IR 05000250/1978018
| ML17338A267 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 09/29/1978 |
| From: | Robert Lewis, Verdery E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17338A265 | List: |
| References | |
| 50-250-78-18, NUDOCS 7811070320 | |
| Download: ML17338A267 (8) | |
Text
~P,R REGS i7 UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
'10'I MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303 Report Nos.:
50-250/78-18 and 50-251/78-18 Docket Nos.:
50-250 and 50-251 License Nos.:
Florida Pover and I.ight Company P. 0. Box 013100 9250 West Flagler Street Miami, Florida 33101 Facility Name:
Turkey Point Units 3 and
Inspection at:
Turkey Point Site, Florida City, Florida Inspection conducted:
August 22-25, 1978
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Inspector:
E..H. Verdery Approved by:
. C.
R.
C. Le~is, Chief Reactor Projects Section No.
Reactor Operations and Nuclear Support Branch sze~z Date Ins ection Summa Ins ection on Au ust 22-25 1978 (Re ort Nos. 50-250/78-18 and 50-251/78-18)
Areas Ins ected:
Routine unannounced inspection of organization and administration, follovup on noncompliance, unresolved items, IE bulletins and circulars, reportable events and open items.
The inspection involved 23 inspector-hours on site and 2 inspector-hours at the General Office by one NRC inspector.
Results:
In the six areas inspected, no items of noncompliance or deviations vere identifie t p
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RII Report Nos. 50-250/78-18 and 50-251/78-18 DETAILS I Prepared by: / C E. H. Verdery, Reactor Inspector Reactor Projects Section No.
Reactor Operations and Nuclear Support Branch Date Dates of Inspection:
August 22-25, 1978 Reviewed by:
-C.
R.
C. Lewis, Chief Reactor Projects Section No.
Reactor Operations and Nuclear Support Branch Date 1. Persons Contacted
~H. E. Yaeger, Plant Manager J.
K. Hays, Plant Superintendent, Nuclear D.
W. Jones, equality Control Supervisor J.
P. Mendieta, IRC Department Supervisor J.
E. Moore, Operations Superintendent, Nuclear H.
M. Ainsworth, Assistant Maintenance Superintendent W. R. Williams, Assistant Superintendent, Electrical Maintenance R. J.
Spooner, gAO Supervisor K. Beatty, Training Supervisor R. Toland, Mechanical Training Supervisor b.
General Office G. E. Liebler, Power Resources Supervisor, Nuclear M. A. Schoppman, Power Resources Specialist, Licensing The inspector contacted several operators and technical support per-sonnel not listed.
"Denotes those attending exit interview.
2.
Licensee Action on Previous Ins ection Findin s a.
Noncom liance (1)
(Closed) Infraction (77-21-02):
Inade uate Procedure for Control of, Tem ora Modifications and Jum ers:
The licensee has revised Administrative Procedure 0103.4, In-Plant Equip-
RII Report Nos. 50-250/78-18 and 50-251/78-18 I-2 ment Clearance Orders, to prohibit the issuance of clearances for hose connections to, from, or within nuclear safety-related systems or components unless either:
(1) the systems or components are considered to be out of service with respect to technical specifications; or (2) the clearance is reviewed by the Plant Nuclear Safety Committee prior to being issued.
(2)
(Closed) Infraction (78-09-01):
Failure to Re ort Hissed Surveillance:
The licensee has revised Administrative Procedure 0103.6, Reportable Occurrences, to amplify the requirement to report missed surveillance requirements as specified in the Technical Specifications within thirty days to the NRC.
The inspector emphasized that a missed surveil-lance, as defined by exceeding the 25 percent grace period allowed by technical specification, is reportable per se and that further evaluation is needed only to determine the significance of having missed the surveillance.
The licensee's position, as stated in FPL letter I.-78-231, is in agreement with this interpretation.
(3)
(Closed) Infraction (78-09-05):
Controlled Procedures Out of Date.
The inspector reviewed the licensee's corrective action as stated in FPL letter L-78-231 and had no further questions.
(4)
(Closed) Infration (78-09-06):
Tem ora
~ Modification Not Reviewed or A roved:
This item is closed based on the discussion in item 2.a.(1)
above.
b.
Unresolved Items (Closed)
(78-02-02):
Numerical Guidance for Determination of Out of Tolerance Readin s on Safet -Related Instrumentation:
The licensee has promulgated numerical guidance to the Nuclear Control Center Operators (NCCOs) to aid them in conducting channel checks of safety-related instrumentation to determine when a particular channel is out of tolerance to the extent that it should be considered inoperable.
The inspector reviewed the criteria used by the licensee to determine tolerances and agreed that the values being used are conservative.
3.
New Unresolved Items None identified during this inspectio ~
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RII Report Nos. 50-250/78-18 and 50-251/78-18 I-3 4.
Exit Interview The inspector met with Mr. Yaeger at the conclusion of the onsite
- inspection on August 24, 1978.
The inspection findings were discussed.
5.
Orphic."ation and Administration Th i: spector verified by review of records and interviews with per-sonnel that:
(1) the licensee's onsite organization structure is as descr bed in Technical Specification (TS) Table 6.2-2; (2) the key personnel qualification levels are in conformance with TS 6.3.1; (3)
the authorities and responsibilities of licensee personnel have been delineated as specified in ANSI 18.7-1972; and (4) the minimum shift crew composition of licensee personnel is in conformance with TS Table 6.2-1.
The following records were reviewed:
Site Organizational Chart, dated January 10, 1978 Personnel qualification Records.
ii..
= of noncompliance were identified.
6.
Licenso.e Actions on IE Bulletins and Circulars a
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IE Bulletin 78-06 - Cutler-Hammer e
M Rela s - In his response dated July 20, 1978, the licensee stated that the subject relays are not in use or planned for use in safety-related systems at Turkey Point.
The inspector verified the licensee's response through discussions with plant personnel and a review of facility records.
The facility has only Westinghouse and General Electric relays installed in safety-related equipment.
This item is closed.
b.
IE Circular 78-02 - Pro er Lubricatin Oil for Ter Turbines The inspector reviewed the licensee's action to determine whether the oil currently in use in the Auxiliary Feed Pump Turbines contains corrosion inhibitor.
The oil currently in use is Texaco RRO 32 (formerly called Regal Oil "A") which has been verbally certified by the vendor to contain a corrosion inhibitor.
The licensee expects to receive a letter documenting this fact from the vendor.
This item is closed.
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IE Circular 78-04 - Installation Errors That Could Prevent Closin of Fire Doors - The inspector accompanied a licensee representative in the inspection of the only two fire doors with sliding door closures of the type described in this circular.
Both door closures were examined and found to be installed correctly.
'this item is closed'
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RII Report Nos. 50-250/78-18 and 50-251/78-18 I-4 IE Circular 78-05 - Inadvertent Safet In ection Durin Cooldown:
The inspector reviewed the licensee's procedures for plant. cool-down with members of the training staff to evaluate the suscepti-bility for inadvertent safety injections during cooldown.
The standard practice is to cooldown using the atmospheric steam dump valves with the MSIVs closed.
This practice has evolved through experience and the inability to effectively control plant cooldown rates using the main condenser steam dump valves.
The facility has experienced essentially no recent problems with inadvertent safety injections using this procedure.
As part of this investigation, the inspector reviewed the safety injection system blocking functions.
The switch blocks SI initia-tion for the (1) low pressurizer pressure coincident with low pressurizer level, (2) high steam line flow coincident with low steam header pressure and (3) low Tavg coincident with high steam line 6 P, if certain permissives are met.
The permissive require-ment for blocking SI initiation on high steam line flow 2/3 loops coincident with low steam header pressure 2/3 or low Tavg 2/3 is that 2/3 Tavg channels must be below 543 F.
The permissive requirement for blocking SI initiation on low pressurizer level coincident with low pressurizer pressure 1/3 pairs, and high steam line b P, 2/3 per steam generator, is that 2/3 pressurizer pressure channels must be below 2000 psig.
Essentially all SI initiation functions except high containment pressure are manually blocked by the time pressurizer pressure is below 2000 psig.
The events described in the circular will normally not occur at Turkey Point because the SI initiation on high steam line b P is blocked shortly after the plant cooldown is commenced, i.e.,
when primary pressure is reduced below 2000 psig.
This item is the subject of an active review by the Division of Operating Reactors, Office of Nuclear Reactor Regulation, and will remain open (78-18-01).
Additionally, the inspector verified that the licensee has proce-dures currently in effect which address all necessary actions by the NCCO prior to and after an SIS reset.
These procedural steps are essentially contained in the Loss of Offsite Power Procedure.
e.
IE Circular 78-08 - Environmental uglification of Safet -Related Electrical E ui ment at Nuclear Power Plants - The inspector reviewed the status of the licensee's program for review of the environmental qualification of installed safety-related electrical components.
Some effort has been expended by the licensee to determine which components would be susceptible to long term hostile environments (i.e., high temperature, pressure and humidity)
in the post accident condition.
However, as of August 25, 1978,
RII Report Nos. 50-250/78-18 and 50-251/78-18 I-5 no formal program had been established which would provide a
coordinated review oi this problem.
During discussions with licensee personnel at the General Office, the inspector requested that such a program be developed with an appropriate schedule for corrective actions.
The licensee committed to establishing the program and will inform the Regional Office of their target date in approximately one month.
The inspector reviewed a letter from Westinghouse to Florida Power and Light Company (J.
B. Willis to C.
O.
Woody, dated May 23, 1978) which addressed the current lack of proper qualification of certain flow and pressure transmitters and in the Turkey Point installation.
The Pressurizer Pressure and Steam Generator Steam flow transmitters were specifically addressed in this letter as not being certified in accordance with the new sequential environmental testing criteria.
This item will remain open pending the licensee's implementation of a formal program for review and corrective action (78-18-02).
7.
Re ortable Events One reportable event was reviewed to ascertain that:
(1) reporting requirements of the Technical Specification 6.9.2 were met; (2) correc-tive action was taken as required by Appendix B to
CFR Part 50; (3)
the event was reviewed and evaluated; and (4) the facility was operated within the requirements of 10 CFR 50.59 and the Technical Specifications subsequent to the event.
Re ortable Event 250-78-08 During a routine plant shutdown on July 6, 1978, main steam isolation valve (MSIV) 3B failed to close fully in response to manual closing signals.
The solenoids for two parallel air supply valves were found to have open circuits which prevented air from being supplied to the closing side of the MSIV operator.
The inspector reviewed the correc-tive action taken by the licensee to ensure that all solenoids in the MSIV control air system had been inspected.
The licensee had checked winding resistance on all Unit 3 MSIVs air solenoids as of August 14, 1978, and had scheduled to perform the same check on Unit 4 solenoids.
The licensee has also included this check as part of his refueling outage preventive maintenance program.
8.
Plant Tour The inspector toured the Control Poom and Unit 4 containment to observe maintenance and operations in progress.
The inspector reviewed the NCCO's logs, equipment out of service logs, and radiation exposure controls and data for work in the 4B steam generator primary side.
The inspector identified several potential cleanliness control problems
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RII Report Nos. 50-250/78-18 and 50-251/78-18 I-6 to the licensee's representatives and discussed them with the plant manager at the exit. interview.
This area will be reviewed in depth during a subsequent inspection (78-18-03).
9.
Status of 0 en Items (Closed)
(77-21-04):
Interim Drawin Control Procedures The inspector reviewed AP 0103.10, Using Plant Drawings, and determined that it contained adequate controls for the use of interim plant drawings.
This procedure, if followed, should ensure that proper attention is given to the.quality and accuracy of drawings used for operations, troubleshooting and maintenance, particularly where perma-nent drawing revisions are still in preparation.
This 'item is closed.
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