Information Notice 1985-56, Inadequate Environment Control for Components and Systems in Extended Storage or Layup

Inadequate Environment Control for Components and Systems in Extended Storage or Layup

ML031180196
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill, Crane
Issue date:	07/15/1985
From:	Jordan E NRC/IE
To:
References
IN-85-056, NUDOCS 8507110108
Download: ML031180196 (4)

SSINS No.: 6835 IN 85-56

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

WASHINGTON, D.C.

20555

July 15, 1985

IE INFORMATION NOTICE NO. 85-56:

INADEQUATE ENVIRONMENT CONTROL FOR COMPONENTS

AND SYSTEMS IN EXTENDED STORAGE OR LAYUP

Addressees

All nuclear power reactor facilities holding an operating license (OL) or a

construction permit (CP).

Purpose

This information notice is being provided to alert addressees to problems which

can occur if equipment is improperly stored or laid up during construction or

extended plant outages.

Addressees

also are reminded that programs for proper

storage and preservation of materials and components are required by NRC

regulations (10 CFR 50, Appendix B), even though not specifically addressed as

license conditions.

It is expected that recipients will review the information

for applicability to their facilities and consider actions, if appropriate, to

preclude a similar problem occurring at their facilities.

However, suggestions

contained in this information notice do not constitute NRC requirements;

therefore, no specific action or written response is required.

Description of Circumstances

Licensee event reports, 10 CFR 50.55(e) reports, and NRC inspection reports

contain many instances where materials and components have been seriously

degraded due to improper storage, protection, or lay up, both at facilities

under construction and facilities with operating licenses. A number of repre- sentative examples are described in the following paragraphs.

A recent NRC inspection at Nine Mile Point Unit 2 disclosed that the cooling

water heat exchanger for the high pressure core spray diesel generator had

water standing in the tube side of the unit.

The heat exchanger had been

delivered to the site and had been "stored in place" in 1977, but was not yet

in service.

The source of the water is unknown, but it has been hypothesized

that the heat exchanger had been inadequately drained after a manufacturer's

hydro-test in 1976.

The site construction organization had no program for

inspection or surveillance of equipment in storage.

Significant corrosion

damage was observed on the copper alloy tubes and the carbon steel tube sheets

and water boxes.

8507110108

IN 85-56 July 15, 1985 Corrosion damage similar to that described above was found during an NRC

inspection at Hope Creek.

In that instance, the two heat exchangers were

supplied for the engine cooling system for the plant emergency diesel genera- tors.

The heat exchangers had been received onsite sometime before, and stored

in place.

They had not yet been placed in service.

In November 1984 the licensee for H. B. Robinson Unit 2 notified the NRC that, while preparing for restart after a 10 month outage, numerous pinhole leaks had

been detected in the stainless steel service water piping.

Further examination

of the piping disclosed other corrosion pits that had not penetrated through

the wall.

Temporary repairs were accomplished by the use of about 800 welded

sleeves.

The licensee has submitted plans for future complete replacement of

the affected pipe.

The corrosion has been attributed to microbiological growth

in the stagnant water that was in the system during the extended outage.

Proper layup of the system could have precluded damage.

IE Information Notice

85-30 provides additional information on this phenomenon.

At Palo Verde, the licensee reported in June 1984 that corrosion attack had

been found on internal surfaces of two Unit 2 auxiliary feedwater pumps.

The

pumps had not been operated.

In December 1984, the licensee reported that the

corrosion had been caused by contaminated water inadvertently left in the pumps

after prestartup flushing of the system.

Discussion:

The cases cited above are a small sample of the wide variety of instances where

improper storage or layup has resulted in significant damage and extended plant

outages.

Many of the events are related to balance-of-plant equipment and are

not reportable to the NRC.

They do, however, often cause extended outages.

The Robinson service water piping damage extended the plant outage for 4 months, and additional down time will be required in the future to install the

replacement pipe.

At Palo Verde, it required extensive work and 6 months time to finally resolve

that the pumps were still serviceable.

10 CFR 50.34(a)(7) requires that each applicant for a construction permit shall

provide a description of the quality assurance program to be applied to the

construction of the facility in accordance with the requirements of 10 CFR 50,

Appendix B. 10 CFR 50.34(b)(6)(ii) requires a description of how the require-

-ments of Appendix B will be satisfied during the operation of each nuclear

power facility.

Among the requirements of Appendix B, Criterion XIII addresses

storage, cleaning, and preservation of materials and equipment.

IN 85-56.

July 15, 1985 No specific action or written response to this information notice is required.

If you need additional information about this matter, please contact the

Regional Administrator of the appropriate NRC regional office or this office.

Xw-a r g

/r

Divisi n of Emergency Preparedness

and IEgineering Response

J. B. Henderson, IE

492-9654 Attachment:

Attachment 1

IN 85-56

July 15, 1985

LIST OF RECENTLY ISSUED

IE INFORMATION NOTICES

Information

Date of

Notice No.

Subject

Issue

Issued to

85-55

85-54

Revised Emergency Exercise

Frequency Rule

7/15/85 Teletheraphy Unit Malfunction 7/15/85

85-53

85-52

85-51

85-50

Performance Of NRC-Licensed

Individuals While On Duty

Errors In Dose Assessment

Computer Codes And Reporting

Requirements Under 10 CFR

Part 21

Inadvertent Loss Or Improper

Actuation Of Safety-Related

Equipment

Complete Loss Of Main And

Auxiliary Feedwater At A PWR

Designed By Babcock & Wilcox

Relay.Calibration Problem

Respirator Users Notice:

Defective Self-Contained

Breathing Apparatus Air

Cylinders

Potential Effect Of Line-

Induced Vibration On Certain

Target Rock Solenoid-Operated

Valves

7/12/85

7/10/85

7/10/85

7/8/85

7/1/85

6/19/85

6/18/85

All power reactor

facilities holding

an OL or CP

All NRC licensees

authorized to use

teletheraphy units

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP, research, and test reactor, fuel cycle and

Priority 1 material

licensees

All power reactor

facilities holding

an OL or CP

85-49

85-48

85-47 OL = Operating License

-

CP = Construction Permit