ML17053B979
| ML17053B979 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/17/1980 |
| From: | Bosnak R Office of Nuclear Reactor Regulation |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8010020013 | |
| Download: ML17053B979 (18) | |
Text
KMNTI'ftlKEHRKNP'l SEP 1 'V]g8O MEMORANDUM FOR:
Thomas A. Ippolito", Chief Operating Reactors Branch 82 Division of Licensing NRC PPR MEB Reading TERA NSIC FROM:
SUBJECT:
Robert J. Bosnak, Chief
,Mechanical Engineering Branch Division of Engineering NINE MILE POINT INSERVICE. TESTING PROGRAM Plant Name:
Ai 1
1 Point Nuclear Station Docket No.:
5 -220 Responsible B
8 Project Manager:
Phil Polk, ORB82 Review Branchs Involved:
Mechanical Engineering Branch Description of Task:
Review and Evaluate Nine Mile Point Inservice Testing Program Review Status:
Requesting Additional Information The Mechanical Engineering Branch, Division of Engineering, has reviewed the Nine Mile Point Inser vice Testing Program.
Additional information in response
. to the attached questions is essential to the completion of our review.
Please request the licensee to have the information available for a meeting.
From past experience we have found it necessary to arrange a meeting with tlie licensee at the plant to, review in detail their response and to seek answers to additional questions that inevitably develop from our evaluation of their responses.
To expedite our review, we request a meeting with Nine Mile Point on October 7 and 8,
1980 at the Nine Mile Point Nuclear Station.
Enclosure:
As stated cc:
R.'Yollmer J. Knight P.
Polk G. Johnson A. Hang V. Nerses F. Cherny R. Lyon, EG&G M. Rekito, IE, Reg. I H.
Brammer--
J.
Page Robert J. Bosnak, Chief Mechanical Engineering Branch Division of Engineering
Contact:
V. Nerses, DE:MEB X27468 80y 0 ~~
OFFICE P SURNAME QATE N DE'M' s.zlb..
9'SO
.K:.
.RB.as 9/J ak,.....
/80 NRC FORM 318 (9.76) NRCM 0240 0 U.S. GOVERNMENT PRINTING OFFICE: 1979-289-369
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ttUESTIONS ANO CENTS CONCERNING THE NIASARA MOHAN POWDER CQO'ANY IN-SERVICE TESTING PR06RAN FDR NiNE NILE POINT UNIT 1
(Ref:
l3ocket Nurser 50-220)
1
Valve Testl Pro A.
Gener a) st4ons and Coeaents i.
Provide the P4IO that shows the Control Rod Drive Hydraulic System.
2.
Provide the PCIO that shows the Drywell Cooling Systee.
3.
Ooes the F)re Protect)on Systea provide a back-up for any saf ety related systeii.
4.
Provide the PLIO that shows the Reactor Siiap)ing System.
5.
$ n instrument l)nes penetrating the drywell or torus oust be included
$n the IST progrca and cateoor ized AfC.
B.
Nain Stem Provide core specific technical information why valves 01-01, 01-%, 01-03, and 01-04 cannot be exercised during power operation or cold shutdown.
2.
Review the safety related functions of valves lS-108A tiirouph F to determine
$f they should be categorize~
8/C.
3.
Review the safety related function of valves 3'e-01 and 34-02 to deterifne
$f they should be categorized 'i and A/C respectively.
Prov)de the specific tech~.ical basis why these valves cannot be exercised dur f,y power operation or co)d shutdown.
4.
Review the safety related funct'on of valve 01-07 through' to determine
$f they should b< included
$n the 1ST program and categor)zed K.
0
C.
Feed<ate r 1.
Review th<: safety related function of valves 31-03 and 31-04 to determine if they should be categorized A.
Provide more specif ~c Information why these valves cannot be exercised durir g power operation and cold shutdown.
2.
M~.at is the safety ~elated function of check valves 31-01 md 022 D.
~Ri CI Review the safety related function of valves 33-01, 02, and 04 to determine if they should be cateqor ized h.
2.
Mhat is the safety related function of check valve 33-03?
K.
~Std C
Review the safety related function of valves 38-01, 02, and 13 and 3B-12 to determine if they should be categor ized A'nd A/C respectively.
Provide core specific technical inforaation why these valves cannot be exercised during power operation or cold shutdown.
F.
Eeer nc Condenser l.
Review the safety related function of valves 39-07, 08, 09, and 10 to determine if they should bi categorized A.
2.
provide core specific technical inforeation why valves 39-05 and 06 cannot be exercised during parer operation or cold shutd~.
Review the safety related functions of these valves to deteroine if they should be cateqorized h.
3.
Mhat is the specific technical basis for not stroke tieing category 8 valves 60-17 and 187 4.
Review the safety related functions of valves 39-03 and Oi to detereine if they should be categorized A/C.
Provide the specific technical basis why these valves cannot be exercised during power operation or co)d shutdown.
5.
lthat is the safety related function of valves 39-11 through 147 5.
Review the safety related function of the fol1owing valves to detereine if they should be inc1uded in the 1ST proqrae and categorized as indicated.
Cate r
B Cate r
05-01 ~ 02, 03, and 04 60-l3 BV60-03 and Oi 39-01 and 02 60.1-14, lS ~ 16, and l7 100-68 and 69 6.
C~S l.
Review the safety related functions of valves 81-01, 02, 21, and 22 to detereine if they should be cateqor ized A.
2.
hre cheek valves 81-07, 0&, 27, and 2&. full st~oke exercised quarterly 3,
Provide the specific technical basis why valves 40-03 and )8 cannot be exercised during power operation or cold shutdown.
4.
Review the safety related function of valves 40-05 and 06 to determine if they shou'ld be categor)zed A.
S.
Provide the specific technical basis why category 8 valves 93-51 and 52 are not stroke timed.
6.
Review the safety related function of valves 40-01, 02, Og, 10, 11 ~ and 12 to detere5ne if they should be categor ized A.
7.
Review the safety related functions of valves 81-31 and 11 to deteriline if they should be categorized A/C.
Oo these valves perform as a containant leak lieiting barrier2 8.
Rev)ew the safety related function of valve 58.1-01 to deteraine 1f it should be included in the IST progree md categor ized A.
H.
Containment S ra
~d Ra> Mater 1.
Review the safety related functions of valves 80-0l, 02, 21, ted 22 to deterline if they should be categorized A.
2.
Provide the specific techn(cal basks why valves 93-25, 26, D, 28, l9, and 50 are not stroke tieed.
3.
Provide Nore specific technical inforlation why check valves 80-05, 06, 25, and 26 cannot be full stroke exercised during power operation or cold shutdown.
4.
Provide more specific technical inforlation why check valves 80-D, 18, 37, 38, 19, 39, 66, 68, 65, and ST cannot be ful) stroke exercised during power operation or cold shutdown.
5.
Prov.ide core specific technical 5nforeation why check valves 93-09, 10, 11, and 12 cannot be full stroke exercised during power operation.
6.
Review the safety related functions of valves 80-15, 16, 35, and 36 to deterline if they should be categorized h.
7.
Rev)~ the safety related function of the fo1laein9 valves to determine
$f they should be included
$n the 1ST procp'ee and citator)zed as )ndicated.
Cat CS-C-4 Cat~eelE
.~ca E
80-11 ~ 12 ~ 31, and 32 bO-40. 41, 44 ~ and 45 93-21 ~ 22. 23, and 24
~Li fdP1 l.
Review the safety related functions of check valves 42.1-02 and 03 to detereine if they should be categorized A/C.
provide the specific technical bas)s
~hy these valves cannot be exerc)sed dur)ng power operation or cold shutd(wn.
2.
- Prov)de the specific technical basis Nhy check valves 42-19
<<nd 20 cannot be full stroke exercised
'during pmter operation.
3.
Nevis the safety related function of valves 42-01 and 02, and 41-06, 18, 12, and 13 to detere)ne if they should be included
$ n the 1ST prograe and categorized E.
J.
05ese)
Ra~ Mater Provide a P4)0 that shows the diesel ram ~ater system.
20 Provide the specific technical basis My check valves DG-CM-) ~ 2, 3, and i cannot be full stroke exercised dur ing
~r operation.
K.
Dr ll and Torus iso)ations Revim the safety related function of the fo)lying valves to detersfne if they should be included in the ISY program and categorized as indicated.
Cat r
A Cate or h/C 70-92 70-94 20).R-25 20).2-26 20).2-27 201.2-28
- 20).2-29 20).2-30 83.)-09 83.)-10 83.)-))
83.)-12 201-09 201-10 20)-3) 20)-32 20).2-03 20).2-32 20)-05 70-43 70-96 20).2-67 20).2-68 20).2-39 201.2-40 301-113 201.2-70 20).2-7)
S3.)-0) 63.)-02 Cate or C
68-0), 02, 03, and 04
~
~
F
'U P
~CI I(
tt d) 201-Ol 201-16 201-11 201.2-96 20).2-33 201 2-23 201.2-24 7E.
P Testi P
rm 1.
Provide the specific technical basis that Justifies quarterly puep testing instead of aonthly pmp testing as required by Section X1.
2.
Are the Core Spray wd Contaiaaent Spray Pueps subaer9ed pueps as indicated by Note 6T 3.
Core Spray Topping Puep suction pressure
{Pi) oust be oeasuref; using reference water level as
$ndicited by Note 2 does not apply-4.
Qhat alternate test methods have been considered to oeasMre vibration anplitude
{V) on the Containment Spray Raw Mater and Oiesel Net Mater Pueps?
S.
Her e'e inlet pressure (Pi} and flow {Q) Neasured for the Liquid Poison Plalet 5.
Mhere ch the QS W~m take a suction fnm?
Hoot is inlet pressure
{Pk) aeasured for the Oiesel Roc Mater Puepst 8.
Oo the Spent Fuel Pool Cceling Pueps have an emergency power supply?
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