ML18219D101
| ML18219D101 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/08/1978 |
| From: | Tillinghast J Indiana Michigan Power Co |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:00015 | |
| Download: ML18219D101 (12) | |
Text
g os'jef~w REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-3
/316 REC:
DENTON H R
NRC ORG:
TILLINGHAST J IN Cc MI PWR DOCDATE: 08/08/78 DATE RCVD: 08/30/78 DOCTYPE:
LETTER NOTARIZED:
NO COPIES RECEIVED
SUBJECT:
LTR 1
ENCL 1
RESPONSE
TO NRC LTR DTD.05/18/78... FURNISHING ADDL INFO CONCERNING VIBRATORY LOADS ORIGINATING FROM THE POSITIVE DISPLACEMENT PUMPS>
ASSOCIATED WITH THE CHEMICAL AND VOLUME CONTROL SYSTEMS OF SUBJECT FACILITY"S...NOTARIZED 08/08/78...
W/ATT INFO.
PLANT NAME: COOK UNIT REVIEWER INITIAL:.
XJ COOK UNIT 2 OISTRIBUTER INITIAL: j DISTRIBUTION OF THIS MATERIAL IS AS FOLLOW NOTES:
I 8c E 3 CYS ALL MATERIAL GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
<DISTRIBUTION CODE A001)
FOR ACTION:
INTERNAL:
BR CHIEF ORBQi BC+4W/7 ENCL REG 4W/ENCL E+<Qg, ENCL HANAUERcc+W/ENCL AD FOR SYS 5 PROJ<+W/ENCL REACTOR SAFETY BR++W/ENCL EEB++W/ENCL J.
MCGOUGH+4W/ENCL NRC PDR+4W/ENCL OELD++LTR ONLY CORE PERFORMANCE BR++W/ENCL ENGINEERING BR++W/ENCL PLANT SYSTEMS BR<+W/ENCL EFFLUENT TREAT SYS++W/ENCL EXTERNAL:
LPDR S ST.
JOSEPH'I++W/ENCL TERA4+W/ENCL NS I C+ >W/ENCL ACRS CAT B++W/ib ENCL ISTRIBUTION:
LTR 40 ENCL 39 SIZE:
3P+iP THE END CONTROL NBR:
7324300oo
/%
INDIANA & MICHIGAN POWER COMPANY P. Oi BOX 18 Bo WL IN G G R E EN STAT ION NEW YORK, N. Y. 10004 August 8, 1978 AEP:NRC:00015 Donald C.
Cook Nuclear Plant Unit 1
and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 Mr. Harold R. Denton, Director Office of Nuclear Reactor'egulation U.S.
Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
This letter is in response to Mr.
A.. Schwencer's letter dated May 18, 1978,. in which he requested additional information to vibratory loads originating from the positive displacement
- pumps, associated with the Chemical and Volume Control Systems of the above captioned. units.
This response was to be sub-mitted. within 60 days of the date of the May 18, 1978 letter,
- however, an extension of two-three additional weeks in our time to respond in this matter was requested and granted by M.
Mlynczak of your staff.
In light of Mr. 'Schwencer's
- letter, CVCS Systems for both Unit 1
and Unit 2 have been reviewed.
Our responses to the re-quest for additional information is given below.
During performance of initial preoperational testing on Donald C.
Cook Plant Units 1
8 2,: observations of the vibration levels on the reciprocating charging pump discharges were made and found to be acceptable.
These observations were performed during various system preoperational tests as directed by operational testing acceptance criteria AC-000-001 which was developed to comply with. FSAR Section 13.1 and FSAR Response to guestions 4.7 and 4.30.
The data generated by these tests for the reciprocating charging pump discharge is included as Table 1.
782430098
Nr.
Har ol d R.
Denton August 8, 1978 Our extended operating experience has confirmed that the vibration levels experienced on this system are acceptable.
- However, both units at the Donald C.
Cook Plant have been ex-periencing some pressure pulsations on the reciprocating charging pump affecting the control systems'esponse.
Ne have decided that pulsation dampening devices should be installed at the re-ciprocating pump discharge to reduce these pressure pulsations.
A specific vendor has
- not, been chosen to provide these dampeners.
- However, we anticipate vendor selection and issuance of a pur-chase order for these dampeners within 60 days of the date of this letter with normal delivery being 24 to 30 weeks thereafter.
We have evaluated the information requested in items 2
through 6 of Nr. Schwencer's letter and have concluded that since test data in this depth was not anticipated during preoperational
- testing, we do not have the specific information you requested.
Although the present vibration levels are acceptable, in our opinion addition of these pressure pulsation dampeners should have a beneficial effect on reducing pump induced piping system vibrations.
- However, we wi 11 provide the information requested in item 1 to the NRC after verification testing following installation of these dampeners.
Very truly yours, JT:em ce President Sworn and subscribed to before me this 9~day of August',
1978 i'
Notary P
i GREGORY M. GURICAN Notary pu>hc, State ot New York No 31-4643431 Qualified in New York CountY ~
Commission Expires March 30, 19~
cc:
(attached}
Mr. Harold R,, Denton August 8, 1928 cc:
R.
C. Callen G. Charnoff P.
W, Steketee R. J. Vollen R.
Walsh D.
V. Shaller-Bridgman R.
W. Jurgensen
TABLE 1 Results of Observed Displacements on Reciprocating Charging Pump Discharge Piping Observed Double Amplitude Inches UNIT Single Uncorrected Amplitude Hanger Span-inches Ft Acceptance Criteria inches 0
0 0
0 0
0 10 10 18
.18
.18
.60 Unit 2 1/8 1/16 1/8 0'
1/8 1/16 1/32
.063 '0
.032 10 063 14.
0 7
0 5
.o63 lo
.o32 24.
.o16 5
- 18
.18
.36
.10
.05
.18 1.08
.o5
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FQR INCOMING MATERIA(
50-316 REC:
DENTON H R ORG:
B-I-M4W R E DOCDATE: 07/21/78 NRC IN 8( MI PWR DATE RCVD: 07/28/78 DOCTYPE:
LETTER NOTAR1ZED:
YES COPIES RECEIVED
SUBJECT:
LTR 1
ENCL 0 FURNISHING NOTIFlCATION OF LISTED" DOCUMENT TRANS UNDER SEPERATE COVERS CONTAINING lNFO RE ENVIRQN QUALIFICATION Ol= BARTON TRANMISTTERS AND ADVISING INFO CONTAINED IN LISTED LTRS DOES NQT CONSTITUTE A SAFETY QUESTION RE ADVERSE CONSEQUENCES TO THE HEAL~
PLANT NAME: COOK UNIT 2 REVIEWER INITIAL:
XJM DISTRIBUTOR INITIAL:
+++++~+~++H%++~% DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4>++>+>+~+>>>+~~++
NOTES:
i.
SEND 3 COPIES OF ALL MATERIAL TO ICE ED REEVES-1 CY ALL MATERIAL PSAR/FSAR AMDT AND RELATED CORE POND-NCE (DISTRIBUTlON'CODE 8001)
FOR ACTION:
INTERNAL:
EXTERNAL:
ASST DIR D EISENHUT44I TR ONLY(1 P
,MLYNZAK++LTRONLY(i)
RE
+~LTR ONLY(i)
I 5 E+4LTR ONLYQ)
OPERATOR LIC BR>+LTR ONLY(i>
QAB++LTR ONLY(i)
MIPC++LTR ONLY(1>
MECH ENG BR++LTR ONLY(1)
MATERIAL ENG BR++LTR ONLY(2)
REACTOR SYSTEMS BR4~4LTR ONLY<1)
CORE PERFORMANCE BR++LTR ONLY(i AUXILIARYSYS BR+4~LTR ONLY< 1)
I 8.
C SYSTEMS BR+~LTR QNLY(i>
AD FOR SITE TECI.I4.+LTR ONLY<5)
ACCIDENT ANALYSIS~4ILTR QNLY(1 >
RAD ASSESSMENT BR+4LTR ONLY<i)
GEOSCIENCES BR+~LTR ONLY(1)
LPDR S ST.
- JOSEPH, MI<4~LTR ONLY( 1 )
TERA++LTR ONLY(i,)
NSIC++LTR ONLY<1)
ACRS CAT B~+LTR ONLY(16)
BR CHIEF ORB$ 1 BC+4LTR ONLY(i)
LIC ASST ORBN1 LA>>LTR ONLY(
NRC PDR+>LTR ONLY(1)
OELD~4LTR QNLY(i)
EMERGENCY PLAN BR>%LTR ONLY(i>
DIRECTOR NRR+%LTR ONLY< 1)
AD FOR ENG>>LTR ONLY(1>
STRUCTURAL ENG BR+<LTR ONLY< 1)
AD FOR REAC SFTY>+LTR ONLY(1)
ANALYSIS.BR44LTR,ONLY<i)
AD FOR PLANT SYSTEMS++LTR ONLY(i
,CONTAlNMENT SYSTEMS<<LTR ONLY< 1 POWER SYS BR++LTR ONLY(1>
AD FOR SITE ANLYS<~LTR ONLY< 1)
EFFLUENT TREAT SYS>4LTR ONLY(i>
KIRKWOOD++LTR ONLY(i)
DISTRIBUTION:
3P
%%%%%%8I%%%%%%%%%%%%%%%%%%%4%%%%%%%%
THE END CONTROL NBR:
7820900 8
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[NpIANA II MICHIGAN PowER CQMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 July 2'b, 1978 AEP:NRC:00058 Donald C.
Cook Nuclear Plant Unit No.
2 Docket No.
50-316 License No.
DPR-74 Environmental Qualification of Barton TransmitteIs i~1"
~
(,gal&'Q lC Mr. Harold R.
Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
I'lease be advised that the Westinghouse
'Corporation is transmitting the following docume under separate cover.
1)
Twenty-five (25) copies of two Westinghouse American Electric Power Service Corporation vironmental Qualification of Safety Related Instruments (Westinghouse Proprietary),
(1)
AEW-7156 a'nd (2)
AEW-7157 and Electric nts to you letters to on the En-Barton 2)
Forty (40) copies of the two Westinghouse letters to American Electric Power Service Corporation on En-vironmental Qualification of Safety Related Barton Instrument (Non-Proprietary),
(1)
AEW-7156 and (2)
AEW-7157 The above documents, submitted at the request of your staff, contai'n reports
'on the recent environmental qualification tests for the Barton Transmitters.
782090018
f r
4 I 4, 0
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4 k
~
I
Mr. Harold R.
Denton July 21, 1978 This letter authorizes the incorporation of the above documents under the docket number 50-316 for Unit No.
2 of the Donald C.
Cook Nuclear Plant.
Westinghouse Electric Corporation has advised us that they believe the information contained in the above documents does not constitute a safety question that could have adverse consequences with regard to the health and safety of the public for Donald C.
Cook Nuclear Plant Unit No.
2.
Their reasons for this determination are that, for automatic pro-tective function initiation, they have determined that the observed test results do not invalidate the safety analysis results for steam line breaks, feedline
- breaks, or loss of coolant accident analysis.
It is Westinghouse's judgement that the effects the transmitters experienced during sequential testing would not occur under concurrent radiation/
temperature conditions that would be present during postulated accidents.
However, in light of current lack of test data to substantiate this conclusion, Westinghouse has recommended (and we have accepted) certain remedial steps that the operator must take following a secondary side break.
These actions consist of temporary modification to the emergency operating procedures to instruct the operator to either confirm RCS pressure using an outside source or to wait a period of two hours following the break before proceeding with cooldown.
In light of the above, and having taken the appropriate actions recommended by Westinghouse, it is our view that the test results, reported in the above referenced documents, do not represent an unreviewed safety question that could result in operation in bounds not specified by the safety analysis, nor do they constitute a situation that could adversely affect the health and safety of the public.
uly
E, Disbx'ow Vice President Notary Public I~THQPgN g~~~
PUBuc, Stare 0] No~ y No. gI;g6p6g9~
audi pod
~ G.e.ns C
cc: (attached) c~ipc4fo m J p
y
~ p!
""> <I 3(ch 3Q, ]p~
Mr. Harold R, Dentin 3
July 2l, 1978 cc:
R.
C.
Ca 1 1 en P.
W. Steketee R.
Wal sh R. J. Vollen D.
V. Shal'ler-Bridgman R.
W. Jurgensen G. Charnoff
E