IR 05000267/1977014
| ML20010B825 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 10/07/1977 |
| From: | Dickerson M, Madsen G, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20010B798 | List: |
| References | |
| FOIA-81-95 50-267-77-14, NUDOCS 8108180191 | |
| Download: ML20010B825 (7) | |
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U. S. fiUCLEAR REGULATORY C0:0!!SS10N OFFICE OF liiSPECTIOil AND Ef;FORCEf;EllT
REGION IV
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IE Inspection Report f:o. 50-26//77-14 j
1l Docket f;o.
50-267 License f;o. DPR-34
P. O. Box 840
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Licer ce:
Public Service Company of Colorado
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Denver, Colorado 80201
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facility flame:
Fort St. Vrain fluclear Generating Station Inspection At:
Fort St. Vrain Site,'Platteville, Colorado
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Inspection Conducted:
Septe.:ber 26-30, 1977 i
inspectors :
h. W.
-M%
./pfy/77
M. W. Ulckcrson, Reactor Inspector Date~
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1. f. Westerman, ' Reactor Inspector Date j
(9/26-28/77 only)
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Reviewed By:
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GT1tadsen, C~hEf7 Reactor Operations and.
Date
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fluclear Support Cranch
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Inspection Sunnary_
Inspection on Scotember 26-30,1977 (Report flo. 50_-267/77-14)
Areas insp'ectedIff5iitine, unannounceil inspection of the status of Stage 2 items; Q/i program annual review; review of plant operations; review of
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licensca event reports; follow up on inspector identified and unresolved
'>roblems and followup on items of noncorpliance. The inspection involved
.56 inspector-hours on-site by two (2) fiRC inspectors.
Res ul_ts : Of the six areas inspected, vio items of noncompliance or deviations were 6_ nd in five areas; one apparent item of noncompliance was inund during the review of plant operations (infraction - failur') to follow procedure, paragraph 3)
.i L.IVEDALE81-95 PDR
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c-2-DETAILS _
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Persons Contacted Public Service Company of Colorado _
l1. Ferris, Engineer Technical Services W. Franek, Senior Results Engineer W. Franklin, Reactor Operator R. Frost, Engineer, Technical Services
- E. Ilill, Supervisor Operations 4*W. Ilillyard, Supervisor Technical Services D. Holmes, Equipment Operator D. Hood, Shif t Supervisor J. Liebelt, Electrical Foreman L. licinroy, Superintendent QA Services B. 11cKinney, QA Engineer J. Salakeweitz, QA Engineer R. Shafer, Jr., Reactor Operator
+E. Swart, Superintendent Operations
C. Tracy, Superintender.t Operations QA
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++D. Warerbourg, Manager QA
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V. Wetzbarger, Shift Supervisor
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General Atomic C. Rodriguez, Engineer
- Denotes those present at 9/30/77 exit interview.
4* Denotes those present at 9/28/77 exit interview.
2.
Licensee Actic,n on Previous inspection Findinas (0 pen) Unresolved Item (7607-04): Seismic and Environmental Qualifications
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to be taken in the event of I
Emergency procedures delineating the actione a seismic event which require manual actuation of valves are presently in The licensee has also identified that seismic bangers preliminary draf t.
are not adequate in portions of piping systems less than 2-1/2 inches.
An evaluation of the hanger requirements by the licensee is presently in progress.
LCO Identification within Surveil-(Closed) Unresolved Item (7613-03):The incorporation of LCO 4.6.1.d into Surveillan lance Procedures.
Procedure SR 5.6.1.cd.A resolves this item.
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-3-(Closed) Unresolved item (7701-01): Procedural Deficiencies. Procedures 50P 22-01 and 50P 48 have bee.n revised to correct procedural deficiencies.
This matter is considered resolved.
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(0 pen) Noncompliance - Infraction A.1 (IR 50-267/77-03): Failure to
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Perform a Proper Reheat Steam Temperature SCRAM Set Point Calibration.
Forrial work sheets for each set point have been established; however, independent verification is incomplete.
(Closed)InspectorFollowUpItem(IR 50-267/77-03/207): Instrument Set Point. The inspector verified that monthly functional tests sign-offs have been incorporated into system calibration procedures.
(Closed) Inspector Follow Up Item (IR 50-267/77-03/218): Core Regional Daily Outlet Temperature Surveillance. The licensee's log sheets have been revised to provide documentation of the daily surveillance of the regional outlet temperatures.
(Closed) Inspector Follow Up Item (IR 50-267/77-04/220): Plant Upset of April 8,1977. The incident uas reported by the licensee (R0 50-267/
77-14).
(0 pen) Noncompliance - Infraction A (IR 50-267/77-09): Failure to
Issue a Radiation Ucrk Permit. The inspector verified by review of an interdepartmental memorandum that all Health Physics personnel have been
instructed with regard to the importance of logging surveys as required
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by in-plant procedures. A new RaCation Survey form to preclude
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recurrence is to be in use by Novenber 1,1977.
(Open) Deviation (IR 50-267/77-09): Failure to Verify and Document functional Acceptability Following Surveillance Testing. The licensee infortred the inspector that two additional weeks will be necessary to complete revision of all affected surveillance procedures. The licensee's initial response had been limited to Technical Specification instrument set point required surveillance tests.
(0 pen) Inspector Follow Up Item (IR 50-267/77-09/277): Stage 2.
IE:lV inspection of the revised Emergency Procedures for plant operation follow-ing a scismic event re 13 ins incomplete.
3.
Review of Plant Operations During the inspection, the conduct of plant operations was reviewed to determine that they conform to reqJis'ements of the facility license and the licensee's procedures. Included in the review were observations of control room activities, logs, records and tours of accessibic areas.
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-4-i During a review of the Form l's (Jun.per Log), it was noted that the
Operator's Log was not consistent with that maintained by the Shift Supervisors. Golden rod copies of form l's still r.aintained in the
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J Operator's log were 7-32, 8-1, 8-19, 8-20 and 9-4.
However, the j
shite and pir.k copies had been removed from the Supervisor's log indicating that the jumpers had been removed. The licensee was i
informed that this is contrary to Administrative Procedure #22,
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" Administrative Procedure for Device Removal Electrical Wiring Detemination, Placement of Electrical Jumpers or Pneumatic Bypasses,"
Rev. 9, dated June 28, 1977, Section 3.4.
Section 3.4 states in part
that, "The white copy of the authorization shall be returned to the i,
appropriate supervisor, who retains it as a permanent record for auditing purposes. The pink copy shall be presented to the 'lactor
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Operator / Assistant Reactor Operator by the Shift Supervisor :.ith instructions to clear the associated System Status Tag or other j
instructions as appropriate, whereupon the golden rod and pink copies
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are to be disposed of at this time."
i The licensee was informed that this was considered an infraction and although the Form l's specified above were removed prior to completion of the inspcction, corrective action to prevent a recurrence had not been completed.
The previously mentioned probicm, as well as several others, had been
discussed with the licensee during inspection 77-09 as an area for
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inspection follow up. Each of these were reviewed with the following results :
a.
Operation Order (System 21,11/4/76) outdated. The operations order has been rescinded, a
The following panels st ll have not been closed up.
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b.
(1) Diesel Air Compressor Control Panel
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(2) 10?.9 Panel - Plant Remote Shutdown Panel and associated Recorder Panel c.
Control Room Form 1 log was not current. This is now considered an infraction as discussed previously.
d.
A Form 1, which bypassed portions of the Dump System Logic Trouble Alams, has been removed.
e.
Plant Trouble Report 7-172. The report of a failure of 1A Emergency Generator Breaker to close has now been reported as
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LER 77-31.
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-5-The following logs and operational records were reviewed by the
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inspector:
I Station tog (7/13/77 - 9/27/77)
Surveillance logs 1-4(7/10/77-9/27/77)
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t Operations Order Cook form l's (Jumper Log)
Plant Trouble Rcpt,rts
j The inspector had no further questions in this area.
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4.
Review of Quality Assurance Program
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I The inspector reviewed the licensee's QA program for changes that had
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been made since the previous QA program inspection and verified that any changes made were in conformance with 10 CFR 50, Appendix B, and
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applicable codes, standards and regulatory guides. Any changes were reviewed with personnel having responsibilities for implementing the changes and any procedures which required changes uere also
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reviewed.
No items of nonconformance or deviations were identified.
I 5.
Review of__ Licensee Event Reports The inspector verified that licensee event reporting activities were in accordance with Technical Specifications, Section 7, ir:luding cicar identificatirn of details, corrective action, review and evaluation, safety espe:ts of operation, and acc.uracy of reporting.
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The following reports were reviewed by the inspector:
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R077-25,77-26,77-27(*),77-28,77-29(*),and77-30 j
No items of noncompliance or deviations were identified. (*) denotes
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open reports.
6.
Circulator Test T60A The inspector reviewed Circulator Test T60A, Rev.1, for consistency
kith the NRC letter of September 9,1977., The' inspector also reviewed the results of the test perfortred oa September 24, 1977. The inspector identified no significant exceptions to the September 9, 1977 NRC letter. A trip of IC Helium Circulator did occur during the
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portion of the test which siraulated an extended loss of normal bearing water in loop 2.
The trip resulted from the improper tripping of the purified helium compressor. There was, however, no apparent inter-action between loop 1 and 2.
The licensee is to provide a formal
report to the NRC within three weeks.
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Control of Fuses During the pre-testing checkcut of the llelium Circulators, in preparation for Circulator Test T60A, the licensee found that the g
control fuse for the ID Helium Circulator doubling circuit had been pulled. The pulled fuse was discovered following a trip of IC Helium Circulator and subsequent loop shutdown due to loop terrperature
differential when the speed of ID Circulator did not increase. The licensee, in follow up to this occurrence, stated that six additional l
fuses were found to not be installed during a subsequent inspection
,4 of the plant's fuse boxes. The licensee stated, in the exit sneeting, that this item would be evaluated for reportability.
This item is considered unresolved (7714-1).
8.
Unresolved items
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Unresolved itens are matters about which more information is required
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in order to ascertain whether they are acceptable items, iter:s of 5,
noncompliance, or deviations. ine following unresolved item was i
identified during the inspection:
'j 7714-1 Pulled fuses, paragraph 7 9.
Exit Interview Interviews with representatives of the licensee were conducted on September 28, 1977 and again on September 30, 1977 following corapletion of the inspection. At the interviews the inspectors discussed the findings indicated in the previous paragraphs. The licensee acknowledged these findings.
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