ML18139A359
| ML18139A359 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/23/1980 |
| From: | Sylvia B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 509, NUDOCS 8006240356 | |
| Download: ML18139A359 (4) | |
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NRG COMMENT:
RESPONSE TO "NOTICE OF VIOLATION" REPORTED IN IE INSPECTION REPORT NOS. 50-280/80-19 Al.'TD 50-281/80-19 Attachment, Page 1 A.
As required by Technical Specification 6.4.A.4, detailed written proce-dures with appropriate check-off lists and instructions shall be provided for actions to be taken for specific and foreseen malfunctions of -systems or components. including alarms, primary system leaks and abnormal reac-tivity changes.
Contrary to the above, detailed written procedures with appropriate check-off lists and instructions have not been provided as of April 25, 1980, for actions to be taken when certain installed radiation monitoring components malfunction.
Consequently, when the Unit 2 radiation monitor (RM-RMS-262) on the manipulator crane intermittently failed on April 21 and 22, 1980 during Unit 2 refueling, appropriate prompt corrective action was not taken to correct the malfunction which was indicated by loss of the green fail/reset light and mR/hr meter indication.
Similarly, procedures do not exist for actions to be taken when flow or filter fault alarms occur on Ri"!-GW-101 and RM-159, 160, 259 and 260.
This is an infraction.
RESPONSE
This violation is not correct as stated.
AP series 5.16 through 5.19 specify specific actions to be taken in the event of a malfunction of RMS-GW-10_1, 102, 201, 202, R.J.'IS-*VG-103, 104, 203, 204, Ri."!S-RMS-159, 160, 162, 259, 260 and 262.
Operation Instruction. 01-1 is the procedure utilized to check lite avail-.
ability.
Tne training in this area will be emphasized during this year.
With the procedures in existance prior to the notification, no further action is necessary.
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Attachment, Page 2 4
NRC COMMENT:
SUBJECT:
RESPONSE TO VIOLATIONS LISTED IN IE INSPECTION REPORT NOS. 50-280/80-19 AND 50-281/80-19 B.
As required by Technical Specifications 6.4.A.2 and 6.4.D, the detailed written procedures with appropriate check-off lists for the calibration and testing of instruments, components, and systems involving nuclear safety shall be followed.
Contrary to the above, Unit 2 Containment Spray Chemical Addition Flow and LHSI Venturi Flow Verification Test, conducted on April 15, 1980, to verify Design Change 77-9 modifications, was not properly followed or completed.
On April 15, and 16, 1980, the following discrepancies were identified.
- 1.
The Initial Conditions of the test required that the Safety Injection and Containment Spray Systems were available for service per OP-7.1 and OP-7.2, respectively.
Valve alignment checklists OP-7.1 and 7. 2 were not completed prior to the_ test.
As a result of this, the LHSI pump 2-SI-P-:-lB was operated for *.
some 30 minutes with the pump suction.valve closed.
- 2.
Step 6.1.1 of the test procedure required the RWST water pH to be bet*,;e.en 4.0 and 4.5; the actual value was 5.4 and corrective action, Ceviations, or changes to the procedure were not made.
- 3.
Step 6.2.2 of the procedure is the first of several steps for CAT flow verification which were conducted but not signed and dated.
- 4.
Attachment IV to the procedure, which verified test instrumentation hook-:.:ps and attachmt=nts, was not completed; none of the several steps were signed off, al though the work was performed prior to conduct of the test.
- 5.
The 13 field changes to the test were unsigned and were not approved by-a i.:i.c:2nsed SRO prior to i:npl,?.mentation of the test.
This is an ii.ifraction.
RESPONSE
The infraction is correct as stated with the exception of Item 5.
SRO's are not required to review field changes prior to implementation.
- 1.
Corrective Steps Taken The Containment Spray Chemical addition flow and LHSI venturi flow.
verification test were satisfactorily conducted on April 30.
Flow and pressure parameters of 2-SI-P-lB have been verfied to be within
Attachment.. Page 3 design tolerances and the pump is also scheduled for disassembly and inspection for damage.
Emphasis will be placed on critical bearing tolerances.
Operators involved have been ins true ted on the impor-tance of procedural compliance.
- 2.
Corrective Action To Prevent Further Non-Compliance The above steps will avoid further non-compliance.
In addition>
increased emphasis will be applied in SRO and RO ret~aining sessions on adherence to procedures, and proper documentation.
- 3.
Date When Full Compliance Has Been Achieved Full compliance has been achieved *