IR 05000400/1986049
| ML18004A325 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/17/1986 |
| From: | Jape F, Taylor P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18004A324 | List: |
| References | |
| 50-400-86-49, NUDOCS 8607290127 | |
| Download: ML18004A325 (9) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
ATLANTA,GEORGIA 30323 Report No.:
50-400/86-49 Licensee:
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Harris
Inspection Conducted:
June 9-13 and June 23-27, 1986 Inspector:
. Lg.
'
P. A. Tay or Approved by:
. Jap
,
ection Chief Engineering Branch Division of Reactor Safety License No.:
CPPR-158 7 r7 E4 ate Signe at Signed SUMMARY Scope:
This routine, unannounced inspection was conducted in the areas of previous enforcement matters, followup on inspector identifed items, review of hot functional test results and plant tour.
Results:
No violations or deviations were identified.,
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REPORT DETAILS Persons Contacted Licensee Employees
¹*R. A. Watson, Vice President, Harris Nuclear Project
¹*J. L. Willis, Plant General Manager
¹G. A. Meyer, Projects General Manager
¹*J. L. Harness, Assistant Plant General Manager
¹*C. S. Hinnant, Manager - Startup
¹*C. L; McKenzie, Acting Director, guality Assurance/guality Control (gA/gC)-
Operations
¹*H. W. Bowles, Director, On-Site Nuclear Safety
- L. J.
Woods, Startup Supervisor - Radwaste Systems
¹*J. L. Dority, Startup Supervisor - Radwaste Systems
¹*D. L. Tibbits, Director Regulatory Compliance B. H. Clark, Startup Engineer C. Petterson, Startup Engineer NRC Resident Inspector
¹*G. F. Maxwell 2.
- Attended exit interview on June 13, 1986.
¹Attended exit interview on June 27, 1986.
Exit Interview 3.
The inspection scope and findings were summarized on June 13 and June 27, 1986, with those persons indicated in paragraph above.
The inspector described the areas inspected and discussed in detail the inspection.
No dissenting comments were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
Licensee Action on Previous Enforcement Matters (92702, 70324)
(Closed) Violation 400/85-47-04, Failure to Provide Appropriate Acceptance Criteria and Identify Data Recorder in Test Procedure 1-2005-P-01, Hot-Functional Test.
(Closed)
Unresolved Item 400/86-23-02, Failure to Provide Appropriate Test Acceptance Criteria for Preoperational Test Procedures 1-1090-P-02, Reactor Protection and Engineered Safety Features Response Test and 1-1090-P-06, Reactor Protection System Logic Tes The licensee's response to the Notice of Violation and the planned corrective actions was submitted to NRC Region II Office in a letter dated March 24, 1986.
Subsequently, an inspection was conducted under report 50-400/86-23 on April 14-18, 1986.
The inspector identified additional examples (400/86-23-02)
where inadequate acceptance criteria was provided in preoperational test procedures.
As a result of these findings, the licensee initiated expanded corrective actions and described
'these and other changes to the Harris preoperational, test program in a letter dated April 25, 1986.
During this inspection, the inspector reviewed the implementation of the licensee's corrective actions identified in the aforementioned letters concerning the specific preoperational test procedures involved in the violation and the unresolved item and also to ascertain the effectiveness of the licensee's corrective actions as they apply to the ov'erall preopera-tional test program.
The inspector reviewed the completed test results of 1-2005-P-01, Hot Functional Test and noted that Revision
to this procedure added quantitative and qualitative criterion, clarified the recording and the review of baseline data and identify the data recorders.
Test procedures 1-1090-P-02, Reactor Protection and Engineered Safety Features 'nd 1-1090-P-06, Reactor Protection System Logic Test were similarly revised to expand and clarify their acceptance criteria.
The licensee also conducted comprehensive training sessions with all startup engineers, startup supervisors, joint tests group members, appropriate quality assurance and operations personnel.
The lesson plan used for the training stressed uniformity in test procedure preparation, correlation between test objective, test method and the acceptance criteria.
In addition memorandum and revisions to the Harris Startup Manual have been issued which incorporated guidelines for providing definitive acceptance criteria statements to clearly indicate the basis for acceptable test results.
To further accentuate the acceptance criteria guidelines, the licensee has incorporate into the Startup Manual several examples of improperly stated acceptance criteria.
The licensee has re-e'xamined test procedures '..in progress and those issued and approved and has made corrections to the test procedures as necessary to ensure definitive acceptance criteria has been provided.
The inspector reviewed several recently re-examination and approved test procedures and noted that the licensee's corrective actions have been effective in assuring that the acceptance criteria is adequate.
The licensee established an independent group of engineers to review those completed preoperational test procedures in document control files.
The results of this review indicated that five preoperational test had unsatisfactory results and these tests would be rewritten and performed again.
A permanent Test Review Group (TRG)
has been established and is identified in the Harris Startup Manual.
The establishing of the TRG provides an independent review of preoperational test procedures, revisions and completed test results prior to the final review and approval by the joint test group.
These items are close t ft I
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(Closed)
Deviation 400/86-04-01, FSAR Test Summary 14.2.12.1.34, Auxiliary Feedwater System Test, Test Objective a.4 and Acceptance Criteria d.3 Are Not Fully Incorporated into Preoperational Test 1-3065-P-02.
Test Objective a.4 requires that the steam turbine auxiliary feedwater pump to be started from cold conditions and measure steam 'pressure operating range during the test.
The acceptance criteria is that the reliability of the steam turbine a'uxiliary feedwater pump be demonstrated by performing five consecutive cold starts.
Test procedure change notice No.
7 was issued to incorporate the five consecutive cold starts, data table 10.5 was added to record steam pressure during the test and requirements to allow cooldown between starts of the turbine driven auxiliary feedwater pump to ensure cold start conditions.
(Closed)
Unresolved Item 400/85-31-03, Identify Preoperation Tests or Exemption from the Testing of Appendix A Section 5u, 5mm, Regulatory Guide 1.68, Revision 2.
The above sections describe operability tests for the MSIV's and Bypass valves during power ascension testing.
The licensee has taken exceptions to these tests as documented by the issuance of 'Amendment 25 to Section 14.2.7 of the FSAR.
(Closed)
Unresolved Item 400/86-02-02 Test Procedures 1-2060-P-Ol, Chemical and Volume Control System Hot Functional Test and 1-8010-P-02, Containment Building Hot Penetration Testing.
The data'ables do not identify the data recorder.
The licensee issued Revision 1 to 1-2060-P-01 and test change notice No.
4 to 1-810-P-02,to incorporate sign off requirements so the recorder of the data is identified.
(Closed)
Unresolved Item 400/86-23-01, Incorporate Testing of R.G.
1. 108, Section C 2.a.(1)
Diesel Generator Startup - Loss of Offsite Power into a Test Procedure.
The licensee issued Revision 2 to test procedures 1-5095-P-01 EDG-1A, Performance Test and 1-5095-P-02 EDG-2B, Performance Test to Incorporate the required testing.
Unresolved Items Unresolved items were not identified during the inspection.
Inspector Followup Items (92701)
(Closed)
400/86-23-03, Confirm Correct Diesel Generator Acceptance Criteria for Set Speed and its Recovery Requirements for Voltage and Frequency FSAR subsection 8.3. 1.2.4 requires that the EDG set speed will not exceed 107.5 percent of nominal speed (450 RPM) during a
recovery from the transient caused by disconnecting of the largest single load.
It also stated that the engine trip setpoint is 110 percent of nominal speed.
FSAR Chapter 14.2, test summary 14.2.12. 1. 16, specifies 111.25 percent of nominal speed and the engine trip setpoint if 115 percent of nominal spee I
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The acceptance criteria for the time that the EDG must recover to within ten percent of nominal voltage and two percent of nominal frequency is also in conflict.
FSAR Subsection 8.3.1.2.4 specifies this time as being within 40 percent of each load sequencer time interval, while FSAR test summary 14.2. 12. 1.16 gives this time as being within 60 percent of each load sequence time interval.
The licensee has changed subsection 8 3.1.2.4 to agree with the criteria specified in test summary 14.2. 12.1.16 by issuance of Amendment No. 27.
6.
Plant Tour The inspector toured the control room, reactor auxiliary building, containment, containment annulus, and outside plant areas to observe work activities in progress, housekeeping and tag controls on equipment.
hlithin the areas inspected, no violations or deviations were identified.