IR 05000267/1979001
| ML19270F908 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/22/1979 |
| From: | Dickerson M, Madsen G, Verduzco G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19270F903 | List: |
| References | |
| 50-267-79-01, 50-267-79-1, NUDOCS 7904030037 | |
| Download: ML19270F908 (7) | |
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U. S. fluCLEAR REGULATORY COMMISSION OFFICE OF It!SPECTION AND ENFORCEMENT
REGION IV
IE Inspection Report No. 50-267/79-01 Docket No. 50-267 Licenta No. DPR-34 Licensee:
Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 Facility flame:
Fort St. Vrain Nuclear Generating Station Inspection At:
Fort St. Vrain Site, Platteville, Colorado Inspection Conducted: January 8-12, 1979 Inspectors:
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M. W. Dickerson, Reactor Inspector
/ Date Accompanying Personnel: 64
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G. H. Verduzco, Rebctor Inspector (Training)
Date Approved by:
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'G. L. Madsen, Chief, Reactor Operations Date
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and Nuclear Support Branch Inspection Summary Inspection on January 8-12, 1979 (Report No. 50-267/79-01)
Areas Inspected:
Routine, unannounced inspection of review and audits; core safety liiiiit; review of safety limits, limiting safety system settings, and limiting conditions for operations; licensee event followup; IE Bulletins and Circulars followup; and review of special reports.
The inspection involved seventy (70) inspection-hours on site by two (2) NRC inspectors.
Results: No items of noncompliance or deviations were identified.
7904030037
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-2-DETAILS 1.
Persons Contacted Public Service Company of Colorado W. Franek, Results Supervisor M. Ferris, Engineer Technical Services R. Frost, Engineer Technical Services
- J. Gamm, Supervisor Technical Services R. Heller, Reactor Engineer Technical Services
- E. Hill, Supervisor Operations
- W. Hillyard, Administrative Services Manager
- T. Howard, Superintendent Operatioas, QA
- F. Mathie, Operations Manager
- D. Warembourg, Manager, Nuclear Production
- Attended exit interview.
2.
Core Safety Limit The inspector reviewed the licensee management system for assuring that the first physical barrier to the release of radioactivity is being maintained.
Implementation of this system is through the use of surveillance procedure 5.1.6-w ' Core Safety Limit," Revision 9.
Selected for review were those surveillance activities completed between October 28, 1977, and December 27, 1978. The total migration to date as determined by review of the curveillance records was 0.217.
Figure 3.1-1 of the technical specification is still under evaluation by the licensee and it is intented that the curve be extended to provide for those power to flow ratios of 1.22 and below and 2.5 and above.
Additionally the in-plant instrumentation for monitoring and recording power to flow ratios is under evaluation.
Submittal of the T/S change is raw scheduled for February 1,1979, and inclusion of provision for power to flow data is intended to be included in CN 922, Data iogger equipment changeout (New CDC 1700 System), and is currently scheduled for completion in September 1980.
This matter will remain an unresolved item (Reference R0 77-17).
3.
Review of Safety Limits (SL), Limiting Safety System Settings (LSSS),
and Limiting Conditions for Operation LCO).
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-3-The inspector verified conformance of reactor operations with Technical Specification requirements for SL's, LSSS's and LC0's by review of the following TS sections, related procedures, alarm settings and plant data:
a.
Safety Limits 3.1 Core Safety Limit (See Paragraph 2 above).
3.2 Reactor Vessel Pressure 1 845 psig, b.
Limiting Safety System Sei;tims_
3.3.1.1 (a) High fleutron Flux Scrams - 70% power.
U (b) High Reheat Steam Temperature Scram < 1075 F.
(c) Low Primary Collant Pressure 1 50 psi below rated, Programmed with load.
3.3.1.2 (a) High Primary Coolant Pressure < 53 psi below rated, Programmed with load.
Trip at 775 psia.
(c) PCRV Rupture Disc (High Set Safety Valve) M-11701, 832 psig i 1%.
High Set Safety Vave V-11702, 812 psig i 1%.
(d)
Helium Circulator Penetration Interpace Pressure, Valves 805 + 3%.
(e)
Steam Generator Penetration Interpace Pressure, Valves 475 1 3%.
c.
Limitim Conditions for Operations 4.1.3 Rod Sequence - approved by fiFSC, February 22, 1973.
4.2.7 PCRV Pressuization Limitation.
(c)
Interspace between primary and secondary penetration closures maintained at pressura greater than primary system pressure.
4.2.9 PCRV Closure leakage.
4.2.15 PCRV Cooling Water System Temperatures.
(a) Maximum temperature difference between Outlet Water temperature of PCRV Cooling Water System, and the PCRV external concret surface tempgrature, averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, shall not exceed 50 F.
(b) MaximumoutletwatertemperaturegfthePCRVCooling Water System shall not exceed 120 F.
(c) The maximum difference between the outlet water temperature and the inlet water temperature of the PCRV Cooling Water System shall not exceed 20.
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-4-4.4.-l (Table)
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Ilot Reheat Header Pressure-Low < 35 psig.
9.
Main Stean Pressure-Low n 1500 psig.
12.
High geactor iluilding Temperature (pipe cavity)
< 325 F.
4.4.-2 (Table)
Sa.
Steam Generator Penetration Overpressure, Loop 1
< 810 psig.
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Steam Generator Penetration Overpressure, Loop 2
< 810 psig.
4.4.6 Room Temperature, 480 Vol t Switchgear - 12( Cf.
The following related surveillance tests were also reviewed:
S.R.5.2.1.cl-A PCRV Switches and Alarm Calibration, May 11, 1978.
S.R.5.2.1.c2-A PCRV Relief Valve indicators, calibration and functional test, September 20, 1978.
S.R.5.2.15-A PCRV Interspace Pressu,e Calibration.
No items of noncomformance or deviations were identified.
4.
Review The object of this inspection effort was to verify that the organization, responsibilities, and authority of the Plant Operations Review Conmittee (PORC), and the Nuclear Facility Safety Conmittee (NFCS), which are delineated in the facility technical specification, are being properly executed.
This was accomplished by review of PORC and NFSC minutes for calendar year 1978.
During this review the following items were considered unresolved:
Technical specifications AC7.1.2 and AC 7.1.3 require that PORC review all proposed tests and experiments to deternine if they affect nuclear sa fe ty.
Should PORC's review indicate that nuclear safety is involved, a safety evaluation must be corrpleted under the provision of 10 CFR 50.59 to determined if the proposed tests or experiments involve an unreviewed safety question.
For those tests or experiments, that PORC determines do involve Nuclear Safety, but do not constitute an unreviewed safety question, NFSC must review the supporting safety evaluation, subsequent to the completion of the test, to verify that no unreviewed safety questions were involved (TS AC 7.1.3.g.l.(a)).
At the time of the inspection, the review of NFSC minutes did not definitely establish that the reviews were properly made.
Additional inspector review of licensee records will be required to confirm the extent of this
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-5-post-test, safety evaluation review by NFSC.
This matter is considered an unresolved item (item 7901-1) pending further review by the inspector.
Technical Specification AC 7.1.2.e.(7) requires that PORC review
" facility operations to detect potential nuclear safety hazards."
The inspector was unable to establish via review of PORC minutes that this responsibility is being fulfilled.
Licensee representatives were unable to specifically define the elements of this review and indicated that it was viewed as a somewhat nebulous requirement that is satisfied via other reviews and investigations conducted within the realm of PORC's responsibilities.. This matter is considered an unresolved item (item 7901-2) pending further review by the licensee of this requirement, as well as his demonstration that this require-ment is being tet.
The inspector had no further questions in this area.
5.
Audits Areas Inspected The inspector reviewed records relating to audits conducted during calendar year 1978, to verify that they were conducted as follows:
1.
In accordance with written procedures.
2.
By trained personnel not having direct responsibility in the area being audited.
3.
Audit results were documented and reviewed by management having responsibility in the area of audit and by corporate management.
4.
Followup action; including reaudit, was either taken, being initiated, or in progress, and 5.
Frequency of audits was in conformance with Technical Specifications.
Audit reports reviewed were:
NFSC Audits NFSC-A-78-1 Technical Specification Conformance.
Conducted September 1978.
NFSC-B-78-1 Performance, Training, Qualification of Plant staff.
Conducted November through December 197.
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NFSC-C-78-1 Corrective Actions.
Conducted February through March 1978.
NFSC-C-78-2 Corrective Actions.
Conducted September 1978.
QA Audits QAA-201 Startup testing.
Conducted July 31, 1978, through August 25, 1978.
QAA-1601-78-1 Emergency Plans / Security.
Conducted November 15, 1978, through November 28, 1978.
QAA-1601-78-3 Emergency Plans / Security.
Conducted August 23, 1978, through August 24, 1978.
QAA-2301 Corrective Actions.
Requirement for this audit satisfied by completion of NFSC-C-78-l&2.
QAA-701 Surveillance Testing.
Requirement for this audit satisfied by completion of NFSC-A-78-1.
QAA-1101 Instrument and Tool Calibration.
Conducted February 16, 1978, through February 22, 1978.
QAA-1801 Administrative Procodures.
Requirement for this audit satisfied by completion of NFSC-A-78-1.
QAA-5301-78-2 Nuclear Fuel.
Conducted June 19, 1978, through June 23, 1978.
QAA-5001-7E-3 Nuclear Fuel.
Conducted October 30, 1978, through November 1, 1978.
The licensee's principle mechanism for correcting audit identified deficiencies is the corrective action request (CAR).
The CAR identifies the deficiency to the cognizant department head, requests specific corrective action, and requires a written response be submitted generally within 60 days.
The inspector noted that responses to numerous CARS remain out' tanding beyond the 60 day guidelines.
However, this problem had been identified in audit NFSC-C-78-1, and corrective actions is in progress by the licensee's Quality Assurance personnel.
This matter will be considered an open item pending completion of the licensee's corrective action.
The inspector had no further questions in this area.
6.
Startup Reports The inspector reviewed the eighth Fort St. Vrain Startup Report. The report covering the period May 22, 1978, through August 22, 1978, was reviewed in the Region IV office.
No items of noncompliance or deviations were identifie..
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Review of Licensee Event Reports The inspector verified that licensee event reporting activities were in accordance with Technical Specifications, Section 7, including identification of details, corrective action, review and evaluation aspects of operation and accuracy of reporting.
The following reports were reviewed by the inspector:
R0 76-05 78-18 77-23 78-25 77-36 78-31 78-16 78-32 No items of noncompliance or deviations were identified.
8.
Bulletins / Circulars The inspector verified by record review, observations, and discussions with representatives of the licensee, the action taken in response to IE Bulletins / Circulars.
The following Bulletins / Circulars were reviewed by the inspector:
Circular Bulletin 78-15
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78-14 No items of noncompliance or deviations were identified.
9.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable itens, items of noncompliance, or deviations.
The following unresolved items were identified during the inspection:
7901-1 Review by NFSC of T/S 7.1.3.g.1.(a) Requirements - Paragraph 4.
7901-2 Review by PORC of T/S 7.1.2.e.(7) Requirements - Paragraph 4.
10.
Exit Interview
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An exit interview was conducted with representatives of f,he licensee on January 12, 1979, at the conclusion of the inspection. At the interview, the inspectors discussed the findings indicated in the previous paragraphs. The licensee acknowledged these findings.
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