IR 05000400/1985031

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Insp Rept 50-400/85-31 on 850812-16.No Violations or Deviations Noted.Major Areas Inspected:Preoperational Test Procedure Review,Preoperational Test Procedure Verification & Plant Tour
ML18019A375
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 09/04/1985
From: Jape F, Taylor P
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML18019A374 List:
References
50-400-85-31, NUDOCS 8509170114
Download: ML18019A375 (8)


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UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTASTREET, N.IN.

ATLANTA,GEORGIA 30323 Report No.:

50-400/85-31 Licensee:

Carolina Power and Light Company P. 0.

Box 1551 Raleigh, NC 27602 Docket No.:

50-400 Facility Name:

Harris

Inspection Conducted:

August 12 - 16, 1985 Inspector:

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ape, ction ie Engineering Branch Division of Reactor Safety License No.:

CPPR-158 Date Soigne 7 v'Z~

ate Soigne SUMMARY Scope:

This routine, unannounced inspection involved 36 inspector-hours on site in the areas of preoperational test procedure review, preoperational test proce-dure verification and plant tour.

Results:

No violations or deviations were identified.

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REPORT DETAILS 1.

Persons Contacted Licensee Employees

  • R. A. Watson, Harris Project, Vice President
  • E. J.

Wagner, Manager Engineering

  • J. L. Wilis, Plant General Manager
  • N. J. Chiangi, Manager, Quality Assurance/Quality Control
  • G. L. Forehand, Director, Quality Assurance/Quality Control
  • C. S. Hinnant, Manager, Startup
  • J. M. Collins, Manager, Operations
  • S. Mabe, Startup Supervisor Balance of Plant
  • C. E. Rose, Jr.,

QA Supervisor-Operations

  • D. L. Tibbitts, Regulatory Compliance L. Wilsher, Startup Engineer R. Duncan, Startup Engineer NRC Resident Inspectors
  • G. F. Maxwell
  • R. L. Prevatte
  • S. P. Burris
  • Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on August 16, 1985, with those persons indicated in paragraph 1 above.

The inspector described the areas inspected and discussed in detail the inspection findings.

No dis-senting comments were received from the licensee.

a.

Inspector Followup Item 400/85-31-01, Amplify and Clarify Certain Steps of Test Procedure 1-2005-P-02, Pressurizer Relief Tank Test - paragraph 5a b.

Unresolved Item 400/85-31-02, Evaluate and Correct Discrepancies in Test Procedure 1-3020-P-01, Main Steam Isolation and Bypass Valves Test - paragraph 5b c.

Unresolved Item 400/85-31-03, Identify The Preoperational Test or The Exemption from Regulatory Guide (RG) 1.68, Revision 2 Tests Specified in Appendix A Section 5u, and 5mm - paragraph

The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio 'll A fk It

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Licensee Action on Previous Enforcement Natter s This subject was not addressed in the inspection.

4.

Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions.

Two new unresolved items identified during this inspection are discussed in paragraphs 5 and 6.

5.

Preoperational Test Procedure Review (703008, 703378, 70347B)

The inspector reviewed several licensee prepared and approved preoperational test procedures to verify that the technical content in the procedures is consistent with FSAR Chapter 14.2 test program and RG 1.68, Revision

requirement and commitments.

The test procedures were also reviewed to verify that the requirements of Harris Plant Startup Nanual Volume I have been incorporated into the test procedures regarding preparation, reviews, management approval, procedure format and the required prerequisites, precautions, and acceptance criteria.

The review of test procedure resulted in comment on two test procedures as follows:

a.

1-200-5-P-02, Pressurizer Relief Tank (PRT) Test (1)

The inspector noted that procedure steps 6. 1.25 and 6.1.27 requires recording PRT pressure when the nitrogen (N,) regulator (1NI-241) oper ates to provide N, gas to the PRT.

These procedure steps do not presently identify what are acceptable pressure ranges.

(2)

Step 6.3. 1 requires that the Reactor Coolant Drain Tank (RCDT)

system be placed in its normal shutdown condition or in the condition required for the next evaluation.

The inspector's concern is that specific instructions are not provided in the test procedure which identify normal shutdown conditions.

Operating procedures for the system are not referred to in the test proce-dure.

These items are identified as Inspector Followup Item 400/85-31-01, Amplify and Clarify Certain Steps of Test Procedure 1-2005-P-02.

b.

1-3020-P-Ol, Nain Steam Isolation and Bypass Valves Test (1)

Section 6.12, Main Steam Isolation Valve (NSIV) Loss of Air Test is not listed in the test objectives section of the procedure.

(2)

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(3)

Evaluate the completeness of the test procedure acceptance criteria 7.1 when it is compared with that specified in FSAR Chapter 14.2, test summary 14.2. 12. 1.50(d)(3)(b).

Steps in the procedure affected by the acceptance criteria are 6.9.3, 6.10.3 and 6.11.3.

(4)

Evaluate the completeness of the test procedure acceptance criteria 7.4 when it is compared with that specified in FSAR Chapter 14.2, test summary 14.2.12.1.50(d)(3)(d).

(5)

Section 6.12 MSIV Loss of Air Test, steps 6.12.2 and 6.12.3; clarify and provide more detail regarding the method to be used to have the MSIV go shut and provide a complete description of the acceptance criteria to be observed during the steps.

Other steps in procedure affect are 6.12.7, 6.12.8, 6.12.12, and 6.12.13.

These discrepancies are identified as Unresolved Item 400/85-31-02, Evaluate and Correct Discrepancies in Test Procedure 1-3020-P-01, Main Steam Isolation and Bypass Valves Test.

6.

Preoperational Test Procedure Verification (70311B)

The inspector reviewed portions of the preoperational test program as described in FSAR Chapter 14.2 to verify.that preoperational test procedures are being prepared for the testing identified and to determine if the testing described in RG 1.68, Revision 2 is being factored into the licen-see's preoperational test program.

RG 1.68, Revision 2,

Appendix A

Sections 5u and 5mm describe operability tests for the MSIV and Bypass valves during power ascension phase.

The inspector could not confirm that

'hese test are being planned as a result of reviewing FSAR Chapter 14.2.

This matter is identified as Unresolved Item 400/85-31-03, Identify Pre-operational Tests or Exemption from the Testing Specified in Appendix A

Section 5u, 5mm of RG 1.68, Revision "p '~ )"

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