IR 05000416/1981014

From kanterella
Jump to navigation Jump to search
IE Insp Rept 50-416/81-14 on 810506-13.No Noncompliance Noted.Major Areas Inspected:Preoperational Testing & Sys run-in Observations
ML20005B673
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 06/10/1981
From: Cantrell F, Garner L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20005B671 List:
References
50-416-81-14, NUDOCS 8107080540
Download: ML20005B673 (5)


Text

r

' ;

'.

[

UNITED STATES o

!

NUCLEAR REGULATORY COMMISSION

~

,

g REGION 11

m

"o

'#

101 MARIETTA ST., N.W, SUITE 3100 ATLANTA, GEOR'. iia 30303

.:

.....

Report No. 50-416/81-14 Licensee: Mississippi Poser ano Light Company Jackson, MS Facility Name: Grand Gulf 1 Docket No. 50-416 License No. CPPR-118 Inspection at Grand Gulf site near Port Gibson, Mississippi Inspector: [ d.

. A /_

4 -/ o-5 /

L. W. Gnnef

/'

Date Signed Approved by: Y k

/

7/

F.' S. Cantrell,3,egion Chief, Division of D' ate' Signed Resident and RVactor Project Inspection SUMMARY Inspection on May 6-13, 1981 Areas Inspected This routine, announced inspection involved 61 inspector-hours on site in the areas of preoperational testing, system run-in observations, and discussions with licensee management.

Findings Of the two areas inspected, no violations or deviations were identified.

l

'd107080540 810611 PDR ADOCK 05000416

<

O PDR

.

,,

.

,

,

DETAILS

'

1.

Persons Contacted Licensee Employees

  • C. Abbott, Plant Quality Assurance L. Eisenberger, Startup Enginee

"J. Elm, MPL Maintenance

  • M. Farschon, GE Operations Manager
  • C. Hutchinson, Startup Manager M. Madison, Startup Engineer
  • J. Roberts, Startup Suparvisor
  • B. Stewart, Construction
  • S. Tanner, QA Construction Coordinator
  • B. Wilson, MPL Maintenance Other licensee employees contacted included maintenance technicians, I&C technicians and operators.

" Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on May 13, 1981, with those persons indicated in Paragraph 1.ibove.

3.

Licensee Action on Previous Inspection Findings Not inspected.

4.

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

A new unresolved item identified during this inspection is discussed in Paragraph 5.b.

5.

Preoperational Testing and System Run-In The inspector witnessed portions of the following test:

a.

Low Pressure Core Spray Preoperational Test Procedure, IE21PT01.

b.

HPCS Preeperational Test, IE22PT01.

c.

Thermal Expansion and Dynamic Test, IC88ST01.

d.

Reactor Vessel Flow Induced Vibration Testing Prior to Fuel Load, IF41ST01.

-

-

---

---

-- -

- -.. -

_ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___

__

'.

DETAILS 1.

Persons Contacted Licensee Employees

  • C. Abbott, Plant Quality Assurance L. Eisenberger, Startup Engineer
  • J. Elm, MPL Maintenance
  • M. Farschon, GE Operations Manager
  • C. Hutchinson, Startup Manager M. Madison, Startup Engineer

,

  • J. Roberts, Startup Supervisor
  • B. Stewart, Con truction
  • S. Tanner, QA Construction Coordinator
  • B. Wilson, MPL Maintenance Other licensee employees contacted included maintenance technicians, I&C technicians and operators.

,

  • Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on May 13, 1981, with those persons indicated in Paragraph 1 above.

,

j 3.

Licensee Action on Previous Inspection Findings Not inspected.

4.

Unresolved Items l

l Unresolved items are matters abcat which more information is required to l

determine whether they are acceptable or may involve violations or deviations. A new unresolved item ider.tified during this inspection is discussed in Paragraph 5.b.

!

5.

Preoperational Testing and System Run-In

!

The inspector witnessed portions of the following test:

a.

Low Pressure Core Spray Preoperational Test Procedure, IE21PT01.

b.

HPCS Preoperational Test, IE22PT01.

c.

Thermal Expansion and Dynamic Test, IC88ST01.

-

d.

Reactor Vessel Flow Induced Vibration Testing Prior to Fuel Load, IF41ST01.

!

i

-

i

.

  • .'

s,

..

.

Items inspected were procedure conformance to Regulatory Guide 1.68 and FSAR Chapter 14, Compliance with Test Procedures, selected test data acceptance criteria, compliance with General Maintenance Instruction 07-5-12-81 and 62, availability of completed Maintenance Calibration Instruction 07-5-53-19 and 181 for selected test instrumentation, and personnel awareness of test precautions and warnings.

a.

On May 10, 1981, an unsupported 3/4" test connections downstream of the High Pressure Core Spray (HPCS) inje: tion line outboard isolation valve, IE22F004, was found broken off during 40% flow testing of the spray system per procedure IE22PT01. The test connection is less than 2 feet long and supports two valve IE22F021 and IE22F022.

The break occurred immediately adjacent to.the weld. Preliminary investigatirn indicates that the probable cause is fatigue failure due to flow induced vibration. The broken pipe has been sent off-site for metallurgic examination. The line has been repaired and a support has been added to prevent recurrence. Review of pipe design documents indicates that no piping support was specified for the test connection.

The architc:: engineer (AE), has identified 5 other similar unsupported connections on the HPCS piping. All are outsice of containment.

The AE will provide a list of similar unsupported lines attached to all Class 1, 2, and 3 pipes in safety systems.

The licensee has committed to visually inspect each one of these during system run-in and provide hangers, as required.

This is an inspector follow-up item 50-416/81-14-01.

The licensee is currently evaluating the event to determine if a part 21 or 50.55(e) report is requ.r,ed.

b.

Inspection of the Low Pressure Core Spray (LPCS), suction valve (IE21F012) from the suppression pool on May 11, 1981, indicated that it was wired in accordance with schematic E-1182-01, but not in accordance with the associated connection diagram.

If the valve had been wired per the connecticq diagram, it would malfunction in a manner readily discernable.

General Maintenance Instruction 07-5-12-81, Step 7.3, requires verification per schematic and connection diagram.

This procedure had been completed January 30, 1981 for this valve.

No comment was made on the completed data sheet to indicate that the connection diagram was incorrect or that a revision was necessary.

Review of records by the cognizant test engineer, revealed no revision request was in processing. A Field Report E21-0011 is to be issued to request revision of the connection diagram.

Discussion with the test engineer indicated that he had issued two other field requests, FR-E21-0005 and FR-E21-0006, March 9,1981, under similar circumstances, (e.g., wiring was correct per schematic, but not in accordance with connection diagram) with neither Field Report, Document Change Notice, Startup Field Report, nor other normal means of revising drawings having been entered into the licensee document change system to enrrect these connection diagrams. This matter is considered an unresolved item 50-416/81-14-02.

,

b. '

m

- - -

__

,*

.

..

..

.

c.

Procedure IE21PT01, Step 7.6.2.11, requires the available NPSH be calculated. Data recorded on Data Sheat 8.7 per Step 7.6.2.7, does not include temperature, a necessary parameter for the calculation. A temporary Change Notice, TCN, was wr.4. ten to include the nece ey calculational data on Data Shaets 8.6 tid 8.7.

If Section 7.5 o

.he procedure had been completed prior to completion of 7.6, the required values would have been available. However, completion of the sections in non-numeric order was authorized by the procedure.

The licensee plans to include in future preoperational test procedures, steps to either take or verify that the data needed for calculations in a given section is available. The inspector had no further questions on this item.

d.

Procedure IE21PT01, Step 4.2.6, specifies vtter quality for injection into the reactor vessel must meet G.E. Specification 22A2707, Section 2.4.1.

Discussions with licensee personnel, revealed that Section 2.4.1 should have been 2.1.4 and the error had occurred because the prototype G.E. preoperational test procedure had a typographical error.

Further discussions revealed that Specification 22A2707 had been superceded by 22A2747. A memorandum from C. R. Hutchinson, Startup Engineer to J. W. Yelverton, QA Field Supervisor was isseed May 11, 1981, to specify that G.E. Specification 22A2747, paragraphs 4.7 and 4.14, water quality requirements, are to be adhered to during pre-operational and startup testing. The inspector had no further questions on this item.