IR 05000309/1979011
| ML19256E092 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 09/06/1979 |
| From: | Guzman J, Keimig R, Lazarus W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256E091 | List: |
| References | |
| 50-309-79-11, NUDOCS 7910290035 | |
| Download: ML19256E092 (8) | |
Text
.
.
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-309/79-11 Docket No. 50-309 License No. DPR-36 Priority
--
Category C
Licensee:
Maine Yankee Atomic Power Company 20 Turnpike Road
'
Westborough, Massachusetts 01581 Facility Name:
Maine Yankee Atomic Power Station Inspection at:
Wiscasset, Maine Inspection condu += ':
July 31 - August 3, 1979 Inspectors:
/
dyr//4tw k6 f
W.
azarg Reactor Inspector date signed
.
la<ar w a-9/'b4
~J.
uz g, Reactor Inspegtor (Co-op)
da'te sign (d
.
date signed -
~
,
,
Approved by:
4/
@
R. R. Keiinig, Chief, Reactor Projects date signed Section No, 1, ROSNS Branch Inspection Summary:
Inspection on July 31 - August 3,1979 (Report No. 50-309/79-11)
Areas Inspected:
Routine, unannounced inspection of:
plant operations, including a tour of accessible areas and a review of selected logs and operating records; followup on selected Licensee Event Reports (LER's); and followup of licensee action on selected IE Bulletins.
The inspection involved 28 inspector-hours by one regional based inspector and one inspector Co-op.
Results:
No items of noncompliance were identified.
'U/
184
.
Region I Form 12 (Rev. April 77)
7910 90 Q3
.
.
.
DETAILS 1.
Persons Contacted
- P. Anderson, Staff Assistant to the Plant Manager
- R. Arsenault, Assistant Operations Department Head P. Cereste, I&C Technician G. Cochrane, Plant Health Physicist
- J. Hebert, Technical Assistant
- W. Paine, Operations Department Head R. Radasch, I&C Department Head
- S. Sadosky, QC and Audit Coordinator D. Sturniolo, Chemistry and Health Physics De9artment Head
- E. Wood, Plant Manager The inspector also interviewed several licensed operators, auxiliary operators, and other members of technical and administrative staffs.
- Denotes those present'at the exit interview.
2.
Followup on Previous Inspection Findinc,s (Closed) Unresolved Item (309/79-06-04):
The inspector reviewed Revision 11 to procedure 3.1.2, "ECCS Routine Testing," and verified that the MS-ISS, SCC-290, 297, 299 and 306 had been added to the locked valve check-list.
3.
In-Office Review of Licensee Event Reports (LER's)
The inspector reviewed LER's received in RI office to verify that details of the event were clearly reported including the accuracy of the description of cause and adequacy of corrective action.
The inspector also determined whether further information was required from the licensee, whether generic implications were indiceted, and whether the event warranted on site followup.
The following LER's were reviewed.
79-13, Defective RPS Low Flow Trip Bistable; and,
--
-*
79-14, CS-14 Operating Linkage Disconnected; Valve Not Fully Open.
Except as noted below for those LER's identified by (*), the inspector had no further que' ions in this area.
[
}8h
.
.
4.
On Site Licensee Event Followup For those LER's selected for on site followup, the inspector verified that reporting requirements of Technical Specifications and Regulatory Guide 1.16 had been met, that appropriate corrective action had been taken, that the event was reviewed by the licensee as required, and that continued operation of the facility was conducted within Technical Specification limits.
The review included discussions with licensee personnel, review of PORC meeting minutes, Plant Information Reports (in-house reports), and applicable logs.
The following LER's were reviewed on site.
79-14, CS-14 Operating Linkage Disconnected.
--
The inspector verified during a tour of the Spray Building that the linkage had been reconnected and the valve properly positioned to full open.
The inspector also reviewed Revision 11 to procedure 3.1.2 and verified that a checkoff had been added for each valve with remote operating linkage requiring the operator to verify the linkage intact after positioning the valves.
The inspector had no further questions in this area.
5.
IE Bulletins Licensee action concerning the following IE Bulletins was reviewed by the inspector to verify that:
The Bulletin was forwarded to appropriate onsite management;
--
A review for applicability was performed; and,
--
Information in the Licensee's respcnse concerning applicacility
--
and corrective action was accurate.
The reviews included FORC meeting minutes, evaluation memos, and discussions with licensee personnel.
IEB 79-03, Weld Defects in ASME SA-312 Type 304 Stainless Steel
--
Pipe.
In a review of the licensee's repsonse, dated March 28, 1979, regarding this bulletin, the inspector noted that the specific questions concerning whether the suspect piping had been used in any safety-related systems, had not been answered by the licensee.
In a phone corversation with the Manager of Operations on August I
[
lob
,
.
7, 1979, the inspector requested that the questions in the bulletin be readdressed and answered in another response as soon as possible.
The Manager of Operations agreed to supply the requested resporise.
Followup in this area will continue upon receipt of the necessary information from the licensee.
--
IEB 79-0A, Incorrect Weights for Velan Swing Check Valves.
The inspector reviewed the architect engineerir.g drawings for swing check valves installed in the High Pressure Safety Injection and Containment Spray System piping and verified that information concerning errors in the valve weights reported by the licensee in a letter to NRC:RI dated May 2, 1979 was correct.
The reanalysis referred to in the licensee's response has not been completed.
Completion of the followup in this area will be conducted following receipt of the licensee's final report.
--
IEB 79-09, Failures of GE Type AK-2 Circuit Breakers.
The inspector reviewed drawinas ll550-ESK-6 (Series) and inspected 480 volt switchgear to verify that information in the licensee's repsonse to NRC:RI of May 21, 1979 was accurate.
No inaccuracles were identified.
Information in the bulletin requires changes to the plant preventive maintenance procedures E6-Z-A and E3-X-B which the licensee has agreed to complete prior to performance of maintenance during the planned September, 1979 outage.
The inspector will verify that the required changes have been made during a subsequent inspection.
IEB 79-11, Faulty OC Trip Devices in Westinghouse D850 ana DB75
--
Circuit Breakers.
The inspector performed an inspection of the 480 volt switchgear to verify that this type of circuit breaker was not in use in safety-related systems as stated in the licensee's response to NRC:RI dated July 3, 1979.
None were identified.
The inspector had no further questions in this area.
6.
Shift Logs and Operating Records a.
The inspector reviewed the following plant procedures to determine whether any changes had been made to the licensee established administrative requirements in this area in preparation for review of various logs and records.
- " 7 187
-
.
0-06-1, " Procedure Preparation, Classification, and Format;"
--
0-06-2, " Procedure Review, Approval, and Distribution;"
--
--
0-09-1, " Reporting Requirements;"
0-09-2, " Reportable Occurrence Reports;"
--
0-10-3, " Maintenance of Operations Department Logs;"
--
--
SP-3.1.1, " Routine Instrumentation Surveillance;" and, 16.1, " Maine Yankee Operation Safeguard, Yellow Tag - Control
--
Log."
b.
Shift logs and operating records were reviewed to verify that:
Control Room log entries involving abnormal conditions
--
provide sufficient detail to communicate equipment status, lockout status, correction, and restoration;
--
Log Book reviews are being conducted by the staff;
--
Operating orders do not conflict with Technical Specifications requirements; Jumper (By;. ass) log does not contain bypassing discrepancies
--
with Technical Specification requirements; Logs and records were maintained in accordance with Technical
--
Specifications and the procedures in 6.a above; and, That the following parameters were within Technical Specifica-
--
tion limits:
(1) Si Tank levels and pressures (2) RW5T level (3) Radial power tilt (T )
q (4) Radial peaking factors (5) Reactor Coolant System (RCS) and Steam Generator activities i n 7 188
.
.
(6) RCS chloride, flouride, and oxygen (7) Steam generator chlorides c.
The review included aiscussions with licensee personnel and the following plant shift logs and operating records.
Control Room Operators' Log, July 1 - August 2,1979;
--
PORC Minutes 79-6 through 79-15;
--
Yellow Tag Control Log Request Forms 79-1 through 79-14;
--
Control Room Log Sheets I and II and Primary Side Log, July
--
1-31, 1979; Reactor Coolant System and Secondary Water Chemistry Reports,
--
July 1-31, 1979; and, All Current Operating Memos (OPMEMOS).
--
No items of noncompliance w re identified.
The following item was discussed with the licensee and remains unresolved.
In a review of PORC meeting minutes 79-12 of May 1, 1979, the inspector noted a PORC discussion concerning Technical Specifica-tion 3.19.b.1 which requires that the Safety Injection Tank isolation valve power operators be " racked out."
The licensee states, in this discussion, that these breakers in a 480 volt MCC are not designed to be racked out.
To meet the intent of the Technical Specification, the valve operator power leads have been disconnected and taped and the breakers locked open.
The plant is investigating a modification to install disconnect links and then to propose a change to Technical Specifications to eliminate the conflict.
This item is unresolved (309/79-11-01).
7.
Plant Tour The inspector conducted a tour of accessible areas of the plant including the Primary Auxiliary Building, Ventilat' ion Equipment Room, Containment Spray Pump area, Auxiliary Feed Pump area, Turbine Building, Switchgear Rooms, Containment, HP Control Point, and the Control Room.
Details are noted below.
!"'97 189
-
.
a.
Monitoring Instrumentation and Annunciators Control Board annunciators were checked for alarms, abnormal for plant conditions, on several occasions during the inspection.
None were identified.
The following monitoring instrumentation was checked to verify that required instrumentation was operable and that, where applicable, values indicated were in accordance with Technical Specifications.
SI Tank levels and pressures;
--
--
Core power distribution (symmetric offset, radial tilt, total radial peaking factor);
--
Off site (115 KV) power supply voltings;
--
Reactor Coolant System pressure; and, RWST level.
--
No items of non:ompliance were identified.
b.
Radiation Controls Radiation concrols established by the licensee, including post:ag of radiation areas, the condition of step off pads, and the disposal of protective clothing were observed for conformance with the Maine Yankee Radiation Protection Manual.
MYAPC Radiatian Work Permits issued for the inspection of the Spray Building and Reactor Containment were reviewed for proper documentation and compliance.
No items of noncompliance were identified.
c.
Plant Housekeeping Plant housekeeping conditions, including general cleanliness and storage of material to prevent fire hazards, were observed in all areas toured for conformance with the Maine Yankee Plant Safety Ma r.ual.
The inspector r.oted that general plant housekeeping conditions were good, d.
Fluid Leaks and Piping Vibrations Systems and equiptent ir. all areas toured were observed for the existence of fluid leaks and abnormal piping vibrations.
None were identified.
i n /
190
.
.
e.
Control Room Manning Control Room manning was reviewed.for conformance with the require-ments of 10 CFR 50.54(k) Technical Specifications, and IEB 79-068.
The inspector observed that appropriate licensed operators were on shift as specified by the posted shift schedule on several occasions during the inspection, and manning requirements were met at all times.
During the inspection tour of the Spray Building on August 1, 1979, it was determined that both seismic monitors had become inoperative since they were last tasted on April 19, 1979.
The inoperability was apparently the result of leakage of corrosive fumes from the self contained re-chargeable batteries which destroyed the connector of one battery
_
terminal in each unit.
An identical situation was discovered by the licensee during an inspection on April 19, 1979.
The batteries were replaced, the electrical connectors renewed and a protective grease applied to the connectors to prevent recurrence.
Both Strong Motion Accelographs were then tested satisfactorily in accordance with plant procedure 6-100-1, " Strong Motion Accelograph Operational Procedure and Record," prior to the completion of this inspection.
The inspector noted that although the FSAR refers to testing these accelographs at six month intervals, procedure 6-100-1 states that the testing will be done every three months.
A review of test records and discussion with licensee personnel indicate that this frequency has not been met.
Since the procedure went into effect in May, 1978, tests were performed on May 10, 1978, October 31, 1978, April 19, 1979, and August 2, 1979.
In light of the two identical failures discovered on April 19, 1979 and August 1, 1979, the licensee agreed to enforce the three month survillance test interval and to make a visual inspection of the battery connections prior to the next test to verity that continuing corrosion of the battery terminals was not a problem.
The licensee's actions in this regard will be reviewed during subsequent inspections.
8.
linresolved Items Unresolved items are items for which more information is needed to determine if the item is acceptable, a deviation or a noncompliance.
Detail 6 of this report contains an unresolved item.
9.
Exit Interview At the conclusion of the inspection, the inspector held a management meeting (see detail 1 for attendees) to discuss the scope and findings of the inspection as detailed in this report.
'7?/
lgl