IR 05000387/1985024
| ML17139D130 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/14/1985 |
| From: | Anderson C, Chung J, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17139D129 | List: |
| References | |
| 50-387-85-24, 50-388-85-20, NUDOCS 8508270055 | |
| Download: ML17139D130 (17) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report Nos.
50-387/85-24 50-388/85-20 Docket Nos.
50-387 50-388 License Nos.
NPF-14 NPF-22 Priority Category C
Licensee:
Penns lvania Power and Li ht Com an 2 North Ninth Street Allentown Penns lvania Facility Name:
Sus uehanna Steam Electric Station Units 1 and
Inspection At:
Berwick Penns lvania Inspection Conducted:
Jul 22-26 1985 Inspectors:
i W. Chung, Lea eacto Engineer r-r~
date a li o, a
act Eng neer ate g. )y/~~
Approved y:
C. J. Anderson, Chief, Plant Systems Section date Ins ection Summar
di i
fli controls; preventive and corrective maintenance programs for instrumentation and controls; implementation of maintenance programs; overview of proposed swing diesel generator; and facility tours.
The inspection included 86 ~inspec-tor-hours on-site by two region-based inspectors.
Results:
Noncompliance:
None.
Deviation:
None.
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DETAILS 1.0 Persons Contacted Bartos, J. A., I&C/C Supervisor Brouse, R.A., Electrical Maintenance Foreman Crimmins, T.M., Plant Superintendent Eustice, E.A.,
QC Supervisor (Acting)
Glaser, G.T., Unit 2 I&C Foreman
"Keiser, H., Vice President, Nuclear Operation Markowski, T.,
Day Shift Supervisor Nork, T., Maintenance Engineer
- O'Neil, L. D., Maintenance Supervisor Palmer, H., Supervisor of Operations
~Poley, R., Compliance Engineer
"Prego, R.J., Operations QA Supervisor Roche, T.,
Lead Project Engineer, EDGE group Robinson, G.E., Unit
I&C Foreman Sitler, D., Senior Result Engineer Willie, L.K., PMIS Supervisor USNRC Plisco, L.R., Resident Inspector 2.0 3.0 The inspector also held discussions with other licensee employees during the inspection, including operations, technical supports, and adminis-trative personnel.
~Denotes those present at the preliminary exit meeting on July 26, 1985.
Administrative Controls for Maintenance Activities Administrative controls were reviewed to determine the licensee's program for implementing requirements associated with the corrective and pre'-
ventive maintenance activities.
The inspection was conducted to assure that the licensees program was consistent with the Technical Specifi-cations, Regulatory Guide 1.33, ANSI N18.7 and
CFR 50, Appendix B.
Documents reviewed are listed in Section 5.0.
Within the scope of this inspection, no unacceptable conditions were, identified.
l Maintenance Pro ram 3. 1 Corrective Maintenance The inspector verified by review of the station administrative
~
procedures and licensee responses to the generic letter 83-28 (Salem ATWS event) that:
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criteria and responsibilities were identified; and f
administrative controls for routine and emergency mainte ance were established; safety related maintenance versus non-safety related maintenance was identified; maintenance records were properly reviewed and stored; QC hold points were established; Programmatic controls for post-maintenance testing were established to assure that work activities were carried out in a safe manner.
li 3e2 Preventive Maintenance The inspector verified by review of Plant Maintenance Information System (PMIS) procedure, unit daily priority lists, and computer printouts that a program was established for controlling PM activi-ties.
The program included systems identified in Technical Speci-fications and other systems required to assure reliable operation of various safety related equipment.
The PM frequency and the respon-sible department for a particular PM were identified by the corres-ponding procedure number as well as the responsibility for documen-tation and review.
The licensee has a program for releasing and returning to servi,ce plant equipment or systems undergoing corrective or preventive I
maintenance.
The program assures that the status of equipment, is documented and allows for QA verification as per Work Authorization (WA) and Equipment Release Form (ERF).
3.4 S ecial Processes The inspector verified that a program was developed for controlIling special processes which included provisions for welding, fire pro-tection and process controls.
3.5
~Findin s
~ki i
i
~ih h
physical plant is maintained in a good state.
I
~Ta in
Color-coded tags and chain-locks were observed.
li uI
QA/gC: The inspector verified by review of maintenance records that QA/QC coverage during maintenance activities is adequate.
However, the inspector observed on July 24, 1985 at 1: 10 p.m. that a Noncon-formance tag was posted on the unit 1 HPCI pump room flood gate.
A subsequent review of NCR ¹82-1206 revealed that a
ramp generator and signal converter for the HPCI controls were removed for rework, and that the tag should have been attached to the converter ratherI than on the door.
Furthermore, the NCR disposition was made and signed by the I&C foreman on January 22, 1983 but the tag was dated March 28, 1984.
The inspector expressed concern regarding the posting of a ne, tag without verifying the status of the equipment.
A QC representative stated that the original NCR tag was attached to the converter,',
and was lost when the converter was removed from the pump room.
On July 26, 1985, the licensee issued a memorandum which emphasized th'
station practices on NCR tags and reissuing a
new tag should t)e original tag be lost.
This memo was intended to prevent recurrence of posting NCR tags in the wrong place.
The inspector determined that this was an isolated case and did not degrade station safety.
PMIS:
The Plant Maintenance Information System (PMIS) is an auto-mated computer information retrieval and tracking system for survei 1-lance, corrective and preventive maintenance, and WA activities.
New supervisory personnel were assigned on the system for administII'ative control of the PMIS and were in the process of training.
ii Post Maintenance Testin
Station procedures, AD-QA-502, Section 5. 11, AD-QA-423, and AD-QA-3-6, Section 306 delineated the require-ments for post-maintenance functional and operability testing.I'hen maintenance work was completed by each responsible department, post maintenance equipment testing was conducted by each department~,and the department turned over the equipment to the operations department for operational checks per ANSI N18.7 Regulatory Guide 1.33, generic letter 83-28 and the Appendix A, and Technical Specifications.[i However s
no written procedures nor guidelines were provided forI the operations shift supervisor performing the operational function'al checks after the maintenance activities.
This would impose a s'ub-stantial burden on the operations shift supervisor as to the post-maintenance operational tests.
This is contrary to the guideli'nes provided in the generic letter 83-28 and is an apparent programmatic inadequacy.
This item was discussed with the licensee previously by the resident inspectors.
During a meeting with the licensee repre-sentatives the NRC inspector concluded that the station is work'ing on this issue consider ing implementation and practicability of theI operational testing schedule '
Instrumentation Maintenance The following implementation procedures were reviewed Within the scope of this inspection, no regulatory issues were'dentified except the post-maintenance operability testing iss'ue, which will be further inspected by the resident inspectors.
4. 1 Procedures The inspector reviewed randomly selected instrumentation maint'enance implementation procedures and temporary changes to verify that', they conform with the criteria of the administrative procedures listed in Section 5.0 and the requirements in Technical Specifications, Section 6.8, and to verify that:
Provision exist for administrative approvals for removing'jthe item from services and returning it to service; Provisions exist to require that the latest approved drawings and instructions are used; Provision exist to assure that materials, parts, and components are correct and suitable; Provisions exist for assuring that Limiting Condition for]',.
Operation (LCO) requirements of the TS are identified and!satis-fied during the repair period including the verification of redundant system operability when required; Provisions exist for the control of housekeeping during the maintenance effort; and Provisions exists for cleaning safety related systems/components during maintenance.
Instrument Maintenance Procedures (1). Instruction No. IC-lA-02, "Calibration/Maintenance of Installed Plant Instrumentation",
Revision 0, January 1,
1985.
(2). Instruction No. IC-1A-03, "IKC/C Surveillance Scheduling",jj Revision 0, January 17, 1985.
The procedures for calibration and maintenance activities are l~isted in Section 5.0 this report.
Within the scope of this inspection, no unacceptable conditionsi were identifie.2 Safet -Related Instrument Maintenance Activities The inspector reviewed the records of preventive maintenance of HPCI and RHR Systems performed by the licensee on a sampling basis to verify that:
I,
'I Maintenance activities were performed within the frequency indicated in the maintenance schedule (schedule reviewed. covered a six year period, 1980 through 1985, see findings).
Required admini strative approvals were obtained prior to )
initiating the work.
An approved procedure was used as appropriate.
Functional testing, adjustments and calibrations as neces'sary were completed prior to returning the equipment to operation.
Data were properly filled in, records were properly signed and dated.
Records were assembled, stored and retrieved as part of t e maintenance history.
Qualified IAC personnel performed the maintenance activities.
The criteria for acceptability were met.
Records of the following preventive maintenance activities were reviewed:
(1)
4. 16 KV Breaker inspection and maintenance per procedure No. MT-GE-005 and insulation resistance test per procedure No. MT-GE-009.
Equipment No.
1A202-02, Activity No. E-0220-01.
Frequency of test - 3 years.
(2)
Valve actuator routine maintenance per procedure No. MT-GE-003.
Equipment No.
MVE111F020, activity No. E-1138-84.
Frequeqcy-annual.
(3)
PM-RHR Relay Vertical Board - Equipment No.
1C618.
Inspection for excessive signs of arcing and wire deterioration.
Cle'an and vacuum using protective gear.
Activity No. E-1017-02
'requency-Annual.
(4)
Pilot Solenoid Valve.
Equipment No.
SV15122A and SV15150A~.
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Replace coil every 3 years per instructions.
Verify coil pickup and valve operation.
Activity No. E-1310-01.
(5)
RHR Pump Motor, Cable, Breaker Double Test per Procedure'o.
MT-11-001.
Activity No. E-1666-04.
Frequency every 4 years.
Equipment No.
1A20402 and 1P202D.
(6)
Motor operated valve maintenance per MT-GE-003.
Equipment No.
MVE 111FOlSB.
Activity No. E-1450-04.
Frequency Annual.
The following WAs were also reviewed for the HPCI and RHR Systems:
A.
~WA: III Preventive Maintenance Records ( 1)
WA ¹P50661, calibration check on Unit
RHR pump suction/
discharge
"D", performed June 3,
1985 (2)
WA ¹P50612, Unit 2 RHR pump A&C Discharge Flow, performed March 27, 1985 (3)
WA ¹P50613, Unit 2 RHR pump B&D Discharge Flow, performed April 12, 1985 Corrective Maintenance Records (1)
WA ¹S56598, Unit 2 Instrument check for PY-E11-1R003B&4B, performed March 26, 1985 (2)
WA ¹S56604, Unit 1 Instrument check for TE-Ell-IN009B, performed March 19, 1985 (3)
WA ¹S57720, Unit 1 FT-15121A recalibration after water Hammer on June 8, 1985, performed July 8, 1985 (4)
WA ¹T46011, Unit 1, Loop check/calibration of Flow Instru-mentation; replaced, completed May 24, 1985 Surveillance Records (1)
WA ¹A44797, 31DY-RHR Cooler Temperature Channels (SI-,249-305) completed January 1,
1985 Preventive Maintenance Records (1)
WA ¹P50669, Unit 2, HPCI Pump Discharge Flow Calibrat'ion, completed May 1, 1985
(2)
WA ¹P50306, Unit 1, calibration check for switch/bistable per IC-DC-400 of HPCI Booster Pump, performed May 1, 1985 (3)
WA ¹P50096, calibration check for switch/bistable for Unit 1 HPCI Pump Discharge, performed March 6, 1985 (4)
WA ¹50399, Unit 1 HPCI Booster Pump Suction indicator, performed March 29, 1985 Corrective Maintenance Records (1)
WA ¹S47047, Unit 1 HPCI Reactor Vessel Injection Valve'troking and GETARS, completed February 20, 1985 (2)
WA ¹S-56333, Unit 1 PSH-E41-IN012A repair, performed April 16, 1985 (3)
WA ¹V56081, Replace Differential Temperature Elements for Unit 2 HPCI Equipment Room, completed February 5,
1985.
(4)
WA ¹S56774, Unit 1 HPCI Control Valve Control, performed May 9, 1985 (5)
WA ¹V56075, Unit 2 HPCI Barometric Condenser Vacuum Pump repair, performed January 28, 1985 (6)
WA ¹S48422, Unit 1 HPCI Turbine Generator Governor Control Speed Setting Potentiometer replaced, performed February 15, 1985 No unacceptable conditions were identified.
4.3 Ins ector's Witnessin of In-Pro ress Maintenance Activities 1.
The inspector witnessed the performance of instrument maintenance activities of selected instruments to verify that:
maintenance procedures were available and in use.
the procedures were adequately detailed to assure sati s-factory performance.
operational personnel were notified and their clearance obtained.
properly specified parts and materials were identified for the activity.
qualified test equipment and tools were used.
proper restoration of barriers and covers was accomplishe adequate functional testing was performed prior to I
returning the equipment to operations for system restora-tion.
The inspector witnessed the calibration of the followingi, instruments:
(1)
Quarterly Calibration of the'HR LPCI mode Pump Discharge Pressure - High (ADS Permissive)
channels PS-Ell-N016 A, B,
C and D in accordance with Procedure No. SI-249-302 Revision 1.
(2)
Monthly channel Functional Test of High Pressure Coolant Injection Systems Turbine Exhaust Diaphragm Pressure channels PSH-E41-N012A, B,
C and D in accordance with Procedure No. SI-52-211 Revision 1.
~Findin s
h Calibrations were performed in accordance with the procedures and met the applicable requirements.
n Documented Performance Data for Quarterly Calibration Trip Setting is noted in Table
, TABLE 1 PS-El 1-N016A PUMP Contact Action on Trip Close Desired Trip Setting pslg 125 As Found Pslg Tolerance
+4 psig 123.2 Final Setting
- pslg Tolerance
+1.2 psig 125.2 Reset psig 117.6 PS-El 1-N016C PS-El 1-NP16B PS-El 1-N016D Close Close Close 125 109.0 109.0 123.4 105.8 107.4 124.2 109.0 108.7 112.6 i,'6. 6 94.4 4.4 ILC Maintenance Personnel uglification The inspector reviewed the qualification records of four IKC techni-cians to verify that the personnel trainings and qualifications were in accordance with the requirements of ANSI N18. 1 and the station training programs, and that implementation of the training programs
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was effectiv.0 Documents Reviewed 4).
Procedure No.
MT-GE-008 Revision 6, 480 volt and under cir'cuit Breaker High Current Testing dated September 25, 1984 5.3. Calibration and Surveillance Procedures 1).
Procedure NO. SI-149-202 Revision 1, Monthly Channel Functional Test of the RHR LPCI Mode Pump Discharge 2).
Procedure No. SI-149-203 Revision 0, dated December 17, 1984 Monthly functional test of the RHR LPCI mode pump discharg'e pressure-high (ads permissive)
channels PS-E11-N020A, B,
C~',
D (Bechtel No.
PS-1N020A, B,
C, D)
Also, the inspector observed the work-in-progress by the I&C tech-nicians, and conducted an interview to ascertain that the personnel were knowledgeable, as per their trai'ning records, and qualified to perform their assigned tasks.
The inspector also noted that during the last four years, only, two out of approximately forty I&C personnel left the I&C departme'nt (from the licensee organization).
Based on this low personnel', turn-over, the inspector determined that this was indicative of goo'd management practices, and that the level of the personnel experience was adequate:
No regulatory findings were identified.
I
)I 5. 1 Administrative Control Procedures 1).
AD-QA-502, Work Authorization System, Revision 6.
2).
AD-QA-423, Station Inservice Inspection Program, Revision~,'3, July 3, 1985 3).
AD-QA-306, System/Equipment Release, Revision 5, June 10, 1985 5 '
Maintenance Procedures 1).
Procedure No. MT-52-002 Revision 2 - HPCI Turbine Maintenance dated October 14, 1983 2).
Procedure No.
MT-GM-009 Revision
Vibration Monitoring
<,
dated August 6, 1984 3).
Procedure No. MT-RC-001 Revision 2, Calibration of Electro-Mechanical and Static Relays dated December 6,
1983
3).
Procedure No. SI-149-204 Revision 0, dated December 11, 1983 Monthly channel functional test of the reactor vessel (RHR cut-i n permissive)
pressure
- high channels PS-B31-N018A and PS-B31-N018B 4).
Procedure No. SI-149-205 Revision 1, dated July 23, 1984 Monthly functional test of RHR equipment area differential temperature-high channels TDSH-E11-N601A, C, B, D.
5).
Procedure No. SI-149-206 Revision 1, dated January 28, 1985 Monthly functional test of RHR area cooler temperature high channels TSH-Ell-N600A, C, B,
D 6).
Procedure No. SI-149-302 Revision 2, dated November 19, 1984 Quarterly calibration of the RHR LPCI mode pump discharge pressure
- high (ADS permissive)
channels PS-E11-N016A, B,
C, D (Bechtel No.
PS-1N016A, B,
C, D)
I 7).
Procedure No. SI-149-303 Revision 2, dated November 13, 1984 quarterly calibration of the RHR LPCI mode pump discharge
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pressure-high (ADS permissive)
channel PS-E11-N020A, B,
C.'
(Bechtel No.
PS-1N020A, B,
C, D)
8).
Procedure No. 31-149-304 Revision 1, dated July 16, 1984 quarterly calibration of the reactor vessel (RHR cut-in per-missive) pressure-high channels PS-B31-N018A and PS-B311-N018B 9).
Procedure No. SI-149-305 Revision 1 dated May 18, 1986 Quarterly calibration of RNR equipment area differential temperature-high channels TOSH-E11-N601A, B,
C, D
10).
Procedure No. SI-149-306 Revision 0, dated January 31, 1985 Quarterly calibration of RHR equipment area temperature high channels TSH-E11-N600A, C,
B, D
11).
Procedure No. SI-149-308 Revision 0, dated June 15, 1984 18 month calibration of RHR system flow channel FT-Ell-N015B (Bechtel No.
FT-1N015B) (Remote shutdown panel)
f!
12). Procedure No. SI-149-310 Revision 0, dated September 11, 1984 I
18 month calibration of the reactor coolant system leakeage pressure-high channel PSH-E11-N022A&B (RHR system dischar'ge header high pressure, LPCI injection)
13).
Procedure No. SI-149-505 Revision 1, dated November 6, 1984 Ij 18 month residual heat removal shutdown cooling isolationtI logic system functional test il 14).
Procedure No. SI-152-201 Revision 0, dated December 20, 1983 monthly channel functional test of high pressure coolant
~~'njection (HPCI) system steam supply pressure channels PSL-E41-N001A, B,
C, D
15). Procedure No. SI-152-203 Revision 0, dated December 2,
1983 h
IJ Monthly functional test of HPCI system steam line a differential pressure channel PDIS-E41-N004 and PDIS-E41-N005 16).
Procedure No. SI-152-205 Revision 0, dated October 8, 1984 Monthly channel functional test of HPCI equipment room differential temperature channel TDSH-E41-N601A, B
17).
Procedure No. SI-152-208 Revision 0, dated December 5,
1983 II Monthly functional test of condensate storage tank low level channels LSLL-E41-N002 and LSLL-E41-N003 18).
Procedure No. SI-152-210 Revision 0, dated December 2,
1983 Monthly channel functional test of suppression pool high water level channels SLH-E41-N015A and LSH-E41-N015B 19).
Procedure No. SI-152-212 Revision 0, dated December 18, 1983 Monthly functional test of HPCI pipe routing area temperature channels TSH-E51-N603C, D
20).
Procedure No. SI-152-301 Revision 1, dated January 3,
1985I (}uarterly calibration of high pressure coolant injection (HPCI) system steam supply pressure channels PSL-E41-N001A",
B, C,
D (Bethtel No.
PSL-1N001A-D)
Ii
21). Procedure No. SI-152-303 Revision 0, dated December 18, 1983 Quarterly calibration of HPCI system steam line pressure, channels PDIS-E41-N004 and PDIS-E41-N005 22).
Procedure No. SI-152-305 Revision 0, dated January 23, 1984 Quarterly calibration of HPCI equipment room differential temperature channels:
TOSH-E41-N601A, B.
6.0 Diesel Generator
"E" The inspector reviewed the status of activities pertaining to the install-ation of the 5th Diesel Generator which will have the capability of'upplying the emergency loads for any one of the four existing diesel generators.
The addition of the 5th diesel generator is being treated as a normal plant modification with implementation of the normal operations QA program.
The modification is divided into two parts, Part I pertains to the diesel generator building and installation of support equipment in the building.
Part II is broken down into three sections pertaining to 1)
Installation of raceways, equipment, cable and hangers 2)
Request for temporary limiting condition for 60 days with one diesel (approximately 13-15 days per diesel)
out of service for operation (LCO) and 3)
Final Tie-In for each diesel.
Mork that does not affect the LCO will be done prior to LCO with detailed, step by step
"
technical procedure.
The licensee expects to have the diesel (5 megawatt Unit) on site by August, 1985.
Part I is approximately 50% complete, and Part II is approximately 10-15% complete.
Completion is scheduled for July 21, 1986.
Applicable documents reviewed by the inspector include:
General arrangement drawing Nos.
E-198216 sh.
152 Safety Evaluation No.82-382 Design Basis Document Design Change Package (DCP)
Nos
~ 83-814, and 83-814B
FI
Plant Modification Request (PMR) No.83-812, 83-813A, B,
C (4. 16KV and control system modification and transfer scheme.)
The inspector had no further questions pending subsequent inspections of the 5th Diesel Generator installation.
ll 7.
~F The inspector observed Control Room operations for shift turnover, 'log sheets, Technical Specification LCO logs, and facility operations in accordance with the administrative control procedures and license conditions.
Plant tours and system "walkthrough" observations were",
conducted including equipment tagging, lock-out, housekeeping, local indications, posting, fire protection, and radiological controls.
Ti he areas toured include:
Turbine generator, Recirculation Pump MG sets, Emergency Diesel Generators, Feedwater pumps, RHR and HPCI pump rooms, Reactor buildings, Battery and charger room, Cable spreading room.
~Findin s
During a routine tour for IEC surveillance calibration test witnessing on July 24, 1985 at 1:05 a.m.,
the inspector noted that Rosemont flow trans-mitted, B31-N014B, at area 33 of Reactor Building, Elevation 683',
was detached from its connecting pipe.
The finding was transmitted to the shift supervisor, and a
WA was subsequently issued.
Corrective action was taken the same day and the item was closed.
The inspector met with the licensee representatives denoted in paragraph 1 on July 26, 1985, and summarized the purpose, scope and findings of the inspection.
The attendees are listed in paragraph 1 of the report.
~,
At no time during this inspection was written material provided to the licensee by the inspector.