IR 05000302/1977009
| ML19317G215 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/17/1977 |
| From: | Jape F, Robert Lewis, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317G171 | List: |
| References | |
| 50-302-77-09, 50-302-77-9, NUDOCS 8002280851 | |
| Download: ML19317G215 (8) | |
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IE Inspection Report No. 50-302/77-9
- Licensee: Florida Power Corporation 3201 34th Street, South P. O. Box 14042 St. Petersburg, Florida 33733
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Facility Name: Crystal River 3 Docket No.:
50-302
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License No.:
DPR-72 Category:
B2 Location: Crystal River, Florirla j
i Type of License: B&W, PWR, 2452, Mwt i
Type of Inspection: Routine, Unannounced
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Dates of Inspection: May 23-26, 1977 i
j Principal Inspector:
F. Jape, Reactor Inspector Accompanying Inspector:
J. D. Martin, Reactor Inspector l
Other Accompanying Perso el: None Reviewed by:
[ /7 R.'C'. Lewis, Chief
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' Data Reactor Operations and Nuclear Support Branch Inspection Summary l
Inspection on May 23-26,1977 (Report No. 50-302/77-9)
i Areas Inspected: Routine, unannaunced inspection of power escalation
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test results, followup of unresolved items, reportable events, and previous items of noncompliance. The inspection involved 28 inspector-hours on site by two NRC inspectors.
Results: Of the four areas inspected, no items of noncompliance or deviation were found in three areas; one apparent item of noncompliance was found in one area (infraction - failure to comply with a limiting
condition for operation was identified - Details I, paragraph 5).
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RII Rpt. No. 50-302/77-9 I-1
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DETAILS I Prepared by:
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F. Jape, Reactor Inspector Date Rasetor Projects Section No. 2
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Reactor Operations and Nuclear
Support Branch
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Dates of Inspection:
y 23-26, 1977 d 7/77 Reviewed by:
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Reactor Projects Sectio [n No. 2 R. C. Lewis, Chief Dace
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j Reactor Operations and Nuclear
Support Branch i
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Persons Contacted Florida Power Corporation (FPC)
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G. P. Beatty, Jr., Nuclear Plant Manager D. W. Pedrick, IV, Compliance Engineer P. L. Breaux, Nuclear Shift Supervisor W. W. Surrency, Chief Nuclear Operator R. L. Skipper, Nuclear Operator W. R. Nichols, Operations Supervisor 2.
Licensee Action on Previous Inspection Findings a.
Noncompliance (Closed) Noncompliance (50-302/,77-3): Failure to report a reportable occurrence. Discussion with licensee management reveal an understanding of the Technical Specification report-ing requirements. Corrective measures as described in the i
licensee's March 22, 1977, letter were verified.
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(Closed) Noncompliance (50-302/77-4, Item I.3): Failure to certify or approve Procedure CP-108. The inspector verified that CP-108 has been reviewed and approved by a FPC Level III Examiner. In additior., as described in FPC's letter, dated i
April 27, 1977, the procedure has been revised to specifically require all NDE procedures to be approved by the FPC Level III tranher prior to use.
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RII Rpt. No. 50-302/77-9
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I-2 b.
Unresolved Items (open) Unresolved Item 77-5/1 (50-302/77-5)
RCS Leakage
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Surveillance.
Followup on Surveillance Procedure 317 data sheets revealed that calculational errors are still being made.
RCS leakage determinations using the input data indicate the leakage to be within the-technical specification
limit.
Licenses management stated that a recent revision to the data sheets should correct the calculational errors.
3.
_Uyresolved Items Unresolved items are matters about which more information is I
items of noncompliance, or deviations. required in order to ascertai during the inspection is discussed in Paragraph 6.An unresolved item disclosed
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4.
Exit Manaaement Interview l
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An exic management interview was held on May licensee representatives.
26, 1977, with The scope and findings of the inspection were summarized.
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Licensee management acknowledged the inspectors
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findings.
The item of noncompliance dealing with the improper steam supply for Emergency Feedwater Pump No. 2 was discussed and j
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licensee management stated that they understood the issue and would initiate corrective action.
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Unresolved item concerning lack of surveillance testing of Emergency Feedwater Pump No.1 procedure 416 was discussed.
Licensee management stated that the matter would be reviewed for resolution.
Licensee representatives who participated in the exit management
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meeting are listed below:
G. P. Beatty, Jr. - Nuclear Plant Manager K. O. Yogel - Computer and Controls Engineer C. M. Williams - Compliance Plan: Engineer (acting for the Technica W. R. Nichols - Operations Supervisor R. C. Bonner - Project Manager
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I 5.
Emermancy Feedwater Pump No. 2 The licensee reported in LER-24 and 37, that when the steam driven emergency feedwater pump, (EFP-2) was started, using main ' steam as O
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RII Ept. No. 50-302/77-9 I-3
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the power source, it would trip ~off due to overspeed. To correct the problem, the steam supply was changed to the auxiliary header
from the main steam header. This action is stated in LER-24 and 37. It is also stated in the control center log as follows:
March 8,1977 - Valve lineup to provide auxiliary steam from Units 1 and 2 by closing ASV-16, MSV-55 and MSV-56, and opening i
ASV-18.
April 16,1977 - EIP-2 is on auxiliary steam and is declared operable.
The steam lineup was returned to normal, that is aligned up to the
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main steam header, on April 27, 1977.
During the periods that EFP-2 was aligned to the auxiliary header, the limiting condition for operation, as stated in Technical Specification (TS) 3.7.1.2b., was not complied with. The reference TS requires EFP-2 to be powered from an operable steam supply sywtem. The auxiliary steam header is not considered to be an
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operable steam supply system due to design considerations.
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During the inspection period, the plant was in Mode 4.
Discussions
with licensee management regarding this matter resulted in an
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understanding that plant startup would not be made with EFP-2 aligned to the auri11mry steam header and that the main steam header would be the operable steam supply system for complying with TS 3.7.1.2b.
This understanding was verified on May 27, 1977, by telephone with the Director of Power Production. Licensee manage-ment also stated that they would submit a supplement to LER-24 and 37 with adequate corrective action statements.
Operation of the plant in Modes'1, 2 or 3 with EFP-2 aligned to the auxiliary steam header is censidered to be an infraction with TS 3.7.1.2.b.
6.
Review of Surveillance Procedure 416. " Emergency Feedwater Automatic Actuation" Technical Specification 4.7.1.2.b. presents the surveillance requirements for the emergency feedwater system (EFW). The surveillance is on an eighteen month cycle and requires verifi-cation that both EFW pumps start automatically on an emergency
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feedwater actuation test signal.
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t, RII Rpt. No. 50-302/77-9 I-4
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The licenses has prepared SP 416, "EFW automatic actuation," to comply with this TS requirement. The inspector reviewed this procedure and found that it does not include any testing for emergency feedwater pump No.1, (EFP-1). EPP-1 is motor driven and has no automatic actuation signal. This pump is manually started
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by the nuclear operator from the control center.
The apparent variance between the TS surveillance requirement, the surveillance procedure and equipment design is considered unresolved.
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RII Rpt. No. 50-302/77-9 II-1 DETAILS II Prepared by:
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M d 7/77
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J. D// Martin,\\ Reactor Inspector
/Da(e Nuc16ar Support Section Reactor Operations and Nuclear Support Branch i
Dates of Inspectio - May 23-26, 1977
[ 7!77 Reviewed by:
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ff. D. hart n, Ch$e~f
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huclearSu[pportSection
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Reactor Operations and Nuclear Support Branch 1.
Persons Contacted j
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Florida Power Corporation (FPC)
G. P. Beatty, Jr., Nuclear Plant Superintendent P. F. McKee, Assistant Nuclear Plant Superintendent
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W. D. Pedrich, IV, Compliance Engineer J. C. Hobbs, Jr., Manager, Generation Testing j
i Babcock and Wilcox Company (B&W)
i J. Putman, Startup Test Engineer 2.
Licensee Action on Prev 1ous Inspection Findings Unresolved Items a.
(0 pen) 77-3/1, (77-2/1) Offsite Organization Followup inspection on previously identified unresolved item 77-3/1, (77-2/1) revealed that an amendment to the Technical Specifications (TS) to change Figure 6.2-1 has now been submitted to NRR. Until such time that the amendment is approved this item will rammin open with followup inspection at a future date to verify the status.
b.
(Closed) 77-4/1 Loss of Offsite Power Test Followup inspection verified that an additional test was successfully conducted on April 23, 1977 in accordance with the scope of a retest as outlined in an attachment to an An il 12, 1977 letter, (W. P. Stewart, FPC to Norman C. Moseley, USNRC).
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RII Rpt. No. 50-302/77-9 II-2
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The review of the test results for the retest conducted also revealed that the licensee had performed an adequate evaluation of the test results and that the results were within established acceptance criteria. The review also verified the adequacy of the methods used for identifying and correcting test deficiencies.
c.
(Closed) 77-5/2 Shutdown From Outside Control Room Test The co:. aments and questions related to TP-800-27, (Rav. O and identified as UN 77-5/2 were re-evaluated by reviewing la.er revisions to TP-800-27, (Rev.1) and EP-113, (Rev. 4) " Plant
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Shutdown From Outside Control Center." The inconsistencies which had previously existed were corrected in the later revisions to the procedures. For example step,9.2.2 of TP 800-27, (Rev.1) states; " Trip the reactor remotely by opening 480V CRD breaker A and B and perform shutdown per i
EP-113."
3.
Unresolved Items None 4.
Manaaement Exit Interview A management interview was held on May 26, 1977. Refer to Details-I, pcragraph 4, for matters discussed at the exit meeting.
5.
Power Ascension Testing Data Review Test results of selected power ascension tests were reviewed to assure that the licensee had performed an adequate evaluation of the test results, and that the results were 91 thin established acceptance criteria. The review also verified that the test commitments contained in Table 1>4, " Power Test Suunnary," of the FSAR and requirements of Regulatory Guide 1.68 - November, 1973 were adhered to.
In addition, the review also verified the ade-quacy of the methods used for identifying and correcting test deficiencies, and assure that adminiatrative control practices required by Section 13.2, "Mainistrative Controls," of the FSAR and Test Program Guide were being adhered to.
The following
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documents were reviewed:
TP-71-80')-26 (Rev. 2), Loss of Offsite Power Test TP-71-800-27 (Rav.1), Shutdown From Outside Control Room Test
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RII Rpt. No. 50-302/77-9 II-3
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TP-71-800-13 (Rav. 0), Loss of Electrical Load _
TP-71-300-0 (Rav. 2), Power Escalation EP-113 (Rev. 4), Plant Shutdown From Outside Control Center Plant Review Consmittee Minutes
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Number Date of Meeting 77-21 May 5, 1977 77-20 April 25, 28, 1977 i
77-19
' April 19, 20, 1977 77-18 April 16, 1977
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77-17 April 14, 15, 1977 77-16 April 5, 7, 1977 77-15 March 25, 29, 31, 1977 77-14 March 22, 24, 1977 77-13 March 15, 18, 1977 77-12 March 11, 1977 77-11 March 10, 1977 77-10 February 29, 1977, March 3, 1977 Within the areas inspected no discrepancias were left identified.
A final evaluation of the power ascension program could not be made
since final documentation of the test results is yet to be completed.
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The final results of the power ascension testing data will be reviewad on a subsequent inspection.
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