ML18004A455
| ML18004A455 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/08/1986 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.068, RTR-REGGD-1.068 4045JDK, NLS-86-301, NUDOCS 8608140280 | |
| Download: ML18004A455 (6) | |
Text
b REQUL RY INFORMATION DISTRIBUTI SYSTEM (RlDS)
ACCESSION NBR: 8608140280 DOC. DATE: 86/08/08 NOTARIZED:
NG DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant>
Unit 1> Carolina 05000400 AUTH. NANE AUTHOR AFFILIATION ZINNERI'fAN>S. R.
Carolina Power 8c Light Co.
RECIP. NANE RECIPIENT AFFILIATIGiV DENTGN> H. R.
Office of Nuclear Reactor Regulation.
Director (post 851125
SUBJECT:
Responds to NRC 8b0709 concerns re Amends 26 8c 27 to FSAR.
Pressurized safetg valves will be exempted from RCS relief valve testing per Reg Guide
- 1. 68(App A> Item i. 9(2) ( i) ).
I 1
DISTRIBUTION CQDE:
DQOID CQPIEB RECEIVED: LTR g ENCL /
BIIE:
~ TITLE: Licensing Submittal:
PSAR/FSAR Amdts 5 Related Correspondence NOTES: Application for permit renewal +i led.
05000400 REC IP IENT ID CODE/NANE PWR-A EB PWR-A FGB PWR-A PD2 PD PWR-A PSB COPIES LTTR ENCL 1
1 1
1 RECIPIENT ID CODE/NAl'IE PWR-A EICSB PWR-A PD2 LA BUCKLEY>B 01 PWR-A RSB COPIES LTTR ENCL 1
2 2
1 INTERNAL: ADN/LFI1B IE FILE IE/DGAVT/GAB 21 NRR PWR-B ADTS NRR/DHFT/NTB RQN2 EXTERNAL: BNL(ANDTS ONLY)
LPDR 03 NSIC 05 0
ELD/HDS1 1
IE/DEPER/EPB 36 1
NIB 1
1 DNB/DSS
( ANDTS) 1 1
NRC PDR 02 1
1 PNL QRUEL> R 0
0 1
'0 1
1 1
TOTAL NUj'}BER OF COPIES REQUIRED:
LTTR 30 ENCL 25
I
<<" f )3)
<4
f
"'f'f I
), jrt f',P1) fj 4
I,'J hr )
I'f g) 'gf,,f I r, f
r h, fh I
h l I.r 'r
'~O f "l. )8 II
'Fjtt f I
ttf h
II ff
'hl Ir fy IC l I v I
I rP
-r 1
~
.'ft f
".',< S L <<'ff(f:'(>>'~
ff 'th i 1r; lk '" c..t.fV Jt t.10.l:lt~~ E fff..
h I'h f 1
~~r. Wtftq q 1 ~ qw, l'"f
- l rf )vtff ~
",.(i":.f,"T:.":".3R j I;.)&;'
th f
', j ',j'l',f'1jf fr,,
fffr}'
rr
">f'6 49f L j sSV.'
f 1.f"',~al
%jf II f,l
- <<gj w't AQ
~(
1 I
l
'h JJ jt'f'h~
~ qf r
(ir,") '
I
('~$ t<~
f Htr l),
r Il I
I'h Q
II+
)
r Iij PI" ',I J;" M$
'I it',9 ftt]
Jttrt I'l G
I
'I I lf
\\I'
'I f' I'"
'II fill
- )Ff/j Il'I' Ih I
trh
~ 1 I trf rl ~
SR%
Carolina Power 8 Light Company SERIAL: NLS-36-30 I AUG 0 8 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. l - DOCKET NO.50-000 INITIALTEST PROGRAM
Dear Mr. Denton:
Carolina Power R Light Company (CPRL) hereby provides response to concerns identified by the NRC staff on 3uly 9, l936 regarding Amendments 26 and 27 to the Shearon Harris Nuclear Power Plant (SHNPP) Final Safety Analysis Report (FSAR). The attached information is submitted to provide further clarifications concerning the SHNPP Initial Test Program.
Necessary changes to the FSAR willbe formally submitted via a post-fuel load amendment.
If you have any questions, please contact me.
Yours very truly, GB/vaw (00053DK)
Attachment cc:
Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. 3. Nelson Grace (NRC-RII)
Wake County Public Library it/4JSSAkt~
. R im erman ger Nuclear Licensing Section
" 8608140280 860808 PDR ADOCK 05000000 P
PDR o<L 411 Fayettevllte Street
~ P. O. Box 1551
~ Raleigh, H. C. 27602
ATTACHMENT NRC Concern:
Amendment 27 included an exception to Regulatory Guide 1.68 (Appendix A, Item 5.i) with insufficient technical justification for not testing the ability of incore nuclear instrumentation to detect a control rod misalignment equal to or less than the Technical Specification requirements.
This exception should be taken only if sufficient technical justification can be provided.
CPRL Response:
This issue was discussed with the NRC in a telecon on 3uly 31, 1986.
In this discussion, CPRL described the method which willbe used to identify the location of a control rod using the movable incore neutron flux detectors system.
The method has been validated using incore maps from other V/estinghouse facilities and is incorporated into the applicable Technical Specification surveillance test procedure.
To address the NRC concern and clarify the exception to Regulatory Guide 1.68, CPRL willimplement the test procedure during the power ascension test program and revise the FSAR to indicate this commitment.
The surveillance test will be implemented at the 50 percent power plateau.
The purpose of the exercise willbe to determine the position of a Control Bank D control rod using the movable incore flux detector system and comparing the result with the position determined from the bank step counter.
The method willbe found acceptable if it can determine the position of the control rod within the tolerance accepted by Technical Specifications (within 12 steps of the bank step position).
NRC Concern:
FSAR Subsection 10.2.12.1.57 (Containment Ventilation Test Summary) should be modified to reinstate testing of the containment recirculation fans during the containment integrated leak or the response to NRC Question 600.5 (Subitem i.h.9) and FSAR Subsection 10.2.7 should be modified to provide technical justification for an exception to Regulatory Guide 1.68 (Appendix A, Item I.h.9).
CPRL Response:
The item in Regulatory Guide 1.68 specifies that:
Testing should include demonstration that fans can operate in accordance with design requirements at the containment design peak accident pressure.
To address this item, the response to NRC Question 600.5.1.h(9) included the following commitment:
Containment recirculation fans willbe operated during the containment integrated leak rate test (ILRT) and motor current monitored.
Determining fan operability during LOCA conditions willbe accomplished by correlating data taken during the containment ILRT to LOCA conditions:
The test summary for ILRT (FSAR Section 10.2.12.142) contained this commitment, but it was deleted because inclusion of the statement in the test summary implied (4045 JDK/vaw )
that failure of a fan during ILRT would require suspension of the ILRT in order to repair a failed fan. The fans were run during the pressurization of the containment for the containment's Structural Integrity Test (SIT) which pressurized the containment to 51 psig.
The ILRT was subsequently run at the required pressure of Ol, psig. The data collected during fan operation has been correlated to LOCA conditions and the results were in accordance with design requirements.
With this clarification to our commitment in response to 600.5, no changes to the FSAR are considered necessary.
Based on discussion of this information with the NRC in a telecon on 3uly 31, 1986, CPRL considers this matter closed.
NRC Concern:
Amendment 27 includes an exception to Regulatory Guide 1.68, Appendix A, Item l.a(2)(i), regarding "Reactor Coolant System Relief Valve" testing.
Reference to these valves is unclear:
the valves of concern are actually the pressurizer safety valves.
This exception is acceptable pending reference to the correct valves.
CPRL Response:
The valves subject to the exception are the Pressurizer Safety Valves.
The FSAR willbe revised to clarify this point. CPRL understands that pending this revision, this matter willbe closed.
(4045 JDK/vaw
)