ML18153B834
| ML18153B834 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/24/1989 |
| From: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18153B833 | List: |
| References | |
| 50-280-88-32, 50-281-88-32, GL-83-29, NUDOCS 8908010116 | |
| Download: ML18153B834 (3) | |
Text
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ENCLOSURE NOTICE OF DEVIATION Virginia Electric and Power Company Surry Docket Nos. 50-280 and 50-281 Litense Nos. DPR-32 and DPR-37 The following d,?viations \\'/ere identified during a Nuclear Regulatory Commission (NRC) inspection conducted on September 12-16, September 26-30, 1988 and November 14-18, 1988.
A.
Nuclear Regulatory Commission Generic Letter 83-29 dated July 8, 1983, required actions based on generic implication of the Salem ATWS event.
Paragraph 2.2. of the Enclosure requires that for vendor interface, licensees establish, implement, and maintain a continuing program to ensure that vendor information for safety-related com~onents is complete, current and controlled throughout the life of their plants, and appropriately referenced or incorporated in plant instructions and procedures.
Virginia Power responses to this Generic Letter (Serial No. 617, dated November 4, 1983; Serial No.85-063, dated February 8, 1985; Serial No.85-211, dated May 20, 1985; and Serial No.85-638, dated August 30, 1985) detailed the program which was implemented for Surry and North Anna Nuclear Plants.
Virginia Power response 85-063 states that revised administrative procedures which improve the availability and adequacy of vendor reference information are in use at each station.
These procedures implement the means of collecting and controlling vendor information for use by personnel involved in maintenance, replacement and repair activities.
It further states that controlling Administrative Procedure 93, Vendor Interface Contro 1 Documents, at Surry, and Administrative Procedure 6.18, Control of Vendor Manuals, Vendor Files and Interface, at North Anna, provide the primary activity for controlling vendor information for safety-related equipment.
These procedures provide a method of accumulating reference information and making the information available to the various work activities. These procedures are currently in use.
Contrary to the above, the requirements of this program are not being followed, in that, the following examples were identified where appropriate vendor information had not been included or referenced in site procedures:
- 1.
Calibration procedure CAL 466, used to calibrate Rosemount transmitters, does not provide the vendor manual required closing torque (90 in-lbs) for the detector vent and drain valves.
- 908010"i.1t.::,
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- 907:?4 or:50002:::0 FDC G!
Virginia Electric and Power Company Surry 2
Docket Nos. 50-280 and 50-281 License Nos. DPR~32 and DPR-37
- 2.
There are no site procedures to implement vendor manual (Limitorque) required mechanical preventive maintenance for valves 01-CW-MOV-lOOA, B,C,D; 01-CW-MOV-106A,B,C,D; 02-CW-MOV-200A,B,C,D; or 02-CW-MOV-206A,B,C,D.
- 3.
Site procedures do not include the following Emergency Service Water Diesel vendor recommendations:
- a.
The vendor manual requires a 20 minute wait after running the diesel for a check of the oil leve~.'
- b.
The vendor manual requires a periodic cleaning of the diesel cooling system using a radiator cleaning compound followed by a reverse flush with fresh water.
- c.
The vendor manual requires a periodic check of the *crankcase pressure.
- d.
The vendor manual requires a periodic cleaning of the air box check valves followed by blow out of the lines.
- e.
The vendor manual requires a periodic inspection and cleaning of the blower screen.
- f.
The vendor manual requires a periodic check/change of the lubrication in the reduction gear.
- g.
The vendor manual requires verifying oil pressure is increasing.
- h.
The vendor manual requires checking for oil leaks during pump runs.
- 4.
The Joseph Oats Corporation's Installation, Operation and Maintenance manual for Recirculation Coolers, Revision 2A, states recommendations for a desiccant maintenance program and rust requirements.
Visual observation of Recirculation Spray Heat Exchangers (RSHXs) prior to their being placed into containment identified ripped or torn covers on the RSHXs nozzles and rusting on bolts and flanges.
Site procedures did not address these vendor recorrmendations.
B.
The Updated Final Safety Analysis Report (UFSAR) Section 7.2.1, states that the reactor protection system and engineered safeguards are designed in accordance with I EEE-279, Standard Nuclear Power Pl ant Protec ti on System, dated August 1968.
Paragraph 4.13 of this Standard states that if the protective action of some parts of the system has been bypassed or deliberately rendered inoperable for any purpose, this fact shall be continuously indicated in the control room.
Virginia Electric and Power Company Surry 3
Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37 Cont1-ary to the above, portions of the Service Water Systems can be bypassed and this condition is not continuously indicated in the control room. Specifically, the Recirculation Spray Inlet and Outlet Valves SW-104A, B,C,D and SW-105A,B,C,D have a bypass function that allows for manually closing the valves during a Consequence Limiting Safeguards Hi-Hi condition.
Please provide to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555, with a copy to t_he Regional Administrator, Region II, and a copy to the NRC Resid~nt Inspecto~, in writing within 30 days of the date of this Notice, the reasons for the deviations, the corrective steps which have been taken and the results achieved, the corrective steps
\\'l'hich will be taken to avoid further deviations, and the date when your corrective action will be completed.
Where good cause is shown, consideration will be given to extending.the response time.
Dated at_.,.,.Atlanta, Georgia this 2-4 day of July 1989 FOR THE NUCLEAR REGULATORY COMMISSION g£;/t;ll~
Stewart D. Ebneter Regional Administrator