ML17277B021

Forwards marked-up Section 6.2 of FSAR Re Annulus Pressurization Load Evaluation,Per 831027 Telcon Request. Info Will Be Incorporated Into Next FSAR Rev

ML17277B021
Person / Time
Site:	Columbia
Issue date:	11/04/1983
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
References
GO2-83-1025, NUDOCS 8311160068
Download: ML17277B021 (7)

Text

REGULATORY 'ORNATION OISTRIBUTION SYN (RIBS)

ACCESSION NBR;8311160068 DOC ~ DATE: 83/11/04 NOTARIZED NO DOCKET FACIE:50 307 HPPSS Nuclear Pr oj ecti 'Unit 2i f0ashi ngton Public Powe 05000397 AOTH ~ NAIIE AUTHOR AFFILIATION SURENSENg G ~ C.

I'Iashington Public Power Supply System REC IP s NAME RECIPIENT AFFILIATION SCHWkNCERrA ~

Liceos)ng Sranch

'2'UBJECT:

Forwards marked-up Section 6,2 of FSAR re annulus pressurization load evaluationiper 83$ 027,telcon requests Info will be,.incorporated into next'SAR rev.

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,TITLE: Licensing Submittal:

PSAR/FS'AR Amdts 8, Related Cor r espondence'OTES:

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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 November 4, 1983 G02-83-1025 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention:

Mr. A. Schwencer, Chief Licensing Branch No.

2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

NUCLEAR PROJECT NO.

2 ANNULUS PRESSURIZATION (AP)

LOAD ADEQUACY EVALUATION, NEDO 24548 Per the telephone request of R. Auluck and R. Li (NRC) on October 27, 1983, attached is a copy of the changes to Section 6.2 of the FSAR regarding AP Load Evaluation (GE document NEDO 24548).

Final submittal of the changes will be made in the next amendment to the FSAR.

If there are any questions, please contact Mr. P.

L. Powell, Manager, WNP-2 Licensing.

Very truly your G.

C. Sorensen, Acting Manager Nuclear Safety and Regulatory Programs BDP/tmh Attachment cc:

R Auluck -

NRC WS Chin

- BPA R

Li NRC AD Toth NRC Site R

0068 83igp~

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MNP-2 e.'HDHENT NO, 25 June 1987 Current state-oC-the-art industry method.,

were used for these annulus pressurization calculations.

These methods resul.t in more realistic prediction oC pressures as compared to the

.more conservati.ve calculations discussed previously.

Each of the three change employed are described below:

Annu 1 a r Volume The current industry approach is to utilize the annular volume excluding the RPV insulation, vo'-

ume which is conservatively

=ssumed not to be available.

This approach is conservatively as-sumed not to he available.

This approach is conservative but more realistic than previous analyses where only the annular volume on one side of the RPV insulati.on was available.

b.

Finite Time Dependent Blowdown The bio<<down loading values given in Reference 5.2-11 were derived with the assumption that the pipe break would occur instantaneously and that the annulus area would se>>

Lhe maximum blowdo<<n instantaneously.

Actually, the Cull flow Crom the severed pipe can not be realized until the severed pipe ends separate a distance equal to one half (1/2) the pipe diameter.

Movement ac-tually occur." in a finite time and is a Cunction of the stiffnes characteristi.cs of the pipe and the restraining capability of he pipe whip restraints..

'- gg+

Current i.n stry practice was used to deve3.op displacem nt versus time data for a finite break opening; the General Electric analytical method 4Ju Cor det rmining the short-term mass and energy release.

The analysis was util.ized Cor the reArculation loop break, but not for the feedwater line since it was determined that the small precentage reduction Cor the feedwater would not warrant the additional calculations.

S USeg C.

Feedwater Break Blowdown Data The bio<<down analysis Cor the postulated Ceed-water line break

<<as based on a comprehensive developed for the entire Ceedwater system from the condenser.

to the reactor vessel.

This

model, in conjunction with the REI.AP4/t4OD5 com-puter program (Reference 6.2-14) was used to calculate the transient and energy blowdown data.

6.2-33e

WNP-2 At4ENDtdENT HO.

25

.June 1982 static load, utilizing the appropriate dynamic load factors.

The components stre ses were found to be within the values specified in the appropriate

Codes, however, after a

J.OCA, re-fueling a bulkhead would require requalif ication prior to use.

Thi.s is consi!ered acceptable since the refueling bulkhead does not perform a

safety-related function and would not become a

mi"sile during the postulated I.OCA.

The analyses Cor the annulus were reported in Cull detail in References

5. 2-9 through

6. 2-ll.

All potential pipe breaks within the sacriCicial shield wall have been <<valuated.

The inCormation is contained in References 3,.0-5, 3.8-6, 3.8-7, and 3.8-24.

These reCerences have been previously submitted to the NRC.

The result of the case of a 60-node model of the shield wall annulus Cor pressure transient. calculation was confirmed by the

NRC, and the analysis was con. idered accept-able for the shield wall base design and the design of the shield wall above the base, as stated in NRC letters (Refer-ences 6.2-12 and 6.2-13).

Peak and transient loading used to establi"h the adequacy of the sacrificial shield wall, including the time/space depen-dent forcing functions are presented in References 6.2-9 through

6. 2-1l and 3.8-24.

Sub-equently, a more realistic approach was used in determin-ing loads Crom postulated pipe break. within'he annulus area.

These loads were used to produce response spectra for use in evaluating the secondary effects (the dynamic effects on piping systems, equipment, and components attached to the sacrificial shield wall of the RPV).

Three principal changes were made in the assumptions used in the previous more con-servative sacriCical shield wall analysis.

Namely:

a.

The volume in the annulus was utilized to re-ceive the blowdown with the RPV installation volume conservatively assumed not to be available.

(gag~ Zygo~)

b.

A finite tim dependent blowdown was used for the recircul tion break, utili.zing NSSS supplier methodology The effect of subcooling has been taken into account.

c.

The feedwater pressurization analysis was devel-oped utilizing blowdown values developed by de-tailed computer analysis rather than the pre-vious hand calculation method.

6.2-33d

HENDHENT NO.

1 1

September 1980 Washington Public Power.

Supply System, Nuclear Pro ject No.

2, Report No.

WI'I>SS-74-2-R2-l3, "Sacrificial Shield Wall Design Supplemental Information", August,19, 1975.

Letter from R.

C.

DeYoung of NRC to J.

J. Stein of

WPPSS, dated August 13, l975.

Subject:

Sacrificial Shield Wall Design.

Letter from R.

C.

DeYoung of NIIC to J. J. Stein of

WPPSS, dated October 15, 1975.

Subject:

Sacrificial Shield Wall Design.

ANCR-NOREG-135, "RELAP4/HOD5 A Computer, Program for Transient Thermal-IIydraulic Analy. is of Nuclear.

Reactor and Related Systems Users Manual" 3

volumes, September, 1976.

AEC-TR-6630, "IIandbook of Hydraulic Resistance, Coefficients of I'ocal Resistance and of Friction", by E. Idol'h ick, 1960.

I3i]anin, W. 'I., "The General I ] ectric Hark TlI Pressure Suppression Containment System Analytical Hodel," June

1974, (NED0-20533).

"Loss-of'-Coolant Accident and I.',mergency Core Cool.ing Hodels for General Electric Boil.ing Water Reactors" Licensing 'I.'opical Report INI.:.DO-108 9,, General Electric, April 1970.

A.

K. Post and B.

H. Johnson, "Containment Systems Experiment Final Program Summary",

BNWL-1592, Battelle Northwest,

Richland, Washington, July 1971

~

G.

Knudsen and R.

K. Hilliard, "Fission Product Transport by Natural Processes in Containment Vessels",

BNWL-943, Battelle Northwest,

Richland, Washington, Jan.

1969.

R.

K. Hilliard and L. F.

Coleman, "Natural Transport Effects on Fission Product Behavior in the Containment Systems Experiment",

BNWL-1457, Battelle Northwest,

Richland, Washington, Dec.

1970.

R.

K. Hilliard, "Removal of Iodine and Particles from Containment Atmospheres by Sprays -- Containment Systems Experiment Interim Report",

l3NWL-1244, Battelle Northwest,

Richland, Wa -.hington, I."eb.

1970.

9.K, Sha.f e,~ /

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