IR 05000327/1987036
| ML20237K706 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/17/1987 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20237K495 | List: |
| References | |
| 50-327-87-36, 50-328-87-36, NUDOCS 8708270268 | |
| Download: ML20237K706 (2) | |
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Items Which Have Been Closed Violation 328/84-18-01; The licensee failed to provide within procedures a step or steps to ensure that safety subsystems, such as portions of-the AFW system, are' properly removed and restored to service with independent verification during the performance of abnormal valve alignment. The NRC i
inspector's review of corrective steps taken by the. licensee indicated satisfactory re m1ts were achieved.
Violation 328/84-18-02; The licensee failed t-establish adequate q
measures to assure that the design basis requirements, which were
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specified in the licensee's FSAR paragraph 10.4.7.2.3 for the AFW system, j
were correctly translated into specifications, drawings, procedures, and instructions.
The licensee's response of October 19, 1984, denied the violation occurred and provided the basis for the denial.
The NRC's
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response of July 10, 1986 indicated that existing regulatory requirements did not clearly warrant enforcement action. in this matter; therefore, deleted this violation from NRC records.
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Unresolved Item (URI) 328/84-18-03; Concerned the inoperability of main feed pump "A" control circuiting on June 30, 1984.
The NRC.previously noted in a July 10, 1986, response letter that a review of this matter had concluded that the licensee's interpretation of applicable TSs were correct and this unresolved item was administrative 1y closed.
Inspector Followup Item (IFI) 328/84-18-04; Concerned the need to upgrade operator training on the AFW system initiating circuitry and the SST logic.
The NRC inspector determined after review that'. the licensee's training letter appears to adequately address this subject.
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IFI 327,328/86-44-03; The licensee's special report issued by the Surveillance Review Committee dated July 10, 1986, involved approximately
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15 potentially. reportable TS issues and approximately 160 enhancement items. The enhancement items were considered an inspector follow-up item.
A review of the licensee's Commitment Action Tracking System (CATS)
indicates that the 160 enhancement items plus 28 additional items have been included in the CATS and being tracked to closure.
The inspector's review of those items that have been closed, indicated closures appear to be technically adequate.
Violation 327,328/85-46-04; The licensee inadequately established ' or maintained surveillance instructions and system operating instructions (i.e., inadequate acceptance criteria in SI-256; fuses with incorrect amperage ratings ' listed in SOI 30.6, and IMI-99 prescribed inadequate measuing and test equipment). The NRC's review of revised procedures and the licensee training on the subject has provided adequate corrective measures.
IFI 327,328/86-32-01; The TS requires testing of each diesel generator by simulated loss of of fsite power in conjunction with an ESF. The licensee states initiation of both signals will accomplish no more than either 8708270268 e70817 PDR ADOCK 05000327 G
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signal--independently. A TS change was requested and grantea to delete this test requirement (TS change 107).
IFI 327,328/86-32-02; The TS requirement 4.8.1.1.2.d.4 was incorporated in SI-26.2A, Revision 13, but was not in SI-26.1A and B.
The NRC inspector's
review of SI-26.1A and B has determined that TS requirement 4.8.1.1.2.d.4 and 4.8.1.1.2d.7 have now been incorporated.
IFI 327,328/86-32-03; SI-40, SI-128, and SI-129, (Pump and discharge pipe J
venting requirements for centrifugal charging pump residual hear removal pumps, and safety injection pumps) do not list acceptance criteria for venting.
The. inspector's review of these revised sis indicates that
acceptance criteria has now been included.
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Violation 327,328/86-05; Failure to follow the requirements of SI-45.1 and TS 3.7.4.
The NRC inspector discussed the issue.with licensee engineers, reviewed the revision to the sis and has determined that the pumps were
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not inoperable during the period in question and that the procedure now provides acceptable guidance for determining pump performance.
IFI 327,328/86-32-06; SI-137.3; Measurement of the controlled leakage to the reactor coolant pump seals, did not account for any changes in the i
'l position of valve FCV-62-89. The licensee's revised SI provided adequate corrective action.
l IFI 327,328/86-32-08; Review of the FSAR's minimum ECCS head capacity curve revealed that the head capacity curve submitted as Amendment 3 to
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the FSAR did not cover the full range of SI pump ECCS flow rates. The NRC
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inspector determined from his review of Amendment 4 to-the FSAR that the-FSAR and SI-260.3 pump head curves are the same.
IFI 327,328/86-32-10; The licensee's channel calibration method specified by IMI-99-CC-11.5B for the OPDT and OTDT reactor trip channels did not measure a dynamic response of the OPDT and 0 TDT.
Review of. the revised procedure indicates adequate test coverage for measuring response time.
IFI 327,328/86-32-11; IMI-99-RT-11.5 response time test method did not time the interval from when all monitored parameters of OTDT and low-low Tavg exceed their trip setpoint at the channel sensor.
Review of the revised procedure indicates adequate test coverage for measuring response time.
IFI 327,328/86-59-02; SI-40, Revision 35, Centrifugal Charging Pump Test, and SI-37, Revision 27, Containment Spray Pump Test, did not clearly cover paragraph IWP-4220 and IWP-4520 of ASME Section XI.
The licensee's clarification of these issues appears to be adequate and review of SI-40 and SI-37 indicate the intent of ASME Section XI requirements have been considered.
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IFI 327,328/86-49-03; The licensee identified, through the SI-1 Appendix F SI Review Program, that certt.in pump parameters may not j