ML18003B308

Forwards Addl Info Re NUREG-0737,Item II.D.1, Relief & Safety Valve Test Requirements & SER Confirmatory Item 6. Info Suppls & Amends 840628 Response

ML18003B308
Person / Time
Site:	Harris
Issue date:	06/06/1986
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NLS-86-197, NUDOCS 8606120334
Download: ML18003B308 (23)

Text

REQULATORY INFORI'1ATION DISTRIBUTION SYSTEI'1 (R IDS)

ACCESSION NBR: 8606120334 DOC. DATE: 86/06/06 NOTARIZED:

NO DOCIcET 0 FACIL:50-400 Sheav on Hav v'is Nuclear Power Plant>

Unit 1> Carolina 05000400 AUTH. NANE AUTHOR AFFILIATION ZINNERBON> S. R.

Cav olina Powev'c Light Co.

RECIP. NAI'IE REC IP IENT AFFILIATION DENTON> H. R.

Office of Nuclear Reactor Regulation>

Director (post 851125

SUBJECT:

Forwards addi info v e NUREQ-0737> Item II. D. 1> "Relief 5 Safety Valve Test Requirements" 0

SER Confiv matov g Item 6.

Info suppls 8c amend,s 840628 response.

DISTRIBUTION CODE:

B001D COPIEB RECEIVED: LTR l ENCL I BI ZE:Q TITLE: Licensing Submittal:.PBAR/FSAR Amdts 8c Related Covrespondence NOTES: Application for pev mit v enewal +iled.

05000400 REClP IENT ID CODE/NAI'1E PWR-A EB PWR-A FOB PWR-A PD2 PD PWR-A PBB INTER NAL:.ADI'1/LFI'1B IE FILE IE/DGAVT/GAB 21 NRR PWR-B ADTS N

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6 SERIAL: NLS-86-197 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. I - DOCKET NO.50-000 TESTING OF SAFETY AND RELIEF VALVES

Dear Mr. Denton:

Carolina Power i!r. Light Company (CPRL) hereby submits additional information concerning testing of safety and relief valves at the Shearon Harris Nuclear Power Plant.

This information is being submitted in response to NUREG-0737 Item II.D.l, "Relief and Safety Valve Test Requirements" and Safety Evaluation Report Confirmatory Item No. 6. The attached information supplements and amends CPRL's previous response dated June 28, 1980.

If you have any questions on this subject or require additional information to close this issue, please contact me.

Yours very truly, SRZ/3HE/mf (39003DK)

Attachment S.. Zi merman nager Nuclear Licensing Section cc:

Mr. B. C. Buckley (NRC)

Mr. G. F. Maxwell (NRC-SHNPP)

Dr. 3. Nelson Grace (NRC-RII)

Mr. Travis Payne (KUDZU)

Mr. Daniel F. Read (CHANGE/ELP)

Wake County Public Library Mr. Wells Eddleman Mr. John D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB)

Dr. J. H. Carpenter (ASLB)

Mr. 3. L. Kelley (ASLB) 8bQbi20334 8bObOb PDR ADOCK 05000400 E

PDR, 411 Fayettevilte Street o P. O. Box 1551 o Raleigh, N. C. 27602

SHEARON HARRIS NUCLEAR POWER PLANT

'AFETY RELIEF VALVE EVALUATION SUPPLEHENTAL REPORT Page 1 of 19

WKKF08 INTRODUCTION This report supplements CPGL's previous response to NUREG-0737, Item II.D.1 "Testin of Safet and Relief Valves" dated June 28, 1984.

The previous report addressed analysis of the safety and relief valve discharge system as well as valve operability for the motor operated block valves, power operated relief valves, and safety valves.

This supplemental report has been issued to discuss the modifications made to the safety valve discharge piping and how those changes affect the ori,ginal report.

It is important to realize that only information pertaining to them has been revised.

The balance of the original report has not been changed and remains as CP&L's official SHNPP response to this TMI Item.

The need to make modifications to the safety valve discharge piping became evident during an engineering review of the present heat transfer analysis on the SRV inlet loop seal piping.

The original analysis was a HEATING5 heat transfer calculation that predicted the average loop seal temperature for the volume of water that protects the SRV seat.

The loop seal temperature directly affects the discharge piping loads because large amounts of flashing are required across the safety valve to disperse the slug momentum forces.

The higher the loop seal temperature the larger the percentage of steam flashing across the SRV.

A 370'F average loop seal temperature was shown to be high enough to prevent translation of excessive stresses to the inlet piping.

The HEATING5 analysis predicted that six inches of MIN-K insulation surrounding the inlet piping would retain the necessary heat to maintain the average loop seal temperature above 370'F.

Review of the calculation versus the as-built product led to a decision to monitor the temperature profile during the January 1986 Hot Functional Testing of the plant.

Measurement of the temperature profile was performed by the site engineering group by installing thirty thermocouples on two loop seals.

All of the thermocouples were run below the MIN-K insulation and physically contacted the pipe wall.

As expected both of the loop seals had similar temperature profiles but there was a

significantly reduced average loop seal temperature of 209.1'F (see figure 1 which shows the as measured test temperatures).

This was far below the required 370'F temperature needed for acceptable stress analysis.

The cool temperature indicated that there would be no flashing across the SRV during a high pressure relief which meant stress levels would be excessive.

An Engineering evaluation of possible system modifications to eliminate this problem was completed.

Three of the evaluated options were:

A.

Install heat tracing on the loop seal to artificially heat the loop seal volume to a point above the stress analysis figure of 370'F.

Page 2 of 19

WKKF08 B.

Drain the loop seals and replace the safety valves internals to the high temperature steam seats, C.

Modify the discharge piping to accept the cool loop seal volume and separate it from the normal steam flow path.

The installation of heat tracing was unacceptable because it was an active system.

It would require redundant wiring and it would add to the number of items that require regular maintenance.

The draining of the loop seals would require the installation of high temperature seats in the SRVs.

Flexidisks have long delivery lead times and their delivery could not support the present fuel load date.

The final option was to 'accommodate the cool loop seal slug by modifying the discharge piping with a slug diversion device that could separate the fluid volume from the steam such that a clear steam path could be established.

This type of modification had the advantage of being a passive resolution which would require no maintenance and also not effect the Class 1 portion of the piping.

SYSTEM DESCRIPTION The addition of the slug diversion devices (slug traps) to the SRV discharge piping was a physical add-on type change.

It did not change the overall layout with respect to 'the PORV piping and the main header to the pressurizer relief tank.

Both layout and detail views are shown in figures 2 and 3 respectively.

The slug trap is simply a device that separates the water from the steam in a two phase flow.

For the SHNPP application, the slug trap is designed to catch the loop seal volume of water as it leaves the discharge of the relief valve.

The slug trap is aligned in a lin ar path with the discharge of the relief valve which ensures, by reason of

momentum, that the loop seal volume won't direct itself towards the free steam path.

The slug trap is oversized volumetrically with respect to the loop seal water volume.

The slug traps stand vertically and at the bottom of each slug trap there is a drain connection which has a limiting 3/8 inch orifice to slow the flow down enough such that it can drain into the main pressure relief header and hence have negligible affect on the flow dynamics.

The three drains from each slug trap tie together to one line which ties into the main 12 inch header.

ORIGINAL~REPORT CHANGES II The following are paragraphs which contain changes and/or

'larifications to the original licensing report entitled NLS-84-263 Testin of Safet and Relief Valves.

The following is intended to amend that report such that it.incorporates the Slug Diversion Devices and their influence to the system design.

In the System Description section, the stress isos utilized in figures 2.1; 1, 2.1.2, and 2.1.3 on pages 4, 5, and 6 respectively will be replaced by the attached sketches which are annotated by a Rev.

1 designation.

Page 3 of 19

WKKF08 On page 9, the third paragraph should be clarified as such:

The six inch discharge piping from the SRV's are connected to the 12 inch common header which leads to the relief tank and to which the PORV common six inch discharge line is also connected.

Each of the six inch discharge lines from the SRV's are equipped with a slug diversion device to remove any liquid remaining from the loop seal at discharge.

The slug diversion devices are initially six inch in diameter and then they transition to ten inch diameter pipe.

On page 10, paragraph 2, the last sentence should be revised to read:

The initial steady state temperatures of the water in the loop seals are based on measured data taken during the SHNPP Hot Functional Testing.

The Stress Analysis Section, beginning on page 147.and ending on page 155, should be completely superceded by the following paragraphs:

The Pressurizer relief system piping stress analysis was performed by Westinghouse.

Westinghouse utilized the RELAP5/MOD1 forcing functions generated by EBASCO by converting them to their WESTDYNE computer program.

Westinghouse also utilized the plant as-built dimensions as well as the as-measured temperature profiles to generate their stress report.

The final stress analysis was submitted to CP&L within the Reactor Coolant System final stress analysis (Ref.

10) on May 3, 1986.

Attached are the pages that are relative to the pressurizer relief system piping.

The addition of slug diversion devices required several changes to the hangers that support the discharge piping and in some cases loads became larger but the end result was an overall acceptable stress analysis within the applicable codes.

Under References one additional document should be shown:

10.

Class 1 As-built anal sis-RC S stem submitted to CPSL May 3,

1986 Westinghouse letter CQL-9320.

The original response to NUREG 737 Item II.D.1 that was submitted under Licensing Letter NLS-84-263 also included a report entitled "0 erabilit of Pressurizer Safet Relief Valves, Power 0 crated Relief Valves and Electrical Motor 0 crated Block Valves' The modifications to the SRV discharge piping in no way affect this report because even though it is now recognized that SHNPP will have a.significantly lowered average loop seal temperature than was previously predicted, it will still be enveloped by the range of test values performed by EPRI.

The SHNPP average loop seal temperature was measured to be 209.1 F and the range of test temperatures was from 100 F to 350 F.

Page 4 of 19

WKKF08

SUMMARY

The addition of Slug Traps to the discharge of the SRU's was a

change mandated by the incorporation of as measured data into the design analysis.

This change in no way hinders the operation of the plant and it ensures that the hydrodynamic forces inherent to relief valve actuation will not be excessive by means of separating the cool loop seal volume from the hot steam flow path.

Page 5 of 19

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FAULTED CONDITION - PRIMARY STRESS

SUMMARY

NODE POINT 2000 3072 3020 3042 7000 5250 5520 5700 PIPING COMPONENT Straight Pipe Long Radius Elbow Butt Weld 5 Diameter Bend Tee Branch Connection Reducer Welded Attachment MAXIMUM EQUATION 9 STRESS (ksi) 15.7 21.1 19.3 12.1 11.9 26.1 19.5 21.8 ALLOWABLE STRESS 3.0 Sm (Vsi)

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