ML17300A221
| ML17300A221 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/26/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17300A219 | List: |
| References | |
| GL-83-28, TAC-59165, TAC-59169, NUDOCS 8607030399 | |
| Download: ML17300A221 (8) | |
Text
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION L
G N RIC LE TER 83-28, ITEMS 3. 1. 1 AND 3. 1 2
N PALO VERDE NUCLE R
G NERATING ST TION, UNITS 1, 2 AND 3 DOCKET NOS.
STN 50-528, 50-529 AND 50-530 I.
INTRODUCTION On February 25, 1983, during startup of the Salem Unit 1 Nuclear Plant, both circuit breakers in the Reactor Trip System failed to open automatically upon receipt of a valid trip signal.
As a result of that
- event, the NRC's Office of Inspection and Enforcement issued IE Bulletin 83-01 which described the event and requested specified prompt corrective and preventive actions by licensees.
As the cause and ramifications of the event were more clearly developed, the NRC's Office of Nuclear Reactor Regulation issued on July 8, 1983, Generic Letter 83-28, "Required Actions Based on Generic Implications of Salem ATWS Events."
This letter addressed issues related to reactor trip system reliability and general management capability.
The letter was sent to all licensees of operating reactors, applicants for operating licenses and holders of construction permits.
One of the areas of reactor trip system reliability considered in Generic Letter 83-28 (GL 83-28), is that of post-maintenance testing of reactor trip system components.
This is identified in GL 83-28 as Items 3. 1. 1 and 3. 1.2.
This evaluation addresses the acceptability of the response to these items provided by Arizona Public Service
- Company, et al.
(APS) for the Palo Verde Nuclear Generating Station, Units 1, 2
and 3 (PVNGS).
II.
EVALUATION Items 3. 1.1 and 3. 1.2 of GL 83-28 state as follows:
"1.
Licensees and applicants shall submit the results of their review of test and maintenance procedures and Technical Specifications to-assure that post-maintenance operability testing of safety-related components in the reactor trip system is required to be conducted and that the testing demonstrates that the equipment is capable of performing its safety functions before being returned to service."
"2.
Licensees and applicants shall submit the results of their check of vendor and engineering recommendations to ensure that any appropriate test guidance is included in the test and maintenance procedures or Technical Specifications, where required."
By letter dated November 3, 1983, APS responded to a number of GL 83-28 items, including Items 3. 1. 1 and 3. 1.2.
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Regarding Item 3.1.1, this letter stated a review of all Reactor Trip System test and maintenance procedures which had been approved at that time, indicated that post-maintenance testing to assure operability was included.
The letter also stated all procedures still in draft form will have retest requirements
- included, as required.
Regarding Item 3. 1.2, (incorporation of vendor recommendations in test and maintenance procedures),
the APS letter of November 3, 1983, stated a review of all approved Test and Maintenance procedures indicated the latest vendor and engineering recommendations available to APS had been incorporated.
APS also stated any deviations from vendor and/or engineering recommendations have been reviewed by the vendor and found to be satisfactory.
III. CONCLUSION Based on confirmation by APS that all test and maintenance procedures for the Reactor Trip System include requirements for post-maintenance testing that assures equipment operability, we conclude APS has acceptably satisfied for PVNGS, the actions requested by Item 3. 1. 1 of Generic Letter 83-28.
Accordingly, this item is closed.
Based on confirmation by APS that the latest vendor and engineering recommendations have been incorporated in the test and maintenance procedures for the Reactor Trip System, as appropriate, and that any deviations from the recommendations have been reviewed by the vendor and found satisfactory, we conclude APS has acceptably satisfied for PVNGS, the actions requested by Item 3. 1.P. of Generic Letter 83-28.
Accordingly, this item is closed.
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION I
N LE N
GENERIC LETTER 83-28, ITEM 4. 1 ARIZ L
N AL.
PALO VERDE NUCLE R
G NER TING S TI N, UNITS 1, 2 AND 3 DOCK T N S.
STN 50-528, 50-529 AND 50-530 I.
INTRODUCTION On February 25, 1983, during startup of the Salem Unit 1 Nuclear Plant, both circuit breakers in the Reactor Trip System failed to open automatically upon receipt of a valid trip signal.
As a result of that
- event, the NRC's Office of Inspection and Enforcement issued IE Bulletin 83-01 which described the event and requested specified prompt corrective and preventive actions by licensees.
As the cause and ramifications of the event were more clearly developed, the NRC's Office of Nuclear Reactor Regulation issued on July 8, 1983, Generic Letter 83-28, "Required Actions Based on Generic Implications of Salem ATWS Events."
This letter addressed issues related to reactor trip system reliability and general management capability.
The letter was sent to all licensees of operating reactors, applicants for operating licenses and holders of construction permits.
One of the areas of reactor trip system reliability considered in Generic Letter 83-28 (GL 83-28), is that of vendor-recommended modifications.
This is identified in GL 83-28 as Item 4. 1.
This evaluation addresses the acceptability of the response to this item provided by Arizona Public Service Company, et al.
(APS) for the Palo Verde Nuclear Generating Station, Units 1, 2 and 3
(PVNGS).
II.
EVALUATION Item 4. 1. of GL 83-28 states "All vendor-recommended reactor trip breaker modifications shall be reviewed to verify that either:
(1) each modification has, in fact, been implemented; or.(2) a written evaluation of the technical reasons for not implementing a modification exists."
This item of GL 83-28 also states licensees should submit a statement confirming this action has been implemented.
By letter dated November 3, 1983, APS responded to a number of GL 83-28 items, including Item 4. 1.1.
Regarding Item 4. 1, this letter stated a review of the latest vendor recommendations and station work documents indicated that all vendor modifications to the reactor trip breakers available to PVNGS as of the date of the letter had been implemented.
In addition, APS stated that to ensure all future vendor-recommended changes to the reactor trip breakers (in maintenance, testing or design) are appropriately addressed, the station procedure governing control of Technical/Instruction Manuals at PVNGS was being revised to include a "front-end" review by the Maintenance Engineering Department of all such changes prior to their incorporation.
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The APS response further states the Nuclear Engineering Department will also review all vendor-recommended modifications.
In addition, APS Records management will file these recommendations with the controlled vendor data and will distribute the recommendations to the Maintenance Department to assure they have been reviewed as discussed above.
III. CONCLUSION Based on confirmation by APS that all vendor-recommended modifications to the Reactor Trip System available at the time of the response had been implemented, and the provisions made for assuring future recommendations are also reviewed and incorporated as appropriate, we conclude APS has acceptably satisfied for PVNGS, the actions requested by Item 4.1 of Generic Letter 83-28.
Accordingly, this item is closed.
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