Dunne 3841 Operations' Ed Beurrier 4831 3545 Operations Don Reisinger 3503 TITLE MID SHIFT

')

ALARA/ Decontamination Lang Jacobus 7397 7308 Dosirnetry Liz Moore 3840 l

Operations Don Debock 7611 3508 EAK Dosimetry 4167 HP Office 4178 i

LICENSING l

t DEPARTMENT HEAD BEEPER E

l Ed Weinkam 2130 7162 l

h

~ ~

NAME

. Generic NRC lasuer '

George Madden -

2053 7155.

f NRC Inspections -

Ed Benken 2032 L7157 e

2 Tech Specs Dick Dietz 4303 7156 i

Surveillances Sean Lavelle 5915 7160 Surveillances -

Tom Quillen 5918 7161 MANAGEMENT INFORMATION SYSTEMS-WEPARTMENT HEAD BEEPER EMI Donna Calabrese 2597 7185 l

MIS SPECIALISTS David Dotson 9046 7188 Rick Anderson-2470 7198 l

John McGlenn -

6450 7187 After Hours Beeper 7394 MAINTENANCE PROGRAMS.

3 DEPARTMENT HEAD BEEPER EKI Tony Menocal.

2468..

7400 l

OUTAGE COORDINATORS

!2604 7245 Kathy Mayhew (Days) 5490 7331 Sparkie Dill (Peaks)

NAME IIILE inserwce inspection Lead Kathy Mayhew 2604 7245 ISI Snubber Coordinator (Peaks)

Sparkie Dill 5490 7332 ISI FAC Coordinator (Peaks)

Patti Cruthers 7331

~ ISI Exam Coordinator (Peaks)'

Patti Cruthers 7331 CSI On-Site Lead Jim Connor 7230 e

CSI NDE Coordinator (Days)

Dan Nowakowski 7489 CSI NDE Coordinator (Peaks)

. Bob Cline 7512

Maintenance Procedures (Days).

Andy Delgado 7426 Maintenance BOM/TEDB (Days) '

Art Deroy 2088 7408 ISI & FAC Coordinator (Days)

Tom Quillen 5918 7332

' ' *

Na A 4-.. -

Done 97 (httSne Man 30efnent

. _ -, +

MIDWAY SERVICE CENTER S/C DUTY PERSONNEL BEEPER E

Joe Mills 8097 1234 8503 1220

Bob Kniprath Tom Jones 8337 1200 Doc Thiery -

~

8126 1200 Bob Scroggin 8094-1200 Tom Branch 8170 1200

~

i Tom Lancaster "

8123 1200 l

Stan Smilowitz 9174 1200 Ken Nipper 8884 1200

Ron Williams -

6606 1226 Dial 8-118-Beeper #

Dial 8-595-Extension #

NUCLEAR ASSURANCE

~

llTLE DAY fitSEI BEEPER EXI QC Supervisor George Schnebli 7001 7280 l

Altemate -

Tommy Dwyer 5361 7464 Altemate Ken Crosby 9396 7366/3714

- QC inspection George Ingram 9391 7462

' cAK SHIFT TITLE r

-QC Inspection Bobby Brown 9387 7365 I

QC inspection Bill Hays 9399

-3716/7279 TITLE MID SHIFT QC Inspechon Dean Gingras 9389-7460 This slignment is subject to change upon final determination by Maintenance and Maintenance Projects for their shift alignments.

NUCLEAR MATERIALS MANAGEMENT (Purchasing and Contracts) l DEPARTMENT HEAD BEEPER EXI 4179 Dan Quilty OUTAGE COORDINATOR Dan Quilty 4197 DAY / PEAK SHIFT SUPERVISORS Dan Quilty -

4179 Mike Ullman 4184

!~'

MID SHIFT SUPERVISOR

[

Art Neuberger -

4180 WAREHOUSES

. Central Receiving-3899 j-

~ Unit 1 Storeroom 3903/3476 G1/G2 Storeroom 3701/3708 5236

~ Dry Storage

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OUTAGE MANAGEMENT OUTAGE MANAGEMENT BEEPER EXI Ash Pell (Cellular: 285-9144) 2011 7104 TITLE DAY SHIFT Schedule Supervisor John Hauger 7395 7126 Lead Scheduler

Bob Maisano 7127 OPS /OM Coordinator Mike Wright 7358 7072 Scheduler-Maintenance Bobby Gross 7497 7182 Scheduler-Elec Maintenance Hugh Casper 2556 7047 Scheduler-I&C Tom Glenn 7843 7382 Scheduler-Projects Doug Hibbard 3471 3152 SD Risk Chuck Scott 2411 7025 TITLE REM < SHIFT Schedule Supervisor of E-Work Tony Marvin 7390 7127 Progress / Scheduler Jeff Monaldi 7133 TITLE RIID SHIFT OPS /OM Coordinator Chuck Couture 2178 7072 TITLE DAILY Daily Work Control Supervisor Bill Hagar 2412 7134 Daily OPS /Maint Coordinator R.J. Davis 2401 7124 Daily OPS /Maint Coordinator PaulWilliams 6592 7129 Shift Director ROTATION Mids 7135 Bob Frechette JeffWest Days 7262 7135 Tony Menocal Attemate 2468 7135 Chris Burton

/Jtemate 4304 7135 Deputy Shift Director Lee Large '

Nights 7597 7135 Harry Bishop Nights 2557 7135 John Brady Days 2392 7135 Frank McGlynn Days 4329 7135'

~ < ~ ~ - -

panos outaae unnaaement

i PROJECT LEADS Pmject Project Leadl Responsible Task Managar Manager l

- 10 Year Reactor Vessel and Core Barrel inspections K. Mayhew Marchese Cordingency plan for repairs (Supv:G. Pustover) Denver l

~

c Pressurizer Code Safety Valve replacements C. Ward Denver RPS NIS Upgrade Repair detector positioning devices G. Pustover Marchese j

l i

i Hardware replacement (detectors, drawers, etc.)

R. Olson Steam Generators (Overail).

R. Ball Marchese i

Westinghouse SG Tube Plugging & PAP (Supv-Flowers) l RWT bottom inspection & water management plan R. Frechette H. Johnson RCGVS Valve replacements and piping modification G. Rodgers Marchese r

incore Instrument Assembly replacements R. Olson Marchese V07161 and bypass replacement G. Rodgers Marchese Polar crane load test D. English Marchese l

TCV 14-4B replacement H. Fagley Marchese l

1A &1B LPSI common piping valve work N. Motley Marchese j

EDGs overall McLaughlin/ Ware Wood Charging header isolation valves repair T. Sanders Marchese j

' SE-02-1,2,3 3

FCV.47-1A/1B maintenance T. Sanders

.Marchese

- SIT valve maintenance N. Motley Marchese I

Quantify leakage pre-outage P. Fulford V3634 stem replacement N. Motley ICW pipir7 at intake structure extemal corrosion R. Ball Marchese inspechon Repair contingency (Supv:Yates)

C. Swistek Wood Purge Valves RCB permanent A/C modification H. Fagley Marchese HJTC replacements R. Olson Marchese l

HP turbine & seal ring replacement R. Ball Marchese l

Condenser Tube Cleaning System and Debris Filter D. Sipos D. Sipos

,j installation Atmosptsic Steam Dump valves seat repair N. Motley.

Marchese

(

Main Generator R. Ball Marchese l

Maintenance / Modification Nichols/Wolaver Turbine tuming gear auto / remote engagement repair Wolaver Wood i

RCPs (allissues)

B. Haines Marchese I

p

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PROJECTS

(.

1-BEEPER EXT DEPARTMENT HEAD 7504 7376 H;nnan Fagley TAPROGG'E i_EAD 3623 Dick Sipos OUTAGE COORDINATOR 7504 7376 Herman Fagley(Days) 3450 3486 Brent Butcher (Nights)

Tooling /Rignina 2565 7283 Ed Burgess Lead 7307 7284

. Lee Miller (Days) 2778 7285-j J. C. Jones (Nights) 3751

)

Foreman @F4 5214 F4-Front Counter 3859 F4-M&TE -

4083 F4-Rigging 5495-

- RCA Hot Tool Room 5490_.

RCB G2' Tool Room BAaintenance Support 7660 4134-Marvin Goodiel-Lead 3422 3946 l

l Claus Hastrom(Days) 9382 3946' l

Paul Ensinger(Nights) l~

Jodi Liberski.

. FPL Maint. Support Tecli.

7216 IITLE PAY SHIFT FPL Project Field Engineer.

Wyatt Jenkins.

2149 4201 FPLTaprogge Randy Ensley 7667 3678 FPL Point / Insulation Paul Donovan 6543' 3464 FPL RCA Jerry Kunkel 5540 3629 3774 FPL RCA' '

Walt Williams -

3851 FPLTurbine Building Jim Sanford

FPL ICW

- Bill Yates -

6458 7423 FPL S/G' Andy Flowers 2572 7467 FPL Start /Up Mke Rober1 son 7480

~5351

)

FPL Freeze Seal Mike Robertson 7480 5351 4023

[

FPL Estrnating -

Irving West George Regal 2180 3344 i

FPL Electncal l

FPL Scheduling.

Doug Hibbard 3471-3152 3649 l

FPL Scheduling Pat Vaugh 3150 L

FPL Scheduling Dave Lucas l

FPL Field Engineer Eric Senkuwicz 4267

,_ u out,,, u n.,,,,n,

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PROJECTS TITLE NIGHT SHIFT FPL OUTAGE COORDINATOR Brent Butcher 3450 3487 j

Stan Niewieroski 3186

'3770 a

FPL Taprogge '

FPL Turt>ine Building -

Stan Niewieroski 3186 3770

.l FPL RCA Gene Chesser 3004 4

Jeff Jenkins -

FPL ICW 5351 FPL S/G Gary Connelly 5351

- FPL Freeze.

Gary Connelly FPL Paint / Insulation Sean Fletcher 7372 3042x FPL RCA David LeFleur 3066 Raytheon Lead Bud Price 5571 Raytheon MechanicalICW Bill Flynt Raytheon Mechanical.

Nick Ordanc.i Raytheon Mechanical John Jochums Raytheon Mechanical E. O'Neal

. Raytheon Electrical

' John Sickler 4032

. Raytheon Civil Jim Miller -

'4032

~ Raytheon Civil' John Malik 5497 Raytheon Turbine Lonnie Holt 5316 Raytheon ISI Fred Young

~'

3567 Raytheon Safety John Bishop 3804 Raytheon Tirne Office S. Dicandeloro 3804 Raytheon Time Office J.Dunn Raytheon Field Engineering 4014-Raytheon Civil Lead Dale Geib 3432 Raytheon Mechanical Larry Stafford 3815 Raytheon Mechanical Bill Palphry 3486/3778 1 Itaytheon Mechanical Joe Brannen l

4207 Raytheon Electrical Neville Mangra 3778

- Raytheon Enginering Tech.'

Linda Benson -

3500 Raytheon Engineering Tech.

Mary Senivk PROJECTS RAYTHEON CRAFT INFORMATION COLOR NAME EXI DAYS

. Boilermakers Blue C. Stone

- 3566 Carpenters Brown G. Franklin 3739 Cement Masons.

Orange R. Homsby Page:

. Electricians Yellow '

J. Prange 3146 o

Ironworkers.

Green J. Hughes 3838 insuistors Green / White G. Shepard 3502 Laborers Gray L. Hall 3073 Millwrights (Green Hat)

Brown / White J. Duke 5424

Operating Engineer BI'ack.

R. Post 3756 i

Pipofitters.

Red / White R. Harrell 3806 SheetmetalWorkers Black / White M. Vandyke 3243

. Teamsters -

Blue / White.

G. Wilhoit 3756

. Craft Representative Green W. Bryant 3807 m._,

n.........

L PWO PROCESSING I

TITLE NAME BEEPER E

Mechanical Maintenance Todd Lyons 9373 7053 l

Mechanical Carh Lamb 1018 7417 l

Electrical Sandie Chaplin 1807 7330 l

I&C Alexis Modenda 1707 7407 i

Day. Shift will be dovered. Coverage will be extended during mode changes as needed.

QUALITY CONTROL J

DEPARTMENT LEAD BEEPER M-George A. Schnebli 7001 7280 l

OUTAGE COORDINATORS l

9396 3714/7366 Ken Crosby 5361 7464 Tommy Dwyer DAY SHIFT 9391

'7462 George ingram 9397 3116 Pev Darress 9390

.,7461 Robert Hawley Andy lit sie '

1424 3713/7039 1982 3514 Mike Meiley

-9392 7277 Doug Melody 5388 3111/7333 (Bob Storms PEAK SHIFT

~

7365 Bobby Brown 9387 9399 3716/7279 Biu Hays 9388 7459

. Gary Buchanan 9394 7278 Bobby Miller 5794 3897 Tony Urevith MID SHIFT 9389 7460

. Dean Gingras Brian Moss

2643 3721

. RADIO Channels -

Mechanical Maintenance 1 and Construchon 1

WiH rotate to mids for support of radiography.

This alignment is subject to change upon final determination by Maintenance and Maintenance Projects for their shift alignments.

n.

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i i-SYSTEMS AND COMPONENTS ENGINEERING l

DEPARTMENT HEAD ASSIGNMENT RADIO BEEPER EXI Chuck Wood 714156 4310 7065 OUTAGE COORDINATORS

~ Jim Porter-Systems 710269 8746 7033 l

Joe Price p

Components 7236 7074

{

j Mike Snyder Programs 710271 2434 7036 i

Dave Stewart Systems 710606 2410 7037 NAME L

l John Campbell Gen, Swgr, Breakers 710265 4361 7057 Joe Cimino -

P-2 1387 7043 Lv'<e Clark MG Sets, PCMs, Cath Prot-710240 4362 7061 l

Gerry Crowley Rotating Equipment 710334

-7234 7052 L

Bill Dean EM Support 710245 2403 7048 L.

Randy Decker Rotating Equipment 710332 6456 7041 7075

' Bill Green Secondary 2402'

! Al Hall.

EM Support 710265 7269 7057 I

l Brian Kelly Rotating Equipment 710309 6457 7055 Roger Kulavich EDG 710252 2409 7080 l

Inman Lanier.

Valves 710335 7890

.7069 l

Victor Mendoza RCS,HVAC' 2447 7076

-l 7050 l-Teny Miller-NPRDS 7052 l

Jon Milton Rotating Equipment 710334 6455 Lisa Petrie Coordinator 710270 7064 L

Ron Rodriguez Valves 710308 7038

. Tom Sanders Valves 710308 2438 7038 7069 Ted Schmit, Valves 710335 Marty Smit Condenser 1379 7079 Scott Tumer Valves ~

710335 6447 7069 i

Mike Wachtel Motors 710220 2583 7045 I

. Doug Weeks Rotating Equipment L710252 7276 7055 Russell Wdliams Safeguards 2029 7077 l

Mark Wolaver AFW, Turbine 2418 7083 Bob Young CVCS,ECCS-8710 7063 Fax Machine 467-7560-375-7572 STA Beeper 8-375-Beeper # -

Beepers on Network Beepers off Network 1-800-447-2433 l

l 1

l

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SYSTEMS AND COMPONENTS ENGINEERING Electrical Systems / Components - Technical Support i

Component Department Primary Engineer Back Up Engineer l

Circu4 Amkens Component Jchn Campbell Luke,Clprk Engineering i

~

Component Mike Wachtel Bryan Griner Motors.

Engineering-l

Switchgear Component John Campbell Luke Clark l

l l.

Engineering l

' Battenes Component Mike Wachtel Luke Clark L

Engineering

- Relays Component Russel! Williams Luke Clark Engineenng l

Safegards/

Component Mike Wachtel RussellWilliams l

Degraded Grid Engineering

)

l Inverters Electrical Bryan Gnner John Campbell l

Maintenance i

l Chargers Electncal Bryan Griner RussellWilliams Maintenance Main Generator Component John Campbell Bryan Griner Engineering Excitabon Electrical John Campbell Al Hall (CSI)

Switchgear Maintenance Transfomrs Component Russell Williams Luke Clark Engineering Main,' Aux and S/Us Component RussellWilliams John Campbell Engineering Cathodic Protection Component Luke Clark Mike Wachtei Engineering Motor Operated Electrical Jeff Cook Dennis Boyett Valves Maintenance

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Inter-Office Correspondence f:PL JQQ-96-086 To: J. Scarola Date: July 8,1996 e From: L. W. Bladow Department: JNA/PSL

Subject:

Quality Assurance Audit OSL-PM-96-08 Attached is a summary report for QA Performance Monitoring activities completed during May/ June,1996 to assess the implementation of the Quality Assurance Program at St. Lucie. 1 The following three findings are documented in this report and have been discussed with appropriate personnel and exited with PSL Plant Management. Findine 1: Inadequate Procedures for Resin Transfer A. The procedure and methods in use during blowdown building resin transfer did not implement 4 the system operating description for Blowdown Building resin discharge as found in the FSAR. B. The procedures used to changeout typically non-radioactive resins do not provide adequate radiological controls when the resins are radioactive. C. The procedures in use during a Blowdown Building resin transfer were not being completely followed in that several radiological controls were not in place. Findine 2: Procedure No'n-compliances with Requirements for Control of Breathing Air Stations Contrary to requirements, HP Techs provided bubble hood respiratory protection with air supply pressures that exceeded procedure limits. Neither procedure HP-61 or a usable Table 1 of that procedure were available. BA station BB 029 calibration data posted with the machine was not complete. Other stations (BB003 and BB004) were found with expired calibration stickers and incomplete calibration sheets. Findina 3: Violation of Over me Guidelines A. During the period 5 through I8 May 96,12% of the sampled population exceeded one or more i i of the overtime guidelines. B. Overtime deviation requests are not being filled out and forwarded to the vault as required. C. Management reviews of overtime guideline adherence are ineffective. l

t I JQQ-96-086 i - July 8,1996 Page 2 ( L Condition Reports have been generated for the above findings. In accordance with the FPL Quality l Assurance Program, please ensure that the Condition Reports which address these findings are responded to-within 30 days of origination. As'noted in QI 16 PR/PSL-2 response to Condition ~ Reports resulting from QA audit findings must include the following: 1. The results of review and investigation of the findings including identification of the probable root cause/ causal factors. l 2. Results of your examination of potential weaknesses in departmental self-assessment programs l which may have impeded self-identification of the problem. 3. A' determination of the generic impact of the finding, i.e., whether it extends to other areas, L systems, drawings, procedures, etc., or whether it is isolated to those examples cited in the audited report. l 4. Actions taken or planned to correct the findings identified and to prevent recurr$nce of the j _ deficiency. Corrective actions should address the causal factors and enhancements to the l audited department's self-assessment program. ~ 5. Date when full corrective action was or will be achieved. ) ? 6. Identification o.f the individual (s) responsible for the corrective action. ] l For those corrective actions which cannot be completed within 90 days from the audit report transmittal, the response shall (1) include an explanation why the action cannot be completed within j 90 days and (2) include both the cognizant Vice President (or Director where the Director is a direct

report of the President - Nuclear Division) and the Director - Nuclear Assurance on distribution.

.- An evaluation should be made of the findings identified in this audit to determine reportability. We sincerely appreciate the cooperation we received from your staff during the course of the audit. Please contact me at extension 7111 or the respective QA contact if you have any questions. l h.- l L; W. Bladow l . Quality Manager-PSL ? ' LWB/JTV/str ' l ~ Attachment l. t 1

QUALITY ASSURANCE DEPARTMENT ~ l AUDIT REPORT DISTRIBUTION AUDIT REPORT: OSL-PM-96-08 PLANT / DEPARTMENT: St. Lucie Plant t NUMBEICQF FINDINGS: Three o CNRB Standard Distribution R. J. Acosta - JNA/JB T, F. Plunkett - JEX/JB W. H. Bohlke - VP/JB T. V. Abbatiello - JNA/PTN J. A. Stall - VP/PSL L. W. Bladow - JNA/PSL R. J. Hovey - VP/PTN R. A. Symes - JNA/JB G. J. Boissy - JPN/JB D. A. Culpepper - JPN/JB Dr. K. R. Craig - JPN/JB QAD Files w/ Checklist & Audit Plan Cheryl Robinson - JNA/JB H. N. Paduano - JPN/JB Health Physics & Cheraintry Related Audits Dr. W. R. Corcoran (CNRB) Manager Nuclear Health Physics / Chemistry D. B. Miller (CNR 3) Frnereency Preparedness Related Audits Manager - Nuclear Emergency Preparedness

CNRB Files: K. E. Gutowski Nuclear Tr=Inine Related Audits j

Audit Specific Distribution ' Manager Nuclear Traimng M. Miller -USNRC Plant Snecific Security Audits E. Weinkam C. Burton Security Supervisor J. Marchese Services Manager H. Johnson T. Menocal Fire Protection Audits H. Buchanan S. Martin, Risk Management C. Wood R. Dawson ~ D. Denver

Only distribution outside the plant for Security Audits containing Safeguards information.}}

ML20148E888

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