ML20247E493

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Forwards Sims Insp Rept on 890705-07 Re Verification Requirements of Sims
ML20247E493
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 07/21/1989
From: Rooney V
Office of Nuclear Reactor Regulation
To: Shemanski P
Office of Nuclear Reactor Regulation
References
TAC-08408, TAC-08409, TAC-8408, TAC-8409, NUDOCS 8907260206
Download: ML20247E493 (4)


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July 21, 1989 Docket No. 50-295 and 50-304 MEMORANDUM FOR:

Paul C. Shemanski, Acting Director Project Directorate III-2 i

Division of Reactor Projects - III, IV, V, and Special Projects FROM:

Vernon L. Rooney, Project Manager Project Directorate I-3 Division of Reactor Projects I/II

SUBJECT:

ZION NUCLEAR POWER STATION SIMS INSPECTION REPORT (TAC NOS. 08408 AND 08409)

On July 5 - 7, I performed an inspection of the following SIMS item at the Zion site:

The purpose of the inspection was to satisfy the verification requirements of SIMS.

The enclosure presents my observations and has been forwarded to the Resident Inspector for inclusion in the next inspection report.

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Vernon L. Rooney., roject Manager Project Directora e I-3 Division of Reactor Projects I/II l

Enclosure:

As stated Dful l

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ZION NUCLEAR POWER STATION l

I SIMS INSPECTION REPORT

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Tnsoection for Verification of Licensee Chances Made to Comolv with pWR doderator Dilution Requirements -- Multi-Plant Action Item B-03 The inspector reviewed licenace records related to disposition of the PWR Moderator Dilution Requirements, Multi-Plant Action (MPA) Item B-03.

Multi-Plant Item B-03 originated when an unreviewed method of moderator dilution was revealed by an incident at an operating PWR facility.

With the reactor in the cold shutdown condition, a portion of the contents of the NaOH tank gravity drained into the Decay Heat Bemoval System during surveillance cycling of a tank isolation valve and was subsequently injected into the Reactor Coolant system.

Licensee evaluation of this incident revealed that unterminated injection of NaOH solution could result in reactor criticality and that this manner of moderator dilution was not bounded by the FSAR analysis.

DDR Information Memorandum No.

7, PWR Moderator Dilution, was issued on October 4, 1977.

Operating PWR licensees were informed of the incident and requested to evaluate potential moderator dilution accidents for their facilities.

Inspection efforts at Zion Station produced no record of the licensee being requested to report, or of the licensee reporting the results of the evaluation to the staff.

Licensee correspondence and vendor analysis for this safety issue were plant specific for Zion Station.

The only situation identified by the vendor as requiring remedy was

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' inadvertent boron. dilution while on RHR with a. shutdown margin less than 5%.

The' vendor concluded that the threat of an unacceptable

' inadvertent dilution was removed by closing valves in the reactor makeup

~uater: supply and valves between the boric acid blender and the volume control tank.

The licensee accepted the vendors analysis of the concern,~and has-incorporate'd the recommendations into procedure PT-0, App.-E-3, as requirements when the plant is on RHR with a' shutdown margin less than 5%.

At the inspectors request the licensee agreed to add a footnote to the procedure relating these requirements to NRC safety issue MPA B-03 so that the origin is preserved, and the requirements aren't inadvertently deleted.

.The actions taken by the licensee appear satisfactory.

The inspector concluded that completion of MPA B-03 is verified for the Zion Station.

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July 21, 1989 c, c ;

e Docket No. 50-295 and 50-304 I

MEMORANDUM FOR:

' Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects - III, 4

IV, V, and Special Projects ~

FROM:

Vernon L. Rooney, Project Manager Project Directorate I-3 Division of Reactor Projects 1/11

SUBJECT:

ZION NUCLEAR POWER STATION SIMS INSPECTION REPORT (TACNOS.08408AND08409) i F

On July 5 - 7, I performed an inspection of the fo'llowing SIMS item at the Zion.ite:

The purpose of the inspection was to satisfy the verification requirements of SIMS.

The enclosure presents my observations and has been fornrded to the Resident Inspector for inclusion in the next inspection report.

Vernon L. Rooney, Project Manager Project Directorate 1-3 Division of Reactor Project, I/II i

l Enclosure As stated l

DISTRIBUTION Docket file NRC & Local PDRS, PDIII-2 r/f RWessman BBoger VRooney WShafer, RIII JHines, RIII CPatel MVirgilio

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