Information Notice 1989-80, Potential for Water Hammer, Thermal Strafication, and Steam Binding in High-Pressure Coolant Injection Piping

From kanterella
Revision as of 04:52, 14 July 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Potential for Water Hammer, Thermal Strafication, and Steam Binding in High-Pressure Coolant Injection Piping
ML031190089
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, Crane
Issue date: 12/01/1989
From: Rossi C
Office of Nuclear Reactor Regulation
To:
References
IN-89-080, NUDOCS 8911270002
Download: ML031190089 (9)


UNITED STATES NUCLEAR REGULATORY

COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555 December 1, 1989 NRC INFORMATION

NOTICE NO. 89-80: POTENTIAL

FOR WATER HAMMER, THERMAL STRATIFICATION, AND STEAM BINDING IN HIGH-PRESSURE

COOLANT INJECTION PIPING

Addressees

All holders of operating

licenses or construction

permits for nuclear power reactors.

Purpose

This information

notice is being provided to alert addressees

to potential

pro-blems resulting

from failure of high-pressure

coolant injection((HPCI)

valves in a boiling-water

reactor (BWR) to prevent leakage of feedwater

into the HPCI system during operation

of the reactor at power. It is expected that recipients

will review the information

for applicability

to their facilities

and consider actions, as appropriate, to avoid similar problems.

However, suggestions

con-tained in this information

notice do not constitute

NRC requirements;

therefore, no specific action or written response is required.Description

of Circumstances:

On February 21, 1989, with Dresden Unit 2 operating

at power, temperature

was greater than normal in the HPCI pump and turbine room. The abnormal heat load was caused by feedwater

leaking through uninsulated

HPCI piping to the condensate

storage tank. During power operation, feedwater

temperature

is less than 350 0 F, and feedwater

pressure is approximately

1025 psi. Normally, leakage to the con-densate storage tank is prevented

by the injection

check valve; the injection valve, or the discharge

valve on the auxiliary

cooling water pump. The injection valve and the injection

check.valve

are shown in Attachment

1.On October 23, 1989, with the reactor at power, leakage had increased

suffi-ciently to raise the temperature

between the injection

valve and the HPCI pump discharge

valve to 275 0 F and at the discharge

of the HPCI pump to 246 0 F.Pressure in the HPCI piping was 47 psia. On the basis of the temperature

gradient and the pressure in the piping, the licensee concluded

that feedwater leaking through the injection

valve was flashing and displacing

some of the water in the piping with steam. This conclusion

was confirmed

by closing the pump discharge

valve and monitoring

the temperature

of the piping. As expected, the pipe temperature

decreased

to ambient.:891127000

o j, @

IN 89-80 December 1, 1989 Accessible

portions of the HPCI piping were inspected, and some loose pipe supports were found near the injection

valves. Concrete surfaces near the support attachment

points were spalled.The licensee declared the HPCI system inoperable

on October 23, 1989, and notified NRC pursuant to 10 CFR 50.72. After performing

a review under 10 CFR 50.59, the licensee opened the normally closed injection

valve, closed the normally open discharge

valve, and will use the discharge

valve temporarily

as the injection

valve.Temperature

measurements

on the HPCI piping at Dresden Unit 3 indicated

that less significant

leakage was occurring.

Discussion:

The event at Dresden is significant

because the potential

existed for water hammer or thermal stratification

to cause failure of the HPCI piping and for steam binding to cause failure of the HPCI pump. Further, failure of HPCI piping downstream

from the injection

valves would cause loss of one of two feedwater

pipes.The licensee has not heard the noise that is usually associated

with water hammers. Nevertheless, loosening

of the pipe supports, damage to concrete surfaces, and the presence of steam in the piping strongly Indicate that water hammers had occurred in the HPCI system, probably during HPCI pump tests or valve manipulations.

Temperature-monitoring

instrumentation

on the piping near the injection

valves was useful in detecting

the leak. NRC Information

Notices 85-76, 86-01, 87-10, and 88-13 all address water hammer events at other facilities.

Attachment

2 lists these and other references

mentioned

in this notice.Concern for potential

thermal stratification

in the HPCI piping is related to three events in pressurized-water

reactors (PWRs) that were the basis for issuing NRC Bulletin 88-08 and the three supplements

to that bulletin.

These events occurred in one of the Farley units and in two foreign reactors.

In all of the events, water leaked either from or to the reactor coolant system through closed valves in an emergency

coolant system. Thermal stratification

of water in the piping of the emergency

coolant system and fluctuations

of the interface

between the hot and cold streams of water resulted in thermal fatigue and cracking of the piping wall in the heat-affected

zones of welds and in the base metal. For these reactors, the configuration

of the piping between the reactor coolant system and the first valve in the emergency

cooling system is approximately

like the configuration

of the piping at Dresden. The licensee for Dresden does intend to examine the piping ultrasonically

at the next scheduled

outage to determine

whether detectable

damage has occurred.During the event at Dresden, the potential

for steam bindingv the HPCI pump existed because the discharge

valve was normally open. Events have occurred in PWRs that have resulted in steam binding of auxiliary

feedwater

pumps.Because the NRC staff was concerned

about the availability

of the auxiliary

-$ '

'4, IN 89-80 December 1, 1988 feedwater

pumps when needed to mitigate the consequences

of an accident, the staff Issued NRC Bulletin 85-01. The bulletin required that certain licensees develop Procedures

for monitoring

the temperature

of the pump discharge

to ensure that it remains at less than saturation

temperature

and to identify steam binding and restore the operability

of the system if it occurs.The NRC may issue additional

information

as more inspection

and analysis is completed.

This information

notice requires no specific action or written response.

If you have any questions

about the information

in this notice, please contact one of the technical

contacts listed below or the appropriate

NRR project manager. I* e4 Charles E. Rossi, Drec Division of Operational

Events Assessment

Office of Nuclear Reactor Regulation

Technical

Contacts:

Eric W. Weiss, AEOD (301) 492-9005 Roger Woodruff, NRR (301) 492-1180 Attachments:

1. Dresden 2 -High-Pressure

Coolant Injection

Line 2. Referenced

Generic Communications

3. List of Recently Issued NRC Information

Notices I

_ , r 1.5/1 1/89 7/18 /89 1 0/23/89 A 140 F 175 F 248 F B 180 F 220 F 275 F c INJECTION VALVES D I SCHARGE VALVE B FEEDWATER A FPC I PUMP TEST RETURN*(DRESDEN 2 -HIGH-PRESSURE

COOLANT INJECTION

LINE ul 0 C- +VD (D oFr a to c-, CD (D CO O CD CX)o -1 CDM..0

Attachment

2 IN 89-80 December 1, 1989 REFERENCED

GENERIC COMMUNICATIONS

1. NRC Information

Notice No. 85-76, "Recent Water Hammer Events," September

19, 1985.2. NRC Information

Notice No. 86-01, "Failure of Main Feedwater

Check Valves Causes Loss of Feedwater

System Integrity

and Water Hammer Damage," January 1, 1986.3. NRC Information

Notice No. 87-10, "Potential

for Water Hammer During Restart of Residual Heat Removal Pumps," February 2, 1987.4. NRC Information

Notice No. 88-13, "Water Hammer and Possible Piping Damage Caused by Misapplication

of Kerotest Packless Metal Diaphragm

Globe Valves," April 18, 1988.5. NRC Bulletin 85-01, "Steam Binding of Auxiliary

Feedwater

Pumps," October 29, 1985.6. NRC Bulletin No. 88-08, "Thermal Stresses in Piping Connected

to Reactor Coolant Systems," June 22, 1988; Supplement

1, June 24, 1988; Supplement

2, August 4, 1988; and Supplement

3, April.11, 1988.

Attachment

3 IN 89-80 December 1, 1989 LIST OF RECENTLY ISSUED NRC INFORMATION

NOTICES Information

Date of Notice No. Subject Issuance Issued to 89-79 89-56, Supp. 1 89-78.89-77 Degraded Coatings and Corrosion

of Steel Containment

Vessels Questionable

Certification

of Material Supplied to the Defense Department

by Nuclear Suppliers Failure of Packing Nuts on One-Inch Uranium Hexafluoride

Cylinder Valves Debris in Containment

Emergency

Sumps and Incorrect

Screen Configurations

Biofouling

Agent: Zebra Mussel Falsification

of Welder Qualifications

for Contractor

Employees Clarification

of Trans-portation

Requirements

Applicable

to Return of Spent Radiopharmacy

Dosages from Users to Suppliers Potential

Overpressurization

of Low Pressure Systems 12/1/89 11/22/89 11/22/89 11/21/89 11/21/89 11/20/89 11/7/89 11/1/89 All holders of OLs or CPs for LWRs.All holders of OLs or CPs for nuclear power reactors.All NRC licensees authorized

to possess and use source material and/or special nuclear material for the heating, emptying, filling, or shipping of uranium hexafluoride

in 30-and 48-inch diameter cylinders.

All holders of OLs or CPs for PWRs.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All manufacturers

and distributors

of radiopharmaceuticals

for medical use, nuclear pharmacies, and medical licensees.

All holders of OLs or CPs for nuclear power reactors.89-76 89-75 89-74 89-73 OL = Operating

License CP = Construction

Permit

IN 89-80 December 1, 1988 feedwater

pumps when needed to mitigate the consequences

of an accident, the staff issued NRC Bulletin 85-01. The bulletin required that certain licensees develop procedures

for monitoring

the temperature

of the pump discharge

to ensure that it remains at less than saturation

temperature

and to identify steam binding and restore the operability

of the system if it occurs.The NRC may issue additional

information

as more inspection

and analysis is completed.

This information

notice requires no specific action or written response.

If you have any questions

about the information

in this notice, please contact one of the technical

contacts listed below or the appropriate

NRR project manager.Charles E. Rossi, Director Division of Operational

Events Assessment

Office of Nuclear Reactor Regulation

Technical

Contacts: Eric W. Weiss, AEOD (301) 492-9005 Roger (301)Woodruff, NRR 492-1180 Attachments:

1. Dresden 2 -High-Pressure

Coolant Injection

Line 2. Referenced

Generic Communications

3. List of Recently Issued NRC Information

Notices*SEE PREVIOUS CONCURRENCE

EAB: NRR*RWoodruff:db

11/12/89 C:PB1:RIII

  • WShafer 11/13/89 IRB:AEOD*EWeiss 11/14/89 C:EAB:NRR*CHaughney

11/15/89 TECH EDITOR*RSanders 11/15/89 C:OGCB:NRR

  • CBerlinger

11/22/89 EAB:NRR*PBaranowsky

11/1§/89 D:06A.CERossi DO 11/;1/89 PM:PD32:NRR

  • BSiegel 11/15/89 I NRCIN 88-xx November x, 1988 monitoring

the temperature

of the pump discharge

to ensure that it is at less than saturation

temperature

and to identify steam binding if it occurs.The NRC may issue additional

information

as more inspection

and analysis is completed.

No specific action or written response is required by this information

notice. If you have questions

about this matter, please call one of the technical

contacts listed below or the Regional Administrator

of the appropriate

regional office.Charles E. Rossi, Director Division of Operational

Events Assessment

Office of Nuclear Reactor Regulation

Technical

Contacts: Eric W. Weiss, AEOD (301) 492-9005 Roger Woodruff, NRR (301) 492-1180 Attachments:

1. Dresden 2 -High-Pressure

Coolant Injection

Line 2. List of Recently Issued Information

Notices*SEE PREVIOUS EAB:NRR*RWoodruff:db

11/ /89 C:PB1:RIII

  • WShafer 11/ /89 CONCURRENCE

IRB:AEOD*EWeiss 11/ /L6 TECH EDITOR EAB:NRR PBaranomsky

11/1 5/89 PM:PD32:NRR

BSiegelrP 11115189 Ko D:DOEA:NRR

CERossi 11/ /89 1 /WY/89 Doc: 299A

4.1.d NRCIN 88-xx November x, 1988 temperature

of the pump discharge

to assure that it is at less than saturation

temperature

and to identify steam binding if it occurs.The NRC may issue additional

information

as more inspection

and analysis is completed.

No specific action or written response is required by this information

notice. If you have questions

about this matter, please call one of the technical

contacts listed below or the Regional Administrator

of the appropriate

regional office.Charles E. Rossi. Director Division of Operational

Events Assessment

Office of Nuclear Reactor Regulation

Technical

Contacts: Eric W. Weiss, AEOD (301) 492-9005 Roger Woodruff, NRR (301) 492-1180 Attachments:

1. Dresden 2 -High Pressure Coolant Injection

Line 2. List of Recently Issued Information

Notices EAB:NRR RWoodruff:db

11/11189 3BM tricpkoa~C:PB1:RILI~

WShafer-Cd,'

11/13/89 IRB:AEOD EWei S 11/1 /89 C:EAB:NRR CHaughney 11/ /89 TECH EDITOR 11/1ST/89 C:OGCB:NRR

CBerlinger

11/ /89 EAB:NRR PBaranowsky

11/ /89 PM:PD32:NRR

BSiegel 11/ /89 D:DOEA:NRR

CERossi 11/ /89