ML20010J205

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Application to Amend Licenses DPR-71 & DPR-62 to Revise Tech Specs Reflecting TMI-related Mods Involving Installation of New Instruments for post-accident Drywell Pressure Monitoring Channels on Each Unit.Class I/Ii Amend Fees Encl
ML20010J205
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 09/24/1981
From: Utley E
CAROLINA POWER & LIGHT CO.
To: Ippolito T
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM NO-81-1561, NUDOCS 8109290703
Download: ML20010J205 (6)


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COAL Carolina Power & Light Company s egg h

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Po- U tr .~9 September 24, 1981 u,,, kl8eg7gg

%g File: NG-3514(B) Serial No.: NO-81-1561 Office of Nuclear Reactor Regulation ATTENTION: Mr. T. A. Ippolito, Chief Operating Reactors Branch No. 2 United States Nuclear Regulatory Commission Washington, D.C. 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. I AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 ADMINISTRATIVE TECHNICAL SPECIFICATION CHANGE REQUEST POST-ACCIDENT MONITORING INSTRUMENTATION

Dear Mr. Ippolito:

Summary of Request In accordance with the Code of Federal Regulations, Title 10, Section 50.90 and Section 2.101, Carolina Power & Light Company (CP&L) hereby requests revisions to the Technical Specifications for its Brunswick Steam Electric Plant (BSEP) Unit Nos. 1 and 2. These changes reflect TMI-related modifications which involve installation of new instruments for the post-r.ccident drywell pressure monitoring channels on each unit.

Discussion This modification is the result of TMI Item II.F.1-4. The new instrumentation to be installed is designed and qualified to more strict standards than the instruments presently installed. In addition, the range of the new instruments has been expanded in order to ensure that readings should always remain on-scale. Also, the instrument channels have been upgraded and will now meet new Class 1E separation requirements.

A 10CFR50.59 review of these changes has been performed and we have determined that the margin of safety is increased because of the expanded range and the improved channel separation. Also, there is no change in the basic function or operation of the new instrumentation. .

Therefore, the Technical Specification changes requested are merely to ht

$0 }\

411 Fayetteville Street

  • P. O. Box 1551
  • Raleigh, N. C. 27602 8109290703 810924D. c.m w l g)I)

PDR ADOCK 05000324 '

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revise the instrument tag numbers and are purely administrative in nature. Therefore, we enclose a check for $1,600.00 for one Class I amendment and one Class II amendment in accordance with 10CFR170.22.

The revised Technical Specification pages with the changes indicated by a vertical line in the right-hand margin are attached.

Schedule Brunswick plans to install the instruments on Unit No. 1 prior to its scheduled startup on September 25, 1981. The work should be com-pleted on Unit No. 2 before the end of 1981. We ask that these administra-tive Technical Specification changes be issued as soon as possible.

Then, since the instrument numbers in Technical Specifications would not match the actual instrument tag numbers for a certain period of time, we would request that this be considered as a temporary administrative inconsistency by I&E.

Please contact my staff should y.au have any questiens regarding this matter.

Yours very truly, 7(d A- Q

/V E. E. Utley Executive Vice President Powcr Supply and Engineering & Construction JAM /lr (8821)

Attachments cc: L. W. Garner (NRC I&E, Resident Inspector)

C. A. Julian (NRC I&E, Atlanta)

Sworn to and subscribed before me this 24th day of September, 1981.

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-  : g O T A ft y i e My commission expires:Oct. 4, 1981 5 i  : E Q \ pU B LIC l l hh'd'itkk

TAI *_I 3.3.5.3-1

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. L'"lY. NO.

OF 0?IELI'I DIS 1252C Dt! 7.S'IN"' AND 2:! '.L*Ih-' hDGIE CEANNEl_'

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1. Rea===r vessel Wa:er Level 2 (321-1.CS-NC26A,3; 321-LR-615; 121-LI-R60AA,3; 121-L -NO37 and 121-L M-NO37-1)
2. Rea ::: 7essel ? assure 2 (321-?!-1004A,3; C22-121-R608 a=d C22-F -N005A,5) .
3. Containment pressure 1.

(CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1 and CAC-PT-4175) 4 C ::ai---:: Temperature 2

(CAO ~"E-1255-1 thru 13,22,23,2/ and C91-?602)

5. Sup :ressi== Chr. :ser 1:=esphere Te=pera ture 2

(LC I-1253-17 th:2 20 and C71 ?602) .

6. Suppressi== C.n=ber *.ta:er 'ave.1 2 (CAC-L2-2601-3; CAC-LA-2602; CAC-1,0-2601; CAO-1 -2602 c=d CAO-LT-1601-1)
7. Suppressi=n Cha=Ser Wa:er 2e=serz: re ..

.2 (CAC I-1255-14, 21 a=d C91-?602) ,

E. C==:ai==e:: Radta:1.. 2 (CAO-AI-1260; CAC-AQE-1260-1,2,3; CAO-12-1261; CAC-AQE-1261-1,2,3; CAC-AR-1262 a=d CAC-AQE-1262-1,2,37 l -

9. C:::-# an: Oxyge: -

2 l (CAC-AT-1259-2; CAC-A2-1259; CAC-AT-1263-2 a=d l CAC-AR-1263)

10. Cen at==ie== Eydrogen 2 1 (CAC-AT-1959-1; CAC-AR-1259; CAC-AT-1263-1 and .

CAC-Al-1263).

11. Saf ety relief valve posizion indication: 1/V81"* '

Pri=ary - Sonic (B21-77-4157 through 4167 Secendary - Te p. (B21-TR-R614 points 1-11) i l

3EO;SVICK - U:in 1 3/. 3/51 l

l w _ _ , . . - _ .. _ . . _ - , - , . - _ _ _ , . ,,

TA n t.I 4_ 3. 3. 3-1

.' l'UST- ACCllENT !!O!!!ToltIllG lilSTillrllEt[rATitWl_ Sti!!VEII.I.AllCE Hi j guillt:llt;lliS

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3

.lHSTittitlEllr ANil lilSTRutlEliT lillfillElt CHAllflEI. I:llAtitlEI. .

y -

CitECK cal.I HitATInfi i va i

1. Reactor Vessel Water I.evel il

' It I, ( 117 l -l.lTS-1e026 A, 8: 821 -I.R-R615; D21 -l.1-R604 A , n g d H21-I.T-il031 and Il21-I.Til-fl031-1)' '

'l

.-- 2. Iteactor Vessel Prc: sure ll It 4

(1821-PI-H00/e A, n; C32-I.PL-R600 and C32-PT-11005A, n)

3. Containment pressure ' ~ ~ ~

il R (CAC-PI le176; CAC-PT-4176; CAC-PR-1257-1 and CAC-PT-4175) l

4. Containment Temperature 11 R (CAC-Tit-125'0-1 tiiru 13,22,23,24 and C91-P602) 48

's' 5. Suppression Clinminer Atenospliere Temperature il R

, (CAC-TR-125ft-11 thru 20 and C91-P602)

U 6 Suppression Clinmtier Water I.evel il R l

(CAC-l.I-2601-3; CAC-l.R-2602; CAC-I.T-260l; cat:-l.T-2602 and CAC-l.Y-2601.-1)

7. Supprension Clinmlier Wat er Temperature si R

) (CAC-TR-1250-14, 21 and C91-P602)

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! II . Con t ainement Radiation il n (CAC-AR-1260; CAC-AQll-1260-1,2,3; CAC-Alt-1261 ; CAC-AQll-1261-1,2,3;

. iAC AR-1262 and CAC-AQll-1262rl,2,3)

9. Con t a lisment Oxygen Concentration i il It i (CAC-AT-12'i9-2; CAC-AR-1259; CAC-AT-1263-2 anil rAC- All-1263)
  • l 10 Canit a lsime ut flyilrogen Concent rat loss il n (CAC- AT-1259-1 ; CAC-AR-1259; CAC-AT-1263-1 nuel CAC-Alt-1263) ll. ;afety rullef valve po::1I lon f inl i ca l. l on (l' rima ry '; nil c) H R (8/l-FY-415/ thru 416/)

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12. Sal et y ia lle f valve pn:al e inn i nit i ca l l ose (Secondary-Temperature) .M R i ( R 71- Th -Rfa l 4 po i n t*; I thru 11) '

.. TABLE 3.3.5.3-1 POST-ACCIDE:'T MONITORING I"STRU'4ENTATIO"

. MI"IMUM .NO.

OF OPERABLE e

T.v.eA..L,C_,u--.

I",i S ~1.",U". ._ r". .~. n.

m I"., S . ?. .L . ._r".s ...' '"u'.".r 9.

Cs.Ls u..".rt S

1. Reactor vessel water level 2 (321-LITS-NO26A,B; 321-LR-615; B21-LI-R604A,3 i

and 321-LITS-NO37)

2. Reactor vessel pressure 2 (321-?I-F.004A, 3; C22-L?R-R605 and C32-PT-N005A, 3)
3. Containment pressure .

2 (CAJ-PI-4176; CAC-PT-4176; CAC-PR-1257-1 and CAC-PT-4175)

4. Contain:en- Temperature 2

(CAC-TR-1258-1 thru 12, 22, 23, 24 cnd C91-P602)

5. Suppressica chanber at=csphere tenparature 2

.(CAC-TR-1258-17 thru 20 and C91-?602)

6. Suppression cht:ber water level 2 (CAC-II-2501-2; CAC-LA-2502; CAC-LT-2601; CAC-LT-2622 and CAC-LT-2ECl-1) 7 .' Suppressien ch::bar varer tenperature 2 (CAC-TR-1258-14, 21 and C91-?602)
6. Centain=ent radiatica 2 (CAC-AR-1260; CAC-AQH-1260-1, 2, 3; CAC-AR-1261; CAC-AQH-1261-1, 2, 3; CAC-AR-1252 and CAC-AQH-1262-1, 2, 3)
9. Contain=ent c:-:ygen 2 (CAC-AT-1259-2; CAC-AR-l'59; CAC-AT-1263-2 and CAC-AR-1263)

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l 10. Contein=en: hydrogen 2 1

I (CAC-AT-1959-1; CAC-AF.-1259; CAC-AT-1263-1 and L

CAC-AR-1263)

11. Safety relief valve positien indic::icn: 1/ valve r

Primary - Sonic (321-T*i ~157 thru 4167) r Secondary - Tenp. (321-!E-R614 points 1-11) f

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l l

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TAHI.R 4. 'l . 'i . 'l- 1. .

l'o!.r- ACCilil:llT linlliT01:1IIG lil!;Titlllli:llTATI8111 SilRVKIl.l.ATICE Hl:H!!I til:llEllTS ,

CilAllllEl, CilAlillEl.

Cill:CK CALillitATI0li IllSTHil?ll'.llT AllD IllSTitilllEllT lilllinER I

co 11 R

% 1. 'He act or vennel unter level

$ (ll21-1.1TS-!!O26A,II; il2 L-1.lt-It615; B21-LT-R604 A,n and n21-I.ITS-Il037)

N Reactor vessel pressure H R 2.

(ll21-PI-R004 A,B; C32-LPR-R608 and C32-PT-t1005A,H)

H R

3. Containment pressure (CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1 and CAC-?T-4175) l

~~

H- R

4. Contalsment (cmperature (CAC 'ti. -125fl-1 thru 13, 22, 23, 24 and C91-P602)

H R

5. Suppression chamber atmosphere temperature 1 (CAC-Tit-1258-17 thru 20 and C91-P602) s.a -

i} R T 6. Suppression chamber water Icvel (CAC-LI-2601-3; CAC-1,R-2602; CAC-LT-2601; CAC-LT-2602 and CAC-LY-2601-1)

T  !! R

M 7. Suppression chamber water temperature

" (CAC-Tit-1258-14, 21 and C91-P602)

H R

8. Containment radiation (CAC-AR-1260; C4C-AQll-1260-1,2,3; CAC-AR-1261; CAC-AQll-1261-1,2,3; CAC- AR-1262 nnd CAC-AQll-1262-1,2,3)

H R

9. Containment oxygen concentration ,

(CAC-AT-1259-2; CAC-AR-12S9; CAC-AT-1263-2 and CAC-AR-1263) i H R

10. Conf alument hyilror,cn concentrntion (CAC-AT-1259-1; CAC-4.R-1250; CAC-AT-1263-1 and CAC-AR-1263)

H R

11. Safety relicf vaIve ponition ind(cation (Primary-Son (c)

(ll71-IT- 4157 thru 4 L67)

R

12. Safety relief valve pnsition inillcatfun (Seconstary-Temperature) 11 (B21-TR-P614 points J thru 11)

.