ML19321A053

Responds to NRC 800502 Request for Info Re Pressurizer Safety Valves.Forwards Gilbert Associates,Inc 800630 Analysis of 800226 Pressurizer Transient Relief Valve Discharge. Supporting Ltrs Encl

ML19321A053
Person / Time
Site:	Crystal River
Issue date:	07/17/1980
From:	Baynard P FLORIDA POWER CORP.
To:	Reid R Office of Nuclear Reactor Regulation
Shared Package
ML19321A054	List: ML19321A053 ML19321A056
References
3.B.5-A, NUDOCS 8007220383
Download: ML19321A053 (9)

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.a Fkrida Power C O M PO R A Y IO *s July 17, 1980 File: 3.B.5-a Mr. Robert W. Reid Chief Operating Reactors Branch #4 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 NRC letter dated May 2,1980, Requesting Information Concerning Pressurizer Safety Valves.

Dear Mr. Reid:

In response to the subject letter requesting information concerning Pressurizer Relief Valves, Florida Power Corporation hereby submits the enclosed report on thermal analysis of the relief piping prepared by Gilbert Associates, Inc.

As indicated in our June 25, 1980 letter, we will transmit to you EPRI inspection report on CR-3 Pressurizer Safety Valves, RCV-8 and 9, when it becomes available.

Should you have any questions on this report, please contact this office.

Very truly yours, FLORIDA POWER CORPORATION atag} hpA l

P. Y. Baynar'd Manager Nuclear Support Services Attachment IHIS DOCUMENT CONTAINS

• P00R QUAUTY PAGES Baynard (WO9)D3-1 b

8 00gg g y gg ; street sootn. P O Box 14042. St Petersburg. Flonda 3373 General Office 320 rmrtuourth

STATE OF FLORIDA COUNTY OF PINELLAS

't P. Y. Baynard states that she is the Manager, Nuclear Support Services of Florida Power Corporation; that she is authorized on j

the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of her knowledge, information and belief.

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E7. U Bayndrd Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 17th day of June, 1980.

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Notary Public, State of Florida at Large, My Commission Expires: June 8, 1984 HansfordNotary (D12)

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Flors da : ower Corporat ion P. O. Box 14042/11-S St. Fetersburg, Florida 33733 Re:

RCV-10(F) Piping to Keactor Coolant Drain Tank Crystal River Unit (3 Fef:

FCS 1217

Dear Mr. Simpson:

The refs enced letter stated that Gilbert censidered the submittal of the "Frr. surizer Transient Relief Vcive Discharge h port" to be final based on the facts presented. One item that was not discussed in depth is the fact that the-subject valve v.1s enslyzed as a low capacity. type, i.e., 106,172 f/hr., whereas in reality the vc1ve is a high capacity type with a discharge rate of 152,888 f/hr.

k' hen Gilbert performed the analysis for the report, the discharge l

capacity was assumed to be 117,000 #/hr. (to account for accumulation).

Fi ure 2 of the report clearly shows that the loed generated is approxi-f mately.4 Kips whereas the original design load was 2 Kips.

If the higher capacity valve RCV-10(F) was used in the analysis, the load would not deubic, but more than likely increase in proportion to discharge rates. The conservative doubling of the load would. provide a'.8 Kip value which is still well helow the original 2 Kip design.

Apain, Gilbert reiterates that the integrity of the piping system from the Prersuriter to the Reactor Coolant Drain Tank has not been jeopardized as a result of the February 26' incident and that the CR-3 Unit is safe to operate in situ.

Should there be any~ questions, please advise.

Very tru v yours,

.N k F. J.

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FJT:ejf Project Manager ec:

E. C. Simpson P. L. F.unker F. J. Tomazie (2)--

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Gilbert / Commonwealth enaineers and consuitants ll GILBERT ASSOCIATES. INC P. O Box 1498. Reading. PA 19603/Tet 215 775-2600, Cable Gilasoc/ Telex 836 431),

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July 3, 1980 y-7 FCS - 1217 Mr. E. C. Simpson Manager, Nuclear Engineering Florida Power Corporation P.O. Box 14042/H-8 St. Petersburg, Florida 33733 Re: Final Analysis of February 26, 1980 Pressurizer Transient Relief Valve Discharge Report 04-4862-008, Frag 42600 Crystal River Unit #3 Ref: FCS 1204 and 1209

Dear Mr. Simpson:

The first referenced letter stated that the subject report was " Preliminary" since verification was not complete and the higher nozzle loadings have not been approved by B&W.

The second referenced letter provided the verifica-tion required.

In a telecon with B&W yesterday with our Mr. R. A. Snow, the nozzle loadings have been approved and a letter stating acceptance will be issued today by B&W.

Gilbert has also performed an analysis of the supports attached to the piping from the Pressurizer (RCV-8F) to the Reactor Coolant Drain Tank in accordance with IE 79-02 and determined that the supports meet the criteria under design loading conditions.

One support, RCH 55, did not meet the safety factor of 4 criterion under the abnormal loading conditions that occurred on February 26, 1980. This safety factor with this loading is between 2 and 4.

Support RCH 35 was determined to exceed the maximum length as recommended in Power Piping Companies (PPC) catalog.

PPC was contacted today and they have advised thatif the design loadings in-clude the abnormal loading conditions (steam and water hammer as well as two phase flow) than these'two supports should be replaced. PPC also stated that the supports are still adequate in spite of the abnormal-loadings provided that these snubbers be stroked in and out to verify that the piston rod is not bent or there is no damage to the wiper or bearing. The adjusting rod should also be checked for samage.

Your Mr. R. C. Widell was notified ~of these con-cerns this morning.

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St. Petersburg, Florida 33733 FCS 1217 July 3, 1980 Page 2 Mr. R. C. Widell has advised Gilbert via telecon that no danage has occurred to RCll 35 and 55 based on the above concerns. Therefore, Gilbert considers the report issued via FCS 1209 final. The CR 3 unit is not in ieopardy for saf e operation as a result of the February 26, 1980 incident and no additional action is re-quired at this time.

In order to make the report complete, B&W's letter ac-cepting the nozzle loadings should be attached to the report.

Should there be any questions, please advise.

Very truly yours, l

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Toma c Project Manager cc:

E. C. Simpson R. A. Snow R. Kopicki P. Bunker F. J. Tomazic (2)

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d Gilbert / Commonwealth engineers and consuitants GILBERT ASSOCIATES, INC, P. O. Bcx 1498, Reaing, PA 19603/Tel 215 775-2600/ Cable Gdasoc/ Telex B36431 July 2, 1980 FCS 1216

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Rcw LivML Mr. E. M impson 3

Manager, Nuclear Engineering PRODUCTION O

ENGINEER!NG Florida Power Corporation 9

P.O. Box 14042/H-8 Y

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Re: PORV RCV-10(F)

High Capacity Discharge Problem 04-4762-065 Crystal River Unit #3

Dear Mr. Simpson:

Gilbert has performed a conservative hand calculation and deter-mined that the nozzle loads on the PORV with the high capacity discharge orifice are below allowables.

This analysis does not affect the status of the piping from the pressurizer to reactor coolant drain tank (Frag 426).

Comments on that status will be issued under separate cover.

In order to keep the records up to date please provide from Dresser sepias of'the installed PORV and send one first-run copy to Gilbert.

Should there be any questions, please advise.

Very truly yours, A

FJT:RS:ac R. Snow Piping Engineer cc:

E. C. Simpson F. J. Tomazic (2)

R. Snow F.

Tomaz Dept. 0430 File Project Manager NM fob test u nWm W Jacasan, na w nsarr:10 rw sunc, he. Yes, rr tu eseo

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P.O Box 1260. Lyn-bburc. Va. 24505 Te'e; hone: (834) 384-5111 July 2, 1980 FPC-80-019 Mr. E.C. Simpson

- Engineering Manager Florida Power Corporation Post Of fice Box 14042 St. Petersburg, FL 33733

Subject:

Crystal River 3 Nuclear Station Stru.ctural Evaluation of the Code Safety Valve Nozzles

Reference:

Letter, R.L. Pittman to D.H. t eck, CR-80-151. dated April 11, 1980 Task 151

Dear Mr. Simpson:

As part of the reference Task 151, Babcock & Wilcox has conpleted an ASME stress analysis on the Pressurizer Code Safety Valve Nozzle using the reaction loads at the nozzles provided by gal.

The calculated stresses were less than the code allowable stress limits for normal operation.

The technical analysis and evaluation has been completed and QA'd to support startup of the CR-3 plant.

The stress report must still be revised including a certification docunent with the calculational package.

Should you have any questions or comaents, please contact me.

Very truly yours, W /? J14 <.

M.R. Stephens Engineering Product Manager MRS/kjb cc:

D.C. Poole-P.Y. Baynard W.P. Ellsberry B.H. Zias r, e ~,-s s. wa e. r m,. i r. ee.e ins 7

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,,era Mr. E. C. Simpson Manager, Nuclear Engineering Florida Power Corporation P. O. Box 14042/H-8 St. Petersburg, Florida 33733 Re:

Crystal River Unit #3

" Analysis of February 26, 1980 Pressurizer Transient Relief Valve Discharge" Report 04-4762-008, Fragment 42600

Dear Mr. Simpson:

Attached are the verification forms for the calculation of the internal piping forces due to the incident water discharge transient and the cal-culation of the piping stresses and piping loads on the pressurizer, reactor coolant drain tank and the pipe supports.

Pending Babcock and Wilcox's approval of the forces and moments on the pressurizer, this report is considered final.

The authorization will be completed with the submit-tal of the calculations next week.

If you have any questions about this subject, please call me.

Yours t uly, RS:FJT: lap i

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Ron Snow Piping E gineer

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E. C. Simpson F. J.

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