IR 05000400/1998006

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Errata Pages 24 & 33 to Insp Rept 50-400/98-06 Issued on 980730.Page 24 Incorrectly Referred to URI USQ Determination Related to Cycle 6 Reload,As URI 50-400/98-400/98-01 & Failed to List Item on Pp 33.Correct Ref URI 50-400/06-04
ML18016A517
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 08/18/1998
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML18016A512 List:
References
50-400-98-06, 50-400-98-6, NUDOCS 9808250145
Download: ML18016A517 (7)


Text

24 E4 E4.1 a.

case, this is identified as an unresolved item, URI 50-400/9 06-01, USQ Determination Related to Cycle 6 Reload.

Conclusion For 19 safety evaluation forms reviewed by the inspect r, the licensee's determinations that a

USQD was not required were cons dered correct, although the bases for those determinations were ty cally weak.

Similarly, the bases for USQDs were weak in some c ses.

The inspector's findings in this regard were consistent with the indings descr ibed in HNAS98-015.

For 15 of 16 USQDs reviewed by the insp ctor, the licensee's determination that the corresponding ch e

did not involve a USQ were considered correct.

An unresolved item opened with respect to the Unreviewed Safety Question Determina on escribed in the safety evaluation for the Cycle 6 Reload.

Engineering Staff Knowledge and P

o mance Containment Sum Loose Parts Ins acti n Sc e

37661 The NRC identified to the c

see on January 27, 1998 that there could otentially be loose boltin material in the containment sumps.

The icensee initiated CR 98-0 95 to investigate and address this condition.

The inspector eviewed the root cause investigation.

Observation and Findi s

A short term operabi ity determination was performed and was documented in ESR 98-00042.

C Inspection Report 50-400/98-01, Section E1.2, Containment Sump ncerns, reviewed the short term operability determination.

e licensee found that the bolting material was a

bracket for for ign material exclusion (FME) covers that were put in place for the lant construction process.

They were not shown on any drawings and therefore were not permanent plant equipment.

They were not removed at the end of plant construction in 1986 as they should have been.

Th licensee found that during refueling outage 7 (RF07), workers and engi ers who were working on containment sump leaking problems observe a bracket on the sump suction pipe that was loose.

An engineer remov the portion of the bracket that was loose.

The remaining brac ts were haraner tested and found to still be soundly attached to the ipe with tack welds.

The licensee concluded in the ESR 98-00042 t t the sumps were oper'able with the parts left in place.

The NRC ncluded that the operability evaluation was adequate.

The licensee performed a root cause evaluation for CR 98-00295.

The cause of the brackets being left in the sump was that they were not recognized as a deviation from design during system and area turnovers during construction walkdowns in 1986.

The reason they were left in the

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E4 E4. 1

case, this is identified as an unresolved item, URI 50-400/98-06-04, USQ Determination Related to Cycle 6 Reload.

Conclusion For 19 safety evaluation forms reviewed by the inspector, the licensee's determinations that a

USQD was not required were considered correct, although the bases for those determinations were typically weak.

Similarly. the bases for USQDs were weak in some cases.

The inspector's findings in this regard were consistent with the findings described in HNAS98-015.

For 15 of 16 USQDs reviewed by the inspector, the licensee's determination that the corresponding changes did not involve a USQ were considered correct.

An unresolved item was opened with respect to the Unreviewed Safety Question Determination described in the safety evaluation for the Cycle 6 Reload.

Engineering Staff Knowledge and Performance Containm nt Sum Loose Part Ins ection Sco e

37551 The NRC identified to the licensee on January 27, 1998 that there could otentially be loose bolting material in the containment sumps.

The icensee initiated CR 98-00295 to investigate and address this condition.

The inspector reviewed the root cause investigation.

Observation and Findin s A short term operability determination was performed and was documented in ESR 98-00042.

NRC Inspection Report 50-400/98-01, Section E1.2, Containment Sump Concerns, reviewed the short term operability determination.

The licensee found that the bolting material was a

bracket for foreign material exclusion (FNE) covers that were put in place for the plant construction process.

They were not shown on any drawings and, therefore were not permanent plant equipment.

'They were not removed at 'the end of plant construction in 1986 as they should have been.

The licensee found that during refueling outage 7 (RF07), workers and engineers who were working on containment sump leaking problems observed a bracket on the sump suction pipe that was loose.

An engineer removed the portion of the bracket that was loose.

The remaining brackets were hammer tested and found to still be soundly attached to the pipe with tack welds.

The licensee concluded in the ESR 98-00042 that the sumps were operable with the parts left in place.

The NRC concluded that the operability evaluation was adequate.

The licensee performed a root cause evaluation for CR 98-00295.

The cause of the brackets being left in the sump was that they were not recognized as a deviation from design during system and area turnovers during construction walkdowns in 1986.

The reason they were left in the

IP 37001:

IP 37550:

IP 37551:

IP 40500:

IP 50001:

IP 61726:

IP 62700:

IP 62?07:

IP 71707:

IP 71750:

IP 92700:

IP 92902:

IP 92903:

INSPECTION PROCEDURES USED

CFR 50.59 Safety Evaluation Program Engineering Onsite Engineering Effectiveness of Licensee Controls in Iden ifying, Resolving, and Preventing Problems Steam Generator Replacement Inspections Surveillance Observations Maintenance Implementation Maintenance Observation Plant Operations Plant Support Activities Onsite Followup of Events Followup - Maintenance Followup - Engineering ITEMS OPENED, CLOS

,

AND DISCUSSED

~Geo ed 50-400/98-06-01 NCV Use Tech ical Specification Interpretations for TS Ch es (S ction 08.1).

50-400/98-06-02 50-400/98-06-03

~Clos d

50-400/98-06-01 50-400/97-07-02 50-400/97-07-0 50-400/97-

-04 50-40 /98-04-03 VIO gr orm ce of "During Shutdown" Surveillance at Power

~ti H8.5).

VI nt inment Sump FHE Sracket Design Deficiency (S tion E4.1).

NCY Use of Technical Specification Interpretations for TS Changes (Section 08. 1).

I Followup on Performance Monitoring of the Condensate Makeup System (Section H8. 1).

VIO Failure to Effectively Monitor the Performance or Condition of the Normal Service Water System (Section H8.2).

YIO Failure to Effectively Demonstrate Performance of the Steam Dump System and the C Charging Safety Injection Pump (Section H8.3).

URI Technical Specitication Literal Compliance (Section 88.5).

IP 37001:

IP.37550:

IP 37551:

IP 40500:

IP 50001:

IP 61726:

IP 62700:

IP 62707:

IP 71707:

.

IP 71750:

IP 92700:

IP 92902:

IP 92903:

~acne

INSPECTION PROCEDURES USED

CFR 50.59 Safety Evaluation Program Engineering Onsite En'gineering Effectiveness of Licensee Controls in Identifying, Resolving, and Preventing Problems Steam Generator Replacement Inspections Surveillance Observations Maintenance Implementation Maintenance Observation Plant Operations Plant Support Activities Onsite Followup of Events Followup - Maintenance Followup - Engineering ITEMS OPENED, CLOSED; AND DISCUSSED 50-400/98-06-.01 NCV Use of Technical Specification Interpretations for TS Changes (Section 08.1).

50-400/98-06-02 VIO Performance of "During Shutdown" Surveillance at Power (Section M8.5).

50-400/98-06-03 50-400/98-06-04 Clos 50-400/98-06-01 50-400/97-07-02 50-400/97-07-03 50-400/97-07-04 50-400/98-04-03 VIO Containment Sump FME Bracket Design Deficiency (Section E4.1).

URI USQ Determination Related to Cycle 6 Reload NCV Use ot Technical Specification Interpretations for TS Changes (Section 08. 1).

IFI Followup on Performance Monitoring of the Condensate Makeup System (Section M8. 1).

VIO Failure to Effectively. Monitor the Performance or Condition of the Normal Service Water System (Section M8.2).

VIO Failure to Effectively Demonstrate Performance of the Steam Dump System and the C Charging Safety Injection Pump (Section M8.3).

URI Technical Specification Literal Compliance (Section M8.5).