IR 05000302/1987004
| ML20205N480 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/19/1987 |
| From: | Stetka T, Tedrow J, Wilson B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20205N467 | List: |
| References | |
| 50-302-87-04, 50-302-87-4, NUDOCS 8704030036 | |
| Download: ML20205N480 (15) | |
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UNITED STATES pm Rf 0 0g'o NUCLEAR REGULATORY COMMISSION g
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REGION ll g
,j 101 MARIETTA STREET.N.W.
- ATLANTA, GEORGI A 30323
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Report No.:
50-302/87-04 i
Licensee:
Florida Power Corporation 3201 34th Street, South St. Petersburg, FL 33733 i
Docket No.:
50-302 License No.:
DPR-72 Facility Name: Crystal River 3 l
Inspection Dates:
February 6 - March 6,1987 Inspectors: bh d
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T Stetka, Senior Resident / Inspector
/ Da'te Signed h.F*h~$h
/,1 3/19/8 )
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4f E. Tedroy, Resident Inspepor
' Date Signed i
Approved by:
M (G_
$1 3/ D!D B.' A. Wison, Section ChTsT/
D' ate 'Si gned Division of Reactor Projectt SUMMARY
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Scope: This routine inspection was conducted by two resident inspectors in the areas of plant operations, security, radiological controls, Licensee Event
Reports and Nonconforming Operations Reports, facility modifications, and
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licensee action on previous inspection items.
Numerous facility tours were conducted and facility operations observed.
Some of these tours and observations were conducted on backshifts.
l Results: No violations or deviations were identified.
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8704030036 870320 PDR ADOCK 05000302
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j REPORT DETAILS 1.
Persons Contacted Licensee Employees e
- J. Alberdi, Manager, Nuclear Site Support
- W. Bandhauer, Assistant Nuclear Plant Operations Manager
- G. Becker, Manager, Site Nuclear Engineering Services
- J. Brandely, Nuclear Security and Special Projects Superintendent
- P. Breedlove, Nuclear Records Management Supervisor W. Brewer, Nuclear Engineer
- J. Buckner, Nuclear Compliance Specialist
- J. Colby, Manager, Nuclear Mechanical / Structural Engineering Services
- J. Cooper, Superintendent, Technical Support J. Ensley, Nuclear Engineer
- P. Ezzell, Radiochemistry and Environmental Specialist
- R. Fuller, Senior Nuclear Licensing Engineer
- V. Hernandez, Senior Nuclear Quality Assurance Specialist
- B. Hickle, Manager, Nuclear Plant Operations
- M. Kirk, Nuclear Operations Engineer
- M. Mann, Nuclear Compliance Specialist R. Marckese, Nuclear Engineer P. McKee, Director, Nuclear Plant Operations
- L. Moffatt, Nuclear Safety Supervisor
- R. Murgatroyd, Nuclear Maintenance Supervisor W. Neuman, Supervisor, Inservice Inspection (ISI)
- R. Pinner, Nuclear Chemistry Supervisor
- J. Roberts, Nuclear Chemistry Manager
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- S. Robinson, Nuclear Waste Manager
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- W. Rossfeld, Nuclear Compliance Manager
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E. Simpson, Director, Nuclear Operations Engineering & Licensing
- S. Sullens, Senior Nuclear Electrical /I&C Supervisor
- D. Sullivan, Nuclear Mechanical / Building Services Clerk
- E. Welch, Manager, Nuclear Electrical /I&C Engineering Services R. Widel, Manager, Nuclear Operations Licensing & Fuel Management D. Wilder, Radiation Protection Manager K. Wilson, Manager, Site Nuclear Licensing R. Wittman, Nuclear Operations Superintendent Other personnel contacted included office, operations, engineering, maintenance, chemistry / radiation and corporate personnel.
- Attended exit interview i
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Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on March 6, 1987.
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meeting, the inspector summarized the scope and findings of the inspection l
as they are detailed in this report with particular attention on the
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Unresolved Items (UNR) and Inspector Followup Items (IFI).
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The licensee representatives acknowledged the inspector's comments and did l
not identify as proprietary any of the materials provided to or reviewed l
by the inspectors during this inspection.
3.
Licensee Action on Previous Inspection Items I
(Closed) IFI 302/86-14-03:
The licensee has revised procedure SP-523 (revision 17, dated September 18, 1986) to include a place to record the final battery bank voltages.
(Closed) IFI 302/86-23-04: The licensee has issued revision 3 to drawing FD-302-285, Lube Oil System for the Emergency Diesel Generators, to delete valves DLV-1 and DLV-2.
(Closed) IFI 302/86-23-10: The licensee has added the Woodward governor on EFTB-1 to the plant's PM schedule.
The governor will be removed and returned to the manufacturer for refurbishment every five years.
l (Closed) IFI 302/86-38-06:
The licensee has added the reactor building accelerometer package inspection to the plant's PM schedule.
The accelerometer will be inspected on a monthly basis to check for humidity
and replace the desiccant as needed.
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(0 pen) IFI 302/86-38-01: The licensee's continued search for radioactive
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l gas leaks in the Auxiliary Building (AB) has identified the following additional leaking components:
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Valves WDV-465, MUV-139, MUV-255, MUV-49; and,
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Packing gland leak-off lines that go to the floor drains for valves
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l MUV-16, MUV-29, and MUV-23.
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This item remains open pending resolution of these various leak problems l
within the AB and the weld weep hole leak in the Make-up Tank (MUT).
(0 pen) UNR 302/85-29-01: In a meeting with Nuclear Operations Engineering personnel and the inspectors on February 11, 1987, the licensee outlined their planned actions to resolve the problems with the Safety Listing.
The licensee's investigation into these problems indicates that I
computerization of the listing should resolve these problems; however, it i
will take about one and a half years to complete this effort.
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interim the licensee has committed to complete the following activities by l
June 30, 1987:
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Establish an index for the Temporary Changes; Expand the introduction to the Safety Listing;
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Provide more frequent updates to the listing; and, Develop a training lesson plan and training schedule for personnel
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that use the listing.
Furthermore, the licensee has committed that this training will be completed by September 1, 1987.
This item remains open pending completion of the interim actions.
(0 pen) IFI 302/86-38-14: The licensee has completed the UT inspections of the main feedwater (MFW) piping and submitted the results for the -
inspector's review. The final report, which will provide a comparison of the pipe nominal wall thickness with that of the manufacturing specifications, remains to be issued.
This item remains open pending receipt and review of the report by the inspectors.
(0 pen) IFI 302/86-09-01: Review of this issue indicates that the licensee had analyzed the calibration problem with the Emergency Diesel Generator (EDG) tachometers and determined that if the tachometers are set at the speed of a calibrated tachometer, i.e., a one point calibration, that they would remain in calibration.
This type calibration was performed on the tachometers.
During a plant tour on March 5, however, the inspector observed that the tachometer on the
"A" EDG was out of calibration.
Therefore, it appears that the licensee's resolution to this problem was not effective. This item remains open pending further action on this item by the licensee.
(Closed) Violation 302/86-23-08:
The licensee has revised procedure SP-434, Fuel Storage Pool Missile Shields, as revision 20 on 02/19/87.
This new revision appears to provide adequate instructions for installation of all the missile shields.
(Closed) UNR 302/82-28-04:
Surveillance procedures for the plant ventilation systems were revised as follows:
SP-185, Reactor Building Ventilation Exhaust System Testing,
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revision 13 dated 01/14/87; i
SP-186, Control Room Emergency Ventilation System Testing,
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revision 14 dated 11/21/86; and,
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SP-187, Auxiliary Building Ventilation Exhaust System Testing,
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revision 13 dated 11/21/86.
These revisions were reviewed to verify that the acceptance criteria were in accordance with the TS, that the procedures provide for review and i
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l approval of the vendor's procedures, ~and that the procedures provide
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adequate instructions for the performance' of the necessar" testing.
(Closed) IFI 302/84-30-01:
Procedure SP-425, Control Rod Drive Patch l
Panel Access Control, has been revised to remove any nonexistent information and to assure that all necessary additional surveillances are conducted.
(Closed) UNR 302/86-20-03:
Procedure SP-201, Accessible / Inaccessible Hydraulic Snubbers Visual Inspection, has been revised to require the i
recording of the "as found" and "as left" fluid levels.
If the level is i
not appropriate, the procedure then requires that fluid be added (if a
Power Piping Snubber) or the snubber be replaced (if an ITT Grinnell Snubber) at the time of discovery.
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(Closed) IFI 302/85-21-04:
The licensee has reviewed this event and determined that the loose contact on relay 0213 which is in the control
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circuit of circuit breaker 3206 would not have rendered the breaker inoperable. Additionally, relay 0213 was replaced with a new style relay
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in accordance with modification (MAR) 85-05-13-01A on 06/25/86 because the old style relay had become obsolete.
(Closed) Violation 302/86-12-02:
The licensee has completed and the I
inspector has verified the completion of the following items:
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Item a (
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Personnel involved in the improper installation were counseled on l
06/27/87; and, l
All applicable personnel received retraining on the use and purpose
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of maintenance procedure MP-149, Check Valve Cap Removal and Reinstallation, as documented on the training attendance lists. This training was completed on 04/14/86.
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Item b A Memo from Nuclear Engineering (NE), dated 08/14/86, documented NE
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review of the vibration test data and concluded that the data did not warrant pump shut down; and, A Management Review Board was held on 03/19/86 to review the event.
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This board established the causes of the event and stipulated the necessary corrective actions. The necessary corrective actions were l
completed by all plant engineering personnel on 08/01/86 as
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documented by individual signatures.
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Item c l
Purge fan operation was immediately secured on 03/12/86 and the event
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l was subsequently reported as a Non-Conforming Operations Report (NCOR). Additionally, on 03/14/86 an Interoffice Cotrespondence was
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written to provide immediate instructions on equipment hatch j
operation; and, i
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Procedure MP-114, Removal and Rein 3.tallation of the Equipment Hatdi,
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was revised to. require personnel to hatify (and sign for same) the Outage Shif t Mariager and Nuclear Shift Supervisor prior to ye00&g~ '
the equipment batch.
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(Closed) Violation 302/86-31-01:
The licsnsee has ceipleted and the inspector has verified the completion of the following items:
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Procidures OP-402, Makeup anc Purification Sy's +,ey, and CP-408,
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Nuclear ServiteLCooling Systed.- have been eevised t? r2 quire that at '
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least' one Makeup, Pump (MVP) be,' cooled from the Dec ty Heat Clo ed Cycle Cooling Water (DC) systen.(t all. times;
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Procedure SP-344C, Nuclear SerOces Valve and Containment,Co'olng g
System Supply Operability, vas revised to ads. indepein'ent ve6 fication signnffs;
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An Interoffice Co respondence, dated 11/14/86, was s r.nt to all.
app 1,1 cable personnel reminding them that if a, procedure.. requires th?
ac:omplishment of an Qndependent ve-ification, that the procec'cre s
Fave appropriate steps ta accomplish this verification;
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An Interoffice Correspondence, de ed 01/05/'.s7, dor.umen ted the operation's section raview of all jurveillance precedures te ass are that all independent verificatior< requirements were being mp ; 4,
Special guidanca dated' 12/15/a6 was issue... to Nuclear Operations
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Personnel to clarify how the 10 CFR 50.59 Safety Ev;1uatNns are to
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Se perfo'rmed.
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(Closed) Violation 302/86-35-01:
.The 1 ice..see tii, coupleted >nd the
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inspector has verified the completion of the following items:
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Valves. DCV-95 and DCV-96 Were re positioned and a review of 6,ilar
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cleerances was concucted to assde that no further errors = is ac' as documented in a Memarandum dated 02/05/87;
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Proceduce compliance tra cing was conducted by tm Nuclear ihift
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Supervtsors on 12/16/86 foroperationsdepartmentppsonnel;
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Proc.edure FP-601, Fuel.Mandl1r.; Equipment Operations, was revised to clarify the directions for locking the,;ontrol console doors. on' the Spent Fuel Bridge;
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Procedure. CP-115, In plant Equipment Cie4rance and Swf tching Orde'rs,
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was -revised to' require valve and/or breaker return-to-1ormal positions be obt6f ned fm r.pproved arm current procwe as 1.1 lieu cf plan diagran s; f
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'f A.nN "Proced. ore Conformance Checklist" was developed and implemented
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,;9 (n 12/29/86. ' This checklist requires a check of cross references as ti jntegral part of the procedure review process; and, K.
P Wcedure JM-202, Duties of the Emergency Coordinator, was revised to
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ccrecct the. procedure cross references.
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"Unresolyrd Item's-s
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I Unresolved \\ items 'are matters about which more information is required to l
determine whether they are acceptable or may involve violations or deviations. New unr'esolved items are identified in paragraphs 5.b.(9)(a)
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and 6.b.(2) of this report.
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5.
Review of Plant 6peratioris j,
L The plant remai[ned in power operation (Mode 1) for the duration of this
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Shift Logs and Facility Records
l The insp6ctor reviewed records and discussed various entries with
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op' stations. personnel to veri fy compliance with the Technical
g tecifications (TS) and the licensee's administrative procedures.
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The following records were reviewed:
Shift Supervisor's Log; Reactor Operator's Log; Equipment f
Out-Of-Service Log; Shift Relief Checklist; Auxiliary. Building jN Opeyator's Log; Active Clearance Log; Daily Operating Surveillance Log; Work Request Log; Short Term Instructions (STi); and Selected Chemistry / Radiation Protection Logs.
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In addiiion to these record reviews, the inspector independently J
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verified clearance order tagouts.
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No violations or deviations were identified.
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b. 7 Facility Tours and Observations i
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p Throughout the inspection period, facility tours were conducted to
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observe operations and maintenance activities in progress.
Some operations and maintenance activity observations were conducted
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during backshifts.
Also, during this inspection period, licensee mr.etings were attended by the inspector to observe planning and
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management activities.
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.The facility tours and observations encompassed the following areas:
i security perimeter fence; control room; emergency diesel generator
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room; auxiliary building; intermediate building; battery rooms; and,
. ' electrical switchgear rooms.
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During these tours, the following observations were made:
s (1) Monitoring Instrumentation - The following instrumentation was observed to verify that indicated parameters were in accordance with the TS for the current operational mode:
Equipment operating status; area atmospheric and liquid radiation monitors; electrical system lineup; reactor operating parameters; and auxiliary f equipment operating parameters.
No violations or deviations were identified.
(2) Safety Systems Walkdown - The inspector conducted a walkdown of the Decay Heat Closed Cycle Cooling (DC) system to verify that the lineup was in accordance with license requirements for system operability and that the system drawing and procedure correctly reflect "as-built" plant conditions.
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No violations or deviations were identified.
(3) Shift Staffing - The inspector verified that operating shift
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staffing was in accordance with TS requirements and that control room operations were being conducted in an orderly and professional manner.
In addition, the inspector observed shift turnovers on various occasions to verify the continuity of plant status, operational problems, and other pertinent plant information during these turnovers.
No violations or deviations were identified.
(4) Plant Housekeeping Conditions - Storage of material and i
components and cleanliness conditions of various areas throughout the facility were observed to determine whether safety and/or fire hazards existed.
No violations or deviations were identified.
(5) Radiation Areas - Radiation Control Areas (RCA) were observed to verify proper identification and implementation.
These observations included selected licensee conducted surveys, review of step-off pad conditions, disposal of contaminated clothing, and area posting. Area postings were-independently verified for accuracy by the inspectors. The inspectors also reviewed selected radiation work permits and obser<ed the use of protective clothing, respirators, and personnel monitoring devices to assure that the licensee's radiation monitoring policies were being followed.
- No violations or deviations were identified.
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(6) Security Control - Security controls were observed to verify that security barriers were intact, guard forces were on duty, and access to the Protected Area (PA) was ~ controlled in accordance with the facility security plan.
Personnel within the PA were observed to verify proper display of badges and that personnel requiring escort were properly escorted.
Personnel within vital areas were observed to ensure proper authorization-for the area.
No violations or deviations were identified.
(7) Fire Protection - Fire protection activities, staffing and equipment were observed to verify that fire brigade staffing was appropriate and that fire alarms, extinguishing equipment, actuating controls, fire fighting equipment, emergency equipment, and fire barriers were operable.
No violations or deviations were identified.
(8) Surveillance - Surveillance tests were observed to verify that approved procedures wert being used; qualified personnel were conducting the tests; tests were adequate to verify equipment operability; calibrated equipment, was utilized; and TS requirements were followed.
The following tests were observed and/or data reviewed:
- SP-110, Reactor Protective System Functional Testing;
- SP-146, EFIC [ Emergency Feedwater Intiation and Control System] Monthly Functional Test;
- SP-187, Auxiliary Building Ventilation Exhaust System Testing;
- SP-312, Heat Balance Calculations;
- SP-317, RC [ Reactor Coolant] System Water Inventory l
Balance;
- SP-3408,
"B" Train ECCS [ Emergency Core Cooling System]
Pump & Valve Operability; and,
- SP-702, Reactor Coolant & Decay Heat Daily Surveillance Program.
No violations or deviations were identified.
(9) Maintenance Activities - The inspector observed maintenance i
activities to verify that correct equipment clearances were in effect; work requests and fire prevention work permits, as
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required, vere issued and being followed; quality control personnel were available for inspection activities as required; and TS requirements were being followed.
Maintenance was observed and work packages were reviewed for the following maintenance activities:
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Alignment check of the pump / motor shaft for the "B" Decay
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Heat Removal pump (DHP-1B) in accordance with procedure l
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Voltage adjustments to the "B" and "D" battery chargers (DPBC-1B and DPBC-10) in accordance with procedure PM-141; Checking, cleaning and testing of the
"B" Emergency Diesel
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Generator (EDG) output breaker (breaker #3210)
in accordance with procedure PM-101;
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Troubleshooting of the "A" steam generator overfill control valve EFV-14, in the
"D" channel of the Emergency Feedwater l
Initiation and Control (EFIC) system in accordance with procedure MP-531 and SP-146;
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Replacement of check valve RWV-36 in the Nuclear Services Seawater System in accordance with procedures MP-122, MP-132, and SP-344A;
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Replacement of the air start air compressor on the "A" EDG in accordance with a Work Request (WR) and modifications (MARS) 87-01-17-01 and 87-01-17-02; and,
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Replacement of opto-isolator in the EFIC system channel A in accordance with Procedures MP-531 and SP-146.
As a result of these reviews the following items were identified:
(a) During the performance of procedures PM-101, 4.16 ' KV and 6.9 KV Switchgear, and PM-141, Tolerances and Set Points for Battery Chargers, the inspector noticed a lack of specific guidance to the craft performing the work.
Specifically step 7.2.8 of procedure PM-101 requires
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resistance measurements be taken on the breaker's blow out coils, and step 7.4.5.2 requires a breaker insulation test y
be conducted.
No acceptance criteria was specified for these steps in the procedure. The workers were questioned about the adequacy of the results obtained but did not know if the results were satisfactory.
The electricians contacted the shop supervisor who did know the procedure's intent and the acceptance criteria.
All results were
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satisfactory.
This matter was discussed with the shop supervisor who stated that the procedure could be clarified to avoid confusion in this area.
During the performance of procedure PM-141, the inspector observed the workers set the battery charger's float voltage and equalizer voltage in accordance with sections 7.4 and 7.5 of the procedure.
The workers then proceeded to adjust the current limiting device in accordance with section 7.6.
This section requires that the previously established float and equalizer voltages be adjusted to set the current limiting device. No requirement exists in the procedure to readjust the float and equalizer voltages back to acceptable values when the craft.is finished with this step.
In this instance the workers realized this readjustment was necessary and subsequently re performed sections 7.4 and 7.5 of the procedure.
The inspector informed the shop supervisor of this potential problem.
Also the inspector noticed that the procedure requires setpoints be recorded for the high and low AC and DC voltage alarms. However, these setpoints are required to be taken after the devices are adjusted to actuate the alarm and before the final setpoint is established.
Therefore, no "as found" or "as left" setpoints are specified to be recorded.
The inspector discussed the intent of this step with the shop supervisor who replied that the "as lef t" setpoint was the desired value to be recorded. The licensee plans to make appropriate changes to the procedure to clarify these steps.
In NRC Inspection Report 50-302/86-09, the licensee was
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cited for failure to have an adequate PM procedure (PM-123). While the observations discussed herein did not result in inadequate PM performance as' occurred with PM-123, it does indicate a possible. inadequacy with the PM.
procedures.
These observations and conclusions were discussed with licensee management personnel. The licensee acknowledged the ' inspector's concerns and will review all PM procedures.
l UNR (302/87-04-01):
Review the preventive maintenance
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l procedures to determine the adequacy of these procedures.
(b) During the post-maintenance test performed on DHP-1B, the workers appeared confused when measuring / recording pump
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vibration readings.
The measuring device utilized had
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several different scales to choose from to indicate displacement and velocity readings. These measurements are taken by one worker and recorded by another. Communication between the two workers is extremely hampered by the noise
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generated by the running pump.
Several readings recorded appeared to be inaccurate. When the inspector requested that these readings be taken again it was discovered that the readings were in error. This matter was discussed with licensee management personnel who stated that refresher training on the correct use of the measuring device would be given to the mechanics before taking future vibration measurements.
This refresher training course was conducted on February 18-20. From review of the attendance sheets and the course outline, the inspector judged that this training should be effective in preventing recurrence of such activities.
(10) Radioactive Waste Controls - Selected liquid and gaseous releases were observed to verify that approved procedures were utilized, that appropriate release approvals were obtained, and that required surveys were taken.
No violations or deviations were identified.
(11) Pipe Hangers and Seismic Restraints - Several pipe hangers and seismic restraints (snubbers) on safety-related systems were observed to insure that fluid levels were adequate and no leakage was evident, that restraint settings were appropriate, and that anchoring points were not binding.
No violations or deviations were identified.
6.
Review of Licensee Event Reports and Nonconforming Operations Reports a.
Licensee Event Reports (LERs) were reviewed for potential generic impact, to detect-trends, and to determine whether corrective actions appeared appropriate. Events, which were reported immediately, were reviewed as they occurred to determine if the TS were satisfied.
LERs 86-26 and 87-04 were reviewed in accordance with current NRC policy.
LER 86-26 is closed.
LER 87-04 remains open.
(0 pen) LER 87-04:
This LER reported the failure to comply with TS radioactive gas effluent monitoring requirements.
This LER will remain open pending revision to procedure OP-412 to clarify flow rate estimation requirements, b.
The inspector reviewed Nonconforming Operations Reports (NCORs) to verify the following: compliance with the TS, corrective actions as identified in tt.e reports or during subsequent reviews have been accomplished or are being pursued for completion, generic items are identified and reported as required by 10 CFR Part 21, and items are reported as required by T.
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All NCORs were reviewed in accordance with the current NRC Policy.
As the result of these reviews, the following items were identified:
(1) NCOR 87-36 identified that a pressure switch (DD-47-PS) for controlling bearing flush water to the nuclear services and decay heat seawater pumps had been changed from the original Static '0' Rings switch to a United Electric switch due to part unavailability. This item was found during a review to update the surveillance procedure for the new part. The old switch was removed in 1985 when. it failed to pass a surveillance calibration check and the switch assembly was found full of water.
The new switch appears to be working satisfactory; however, the " proof" pressure (the maximum pressure which the manufacturer recommends - the switch to be exposed to (25 psig))
is less than the normal system operating pressure (32 psig).
This matter has been referred to the licensee's engineering staff to evaluate the continued use of this switch in this application and the effect on system operation.
IFI (302/87-04-02):
Review the engineering evaluation for the use of a United Electric switch for controlling flush water to
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the nuclear services and decay heat seawater pumps.
(2) NCORs 87-27, 87-28, and 87-35 reported surveillance testing
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deficiencies with surveillance procedures SP-130, Engineered j
Safeguards Monthly Functional Tests, and SP-358 (A,B,C),
l Operations ES Monthly Automatic Actuation Logic Functional Test (#1,#2,#3).
In NRC Inspection Report 50-302/87-01, the events reported in NCORs 87-27 and 87-28 were discussed and considered to be a licensee identified violation in which adequate corrective action was taken to prevent recurrence. However, the issuance of NCOR 87-35, which identified the. discovery of
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additional discrepancies, appears to indicate that the previously taken corrective actions may not have been adequate.
The licensee is continuing to review these procedures to assure that no further discrepancies exist. This item is considered to be Unresolved pending completion of f the licensee's review and implementation of corrective actions and subsequent review by the NRC.
UNR(302/87-04-03): Review procedures SP-130 and SP-358 (A,B,C)
to insure that no further testing deficiencies exist.
(3) NCOR 87-34 reported that the valve internals for valve MUV-16 were replaced with that of a.different manufacturer and that no Modification (MAR) package was generated to cover this change.
To correct this discrepancy, a MAR was written and implemented to identify the correct internals for this valve.
During the inspector's review of this NCOR, it was noted that during the valve work some debris in the form of a crystalline
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and metallic substance was - found in the valve body.
The licensee has sent this debris to a contractor for analysis but has not yet received the results of this analysis.
Additionally, the licensee is examining the types of packing in use on the valve since it is speculated that the packing may have had an effect upon the operation of the valve.
The licensee's progress on these items will be tracked as an IFI.
IFI (302/87-04-04): Review the analysis for the debris in valve MUV-16 and the final packing determination for this valve.
!
(4) NCOR 87-39 reported the failure of check valve RWV-36 to shut.
i This check valve is located in the Nuclear Services Seawater (RW) system and has since been replaced by a new valve.
An
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engineering investigation is underway to determine the affects
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of this failure on the RW system operability.
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IFI (302/87-04-05):
Review the results of the engineering investigation into the RWV-36 valve failure.
.
7.
Design, Design Changes and Modifications Installation of new or modified systems were reviewed to verify that the i
changes were reviewed and approved in accordance with 10 CFR 50.59, that
the changes were performed in accordance with technically adequate and
approved procedures, that subsequent testing and test results met acceptance criteria or deviations were resolved in an acceptable manner, f
and that appropriate drawings and facility procedures were revised as
,
necessary.
This review included selected observations of modifications and/or testing in progress.
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l The following modification approval records (MARS) were reviewed and/or
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associated testing observed:
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MAR 87-01-17-01, Emergency Generator Pump (EGP) Pipe Coupling;
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MAR 87-01-17-02, EGP Unloader Piping;
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MAR 86-04-20-01, Reactor Trip on High Pressure Setpoint;-
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MAR 86-11-19-01, Anticipatory -Reactor -Trip on Turbine Trip Setpoint
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Increase; and,
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MAR 87-02-03-01, Return MUV-16 to Original Configuration.
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No violations or deviations were identified.
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8.
Review of Special Reports l
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i The licensee submitted a special report, dated - February 23, 1987, j
regarding noncompliance with 10 CFR Part 50 Appendix J requirements for j
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containment air lock testing.
Due to confusion between the Technical
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Specification -(TS) 4.6.1.3.b, which is allowed a 25% extension by TS 4.0.2.a and Appendix J which does not allow an extension, the six month interval for the Type B test of the containment air locks had been exceeded. The licensee has implemented a tracking system which should i
prevent the recurrence of this event. Action on this matter is considered
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complete.
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