IR 05000324/1979037
| ML19260D258 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/28/1979 |
| From: | Kellogg P, Ouzts J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19260D246 | List: |
| References | |
| 50-324-79-37, 50-325-79-39, NUDOCS 8002080210 | |
| Download: ML19260D258 (8) | |
Text
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o 101 MARIETTA ST., N.W., SulTE 310o e ATLANTA, GEORGIA 30303 ..... Report Nos. 50-324/79-37 and 50-325/79-39 Licensee: Carolina Power and Light Comp ny 411 Fayetteville Street Raleigh, North Carolina 27602 Facility: Brunswick Units 1 and 2 Docket Nos. 50-324 and 50-325 License Nos. DPR-62 and DPR-71 Inspection at South ort, North Carclina Inspector: M ~ M h) N/ze/rr - J. E. Ouzts [/ / Date Signed - Approved by: / pert [[ J p/eg/79 P. J. Kellog Section Chi 6f, 'RONS Pranch , Date Signed SUMMARY Inspection on September 29 through October 26, 1979 Areas Inspected This routine inspection by the resident inspector involved 52 manhours of inspec-tion time onsite of previously identified events, plant operations, radiation protection, physical protection, quality assurance, organization and adminsitration and unit I maintenance.
Unit 1 Areas Inspected This routine inspection by the resident inspector involved 27 manhours of inspection time onsite in the areas identified above.
. , Unit 1 Findings Of the six arer.a inspected, no apparent items of noncompliance or deviations were identified in five areas. One apparent item of noncompliance was identi-fied in one area-failure to recognize that a limiting condition for operaton was established and take compensatory measures required by technical specifications, when fire protection deluge valves were manually isolated, causing isolation of sections of the sprinkler and standpipe systems to diesel generator No. 3.
8002080
. . - ,,. . Unit 2 Areas Inspected This routine inspection by the resident inspector involved 25 manhours of inspection time onsite in the areas identified above.
Unit 2 Findings Of the five areas inspected, no apparent items of noncompliance or deviations were identified in four areas. One apparent item of noncompliance was identi-fled in one area-failure to recognize that a limiting condition for operation was established and take compensatory measures required by technical specifi-cations when fire protection deluge valves were manually isolated, causing isolation of sections of the sprinkler and standpipe systems to diesel generator No. 3.
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DETAILS 1.
Persons Contacted Licensee Employees
- A. C. To11ison, Plant Manager
- J. M. Brown, Operations and Maintencance Superintendent
- C. R. Gibson, Acting Administrative and Technical Superintendent
- R. Porterfield, Project Engineer
- R. M. Poulk, NRC Coordinator
- S. E. Thorndyke, Operating Supervisor L. F. Tripp, Acting E &RC Supervisor Other licensee employees contacted included 4 technicians, 10 operators, 6 mechanic, 4 security force members, and 3 office personnel.
- Attended exit interview
' 2.
Exit Interview The inspection scope and findings were summarized on October 5, 19 and 26, 1979 with those persons indicated in Paragraph I above. The licensee acknowledged the item of noncompliance as discussed in Paragraph 13 of these details.
3.
Licensee Action on Previous Inspection Findings Closed - Noncompliance - Item 324/325-77-18 Dosher Hospital plan was checked and found to be up-to-date during a subse-quent inspection (324/325-78-26). Dosher had been added to the accountobility log in the document control vault.
Closed - Noncompliance - Item 324/325-77-1 These requirements have changed since they were identified and this item is of no consequence now.
Closed - Noncompliance - Item 324/325-78-30-1 During this inspection period the procedure for cleaning and inspecting the spent fuel baskets prior to installation in the spent fuel pool was reviewed and found to be satisfactory. The initial cleaning will take place outside where any rust and foreign matter will be r,emoved and the baskets flushed 'with demineralized water.
The baskets will then be taken to the refueling ~ floor where they will again be fluched prior to being placed in the spent fuel pool.
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Unresolved Items Unresolved items were not identified during this inspection.
5.
Plant Operations The inspector conducted tours of plant areas, reviewed operating documents and followed up on findings as follows: Reviewed operator's logs to insure entries were correctly made.
a.
b.
Reviewed the status of limiting conditions for operation (LCO's) with the operators.
Inspected the control boards for the status of safety systems and c.
tagged out components.
d.
Reviewed with the operators the cause for energized annunciators and any corrective action being taken to clear the annunciators.
Witnessed several shift turnovers to insure that the oncoming shifts e.
were being properly briefed on the status of the plant.
f.
Toured the emergency diese] generator building to insure that the diesel generators were in a condition for automatic starting and that no abnormal condition existed as determined from the annunciator board.
g.
Toured vital plant areas to insure that proper housekeeping and clean-liness were being maintained and that combustible materials did not exist in uncuthorized areas.
h.
Toured the service water building to check the operation of the service water pumps and the status of indications on the annunciator board.
i.
Witnessed the cleaning of spent fuel baskets and reviewed the procedure for clezning with the licensee.
6.
Radiation Protection Frequent tours were made to insure that radiological control requirements were being followed. Radiation control arcas were inspected for the proper handling and storage of radioactive waste and contaminated materials, and for the posting of proper warning and caution signs. A facility setup in the plant yard to decontaminate metal-and wood scaffolding was inspected.
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7.
Physical Protection Frequent tours were made of the physical protection boundaries and access to protected areas as follows: Gates and doors to protected areas were closed and locked or attended.
a.
b.
Barrier fences enclosing protected areas were in a condition to prevent entry into the area.
Isolation zones were free of destructions and unauthorized objects.
c.
d.
Compensatory measures were implemented where equipment failures or impairment existed.
Witnessed security checks and badging at the entrance to controlled e.
areas to insure that they were being performed.
8.
Quality Assurance . The Quality Assurance Program was discussed with the licensee's management to verify that any changes to the program were in accordance with his established program and applicable codes standards and regulatory guides.
No changes were reported for the period of this report.
9.
Organization and Administration The inspector discussed organizational changer with members of management to verify that: The licensee's onsite organizational structure is as described in the a.
Technical Specifications.
b.
Qualification levels of persons filling new potitions are in conformance with applicable codes standards and Technical Specifications.
Organizational changes had been reported to the Nuclear Regulatory c.
Commission.
No organizational changes were reported for the period of this report.
10.
Maintenance Electrical maintenance was witnessed for Unit 2 plant batteries per main-tenance procedure M2-10-6G, to verify that: The correct procedure was being used.
a.
b.
The equipment had been tagged out.
c.
The procedure was being followed.
d.
Testind was performed prior to returning the equipment to operation.
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Unit 1 Reactor Trip Coverage Following the Unit No. I trip, due to resin intrusion on October 19 at 12:51 a.m., NRC inspector coverage of the event was increased with the aid of three inspectors dispatched to the site from the Region II office. A report on the coverage of this Unit No. I reactor trip is covered in report 50-325/79-38.
12.
Acceptance Criteria The inspector used one or more of the following sources of Acceptance Criteria for evaluating the above areas inspected: a.
10 CFR 50, Appendix B b.
10 CFR 20 c.
Technical Specifications d.
ANSI N45.2.3 (1971) e.
ANSI N18.7 (1972) f.
Regulatory Guides , g.
Site Security Plants h.
Quality Assurance Program 13.
Results of Inspection During the period of this inspection one apparent item of noncompliance was identified. No deviations were identified. A number of items of concern were observed and brought to the attention of the licensee for corrective action. The item of noncompliance and the items of concern along with the licensee's response are identified below: Noncompliance (50-324/79-37-1; 50-325/79-39-1) a.
Section 3.7.2.2 of the Technical Specifications r2 quires that where one or more of the diesel generator spray and/or sprinkler systems are inoperable a continuous fire watch with backup fire suppression equip-ment shall be established at the location within one hour. Contrary to this requirement, on October 16 the inspector found fire protection sprinkler and standpipe systems isolated to diesel generator bay No.
3.
The isolated systems were indicated by low pressure annunciator alarms for the systems. A followup investigation revealed that two deluge valves (DV-15 and DV-17) had been isolated for maintenance by the manual closing of three isolation valves. This action was taken without notifying operating personnel and having the system placed in a limiting condition for operation (LCO) and taking compensatory measures required by Technical Specifications. The LCO was established after the inspector found the condition, notified operating personnel
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-5- ' . and they had investigated the cause of the annunicator alarm. This is an infraction. Similar items were brought to your attention in our letters dated May 14, 1979 and September 19, 1979.
b.
In the area of radiological control the following unsatisfactory conditions were noted: The 350 mr activity at the base of the auxiliary surge tank - adjacent to Reactor Building No. 2 requires that an area extending up to the road on two sides be roped off. Any increase in activity in thf4 tank could present a problem in access and radiation control in the area. The licensee has agreed to investigate to detemine what can be done to reduce the activity in the tank.
Excessive leakage from a steam leak was found on the floor of - Reactor Building No. 2 at the Sk' corner 20 foot level. This leakage was coming from an electrical connection box mounted on the wall of a room containing a leaking steam valve. The steam , was leaking through a conduit penetration into the connection box where it was condensing and leaking onto the floor. The licensee
took corrective _ action to contain the steam leak in the valve room and direct the leakage to appropriate drains in the room.
. In the area of maintenance the following unsatisfactory conditions c.
we'e noted: r - The right fire door on entering the diesel generator building at the south end is in urgent need of repair and would be difficult to close and contain a fire. The licensee management agreed to have maintenance performed to correct this, problen. A power cable and its conduit were pulled out of their connection box near the ceiling in Unit No. I cable spreading room. The cable was resting hard against the conduit coupling. This condition was brought to the attention of the operating personnel and they had the condition promptly repaired.
A large ESS-Div. 2 electrical connection box was found open at - the 20 ft.
level, SW corner in Reactor Building 2.
The cover was replaced after being brought to the attention of the operating personnel.
In Reactor Building 1 and 2 numerous covers were missing from - conduit openings. These findin3s were brought to the attention of management who agreed to investigate and have these covers replaced.
- Followiug earlier tains several minor washouts were found under the barrier fence adjacent to the switch yard and warehouse "H".
These findings were brought to the attention of security personnel, who had repairs made and drain pipes installed under the fence where flooding occurred.
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In the area of operations the following unsatisfactory conditons were noted: Unit No. I south end scram discharge accumulator and drain piping - has broken hangers and damaged grout around the accumulator mounting. This damage apparently occurred during the Unit I reactor trip on October 19. The cause of this damage is currently being investigated by the licensee. No similar damage was observed at the North side accumulator for Unit 1.
- Several low pressure alarms for the fire protection system were observed to be energized at the panel in the Service Water Building.
This condition was brought to the attention of the operating supervisor to determine the cause for the energized annunciators.
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