L-87-121, Application for Amend to License DPR-67,changing Tech Specs to Remove Outdated Matl,Make Minor Text Changes & Correct Typos.Tech Specs,Safety Evaluation & NSHC Determination Encl.Fee Paid
| ML17219A451 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/17/1987 |
| From: | Woody C FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17219A452 | List: |
| References | |
| L-87-121, NUDOCS 8703250094 | |
| Download: ML17219A451 (13) | |
Text
RECUL*TORYlFORNATION DISTRIBUTION SYN (RIDE)
ACCESSION NBR: 8703250094 DOC. DATE: 87/03/17 NOTARIZED:
NO FACIL 50 335 St.
Lucie Plant>
Unit 1I Florida Power 8c Light Co.
AUTH. NAME AUTHOR AFFILIATION NOODYi C. O.
Florida Power 5 Light Co.
RECIP. NANE RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUB JECT: 'Application for amend to License DPR-67'emoving outdated mat)i making minor text changes 0 correcting, typographical errors. Tech Specsi safety evaluation 5 NSHC determination encl. Fee pai d.
DISTRIBUTION CODE:
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TITLE:
OR Submittal:
General Distribution NOTES:
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P. O. B~OOO, JUNO BEACH, FL 33408-0420 y$
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S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 MARCH 17 1987 L I 2 I Gentlemen:
Re:
St. Lucie Unit I Docket No. 50-335 Proposed License Amendment Administrative U date In accordance with IO CFR 50.90, Florida Power 8 Light Company (FPL) submits herewith a request to amend Appendix A of Facility Operating License DPR-67.
This amendment is submitted to make administrative changes to the St. Lucie Unit I Technical Specifications to remove outdated material, make minor text
- changes, and correct typographical errors.
Items identified in the NRC Staff's letter dated August 28, l986 (E. G. Tourigny to C. O. Woody) are also included in this submittal.
Attachment I
to this letter includes the proposed Technical Specification changes.
Attachment 2
is the Safety Evaluation in support of the proposed amendment.
Attachment 3
is a "Determination of No Significant Hazards Consideration".
The proposed amendment has been reviewed by the St. Lucie Facility Review Group and the Florida Power &Light Company Nuclear Review Board.
In accordance with IO CFR 50.92(b)(l), a copy of the proposed amendment is being forwarded to the State Designee for the State of Florida.
ln accordance with IO CFR l70, FPL Check No. 3980 is attached as remittance for the license amendment application fee.
Please contact us if you have questions about this submittal.
Very truly yours,
. Woody Group Vice esident Nuclear En rgy COW/EJW/gp Attachments cc:
Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC USNRC Senior Resident Inspector, St. Lucie Plant Mr. Lyle Jerrett, Florida Dept. of Health and Rehabilitative Services 8703250094
- 870317, PDR ADQCK 05000335 EJW4/022/I F'" "
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STATE OFFLORlDA)
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COUNTY OF PALM BEACH)
~C.O.Wdb*i i
d That he is aGrou Vice President of Florida Power&Light Company, the Licensee herein; That he has executed the foregoing document; that thestatementsmade in this document are true and correct to the best of his knowledge, information,and belief,and that he is authorized to execute the document on behalf of said Licensee.
C. O. Woody Subscribed and sworn to before me this lP day of 1 9 $ 7.
NOTAR'(PUBLIC, in and for the County of Palm'Beach,State of Florida 4
<~P, ~ m ROTARY PUBLIC STATE OF FLORIOA
'a HYCOHHISSIOHEXPSEPT18,1989 My Comm 1$ $jon expiI es BQHDEo THRU GEHERAL IHB. UHD
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ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGES This Attachment includes (1) a summary listing of revised Technical Specification pages for St.
Lucie Unit 1,
(2) a description of the proposed
- changes, and (3) marked up Technical Specification pages.
(1)
Summar Listin of Revised Technical S ecification Pa es PAGE 3/4 1-1 3/4 1-2 3/4 1-3 3/4 1-5 3/4 1-10 3/4 1-18 3/4 3-25 3/4 3-54 3/4 4-58 3/4 7-8 3/4 7-10 3/4 7-11 3/4 7-12 B 3/4 1-1 B 3/4 1-2 B 3/4 7-3 REMARKS Change
% Delta-k/k to pcm Change
% Delta-k/k to pcm Change 4 Delta-k/k to pcm Change Delta-k/k/ F to pcm/
F Change
% Delta-k/k to pcm Change
% Delta-k/k to pcm Remove outdated footnote*
Correct typographical error Remove outdated 'footnote*
Correct typographical error Remove outdated (and redundant) requirements*
Remove outdated (and redundant) requirements*
Remove outdated (and redundant) requirements*
Change
% Delta-k/k to pcm Change
% Delta-k/k to pcm Remove outdated (and redundant) requirements*
6-9 6-15 6-16 Update CNRB composition Revise report addressee to reflect rule change (10 CFR 50.4)
Revise report addressee to reflect rule change (10 CFR 50.4) 6-19 Revise report addressees to reflect rule change (10 CFR 50.4) 6-23 Remove outdated Specifications 6.13.1 and 6.14.1*
- Changes recommended in letter dated August 28, 1986 from E.
G. Tourigny (NRC) to C.
O.
Woody (FPL).
(2)
Descri tion of Pro osed Chan e
SPECIFICATION 3.1.1.1 PAGE 3/4 1-1 DESCRIPTION 3
~ 6 o delta-k/k is changed to the equivalent 3600 pcm in two places.
4 ~ 1 ~ 1 ~ 1.1 3/4 1-1 3.64 delta-k/k is changed to the equivalent 3600 pcm in one place.
4 gal.1.2 3/4 1-2 1.04 delta-k/k is changed to the equivalent 1000 pcm in one place.
3
~ 1 ~ 1.2 3/4 1-3 2.0$ delta-k/k is changed to the equivalent 2000 pcm in one place.
3.1
~ 1'.a 3/4 1-5
+0. 7 x
10 4
delta-k/k/degree-F is changed to the equivalent
+7 pcm/degree-F.
3
~ 1. l. 4.b 3/4 1-5
+0. 2 x
10 4
delta-k/k/degree-F is changed to the equivalent
+2 pcm/degree-F.
3.1.1.4.c 3/4 1-5
-2. 8 x
10 4
delta-k/k/degree-F is changed to the equivalent
-28 pcm/degree-F.
3 '
~ 2 '
3/4 1-10 2.0% delta-k/k is changed to the equivalent 2000 pcm in one place.
3.1.2.8 3/4 1-18 2.04 delta-k/k is changed to the equivalent 2000 pcm in one place.
3 ' '.2 3/4 3-25 The footnote at the bottom of the page specifies incore detector operability require-ments that expired October 1,
1981.
Table 4.3-9 3/4 3-54 The "CHANNEL CALIBRATION" column for Item 2,
Waste Gas Decay Tanks Explosive Gas Monitoring
- System, should refer to Note(4);
there is no Note(5) to Table 4 '-9.
3 '.12 3/4 4-58 The footnote at the bottom of the page specifies certain valve closure requirements that ex-pired October 1,
1981.
Table 4.7-2 3/4 7-8 A
typographical error is corrected in Item 2.a.
The word "indicates" is misspelled.
3/4 '.1.6 3/4 7-10 through 3/4 7-12 Specifications 3/4.7.1.6 apply to secondary water chemistry,
- however, secondary chemistry is under administr'ative control by way of Specification 6.8.4c on pages 6-14 and 6-15.
Therefore, since Specifications 3/4.7.1.6 and their respective Tables 3.7-3 and 4.7-3 are outdated and redundant, their removal is recommended.
B 3/4
~ 1. 1 ~ 1 B 3/4
~ 1 ~ 1.2 B 3/4 1-1 In the second paragraph, four values of delta-k/k (3. 64, 24, 24, and 1%)
are changed to the equivalent pcm values (3600,
- 2000, 2000, and 1000) in the BASES section for SHUTDOWN MARGIN.
B 3/4 '.1.4 B 3/4 1-1 Three delta-k/k/degree-F values'+0.7 x 10 4, +0.2 x 10 4, and
-2.8 x 10 4) are changed to the equivalent pcm/degree-F values
(+7,
+2, and
-28) in the BASES section for MODERATOR TEMPERA-TURE COEFFICIENT.
B3/4.1.2 B 3/4 1-2 2.0$ delta-k/k is changed to the equivalent 2000 pcm in one place in the BASES section for BORA-TION SYSTEMS.
B 3/4.7.1.6 B 3/4 7-3 Secondary chemistry is under administrative control by way of Specification 6.8.4c, therefore, it is recommended that the BASES section for SECONDARY WATER CHEMISTRY be deleted.
6.5.2.2 6-9 The CNRB composition is expanded from eight to ten
- members, and the list of titles is revised to reflect the current organiza-tion.
6.9.1 6-15 The text is revised to reflect a
recent change to 10 CFR 50.4 on procedures for communicating with the NRC Staff (51FR40303) 6 ~ 9. 1.6 6-16 The text is rev'ised to reflect a
recent change to 10 CFR 50.4 on procedures for communicating with the NRC Staff (51FR40303).
6.9.1.9, 6.9.1.10, and 6 '
6-19 The text is revised to reflect a recent change to 10 CFR 50.4 on procedures for communicating with the NRC Staff (51FR40303).
- 6. 13. 1 6-23 This Specification applies to the Process Control Program (PCP) and states that "the PCP shall be approved by the Commission prior to implementa-tion."
The Commission approved the PCP on May 10,"
1983 by letter from G.
W. Knighton (NRC) to R.
E.
Uhrig (FPL).
There-fore, it is proposed that Speci-fication 6.13.1 be deleted and the subsequent sections be re-numbered accordingly.
6-23 This Specification applies to the Offsite Dose Calculation Manual (ODCM) and states that "the ODCM shall be approved by the Commission prior to imple-mentation."
The Commission approved the ODCM on July 28I 1983 by letter"from G.
W. Knigh-ton (NRC) to R.
E. Uhrig (FPL).
Therefore, it is proposed that Specification 6.14.1 be deleted and the subsequent sections be renumbered accordingly.
(3)
Marked-u Technical S ecification Pa es 3/4 1-1 3/4 1-2 3/4 1-3 3/4 1-5 3/4 1-10 3/4 1-18 3/4 3-25 3/4 3-54 3/4 4-58 3/4 7-8 3/4 7-10 3/4 7-11 3/4 7-12 B3/4 1-1 B3/4 1-2 B3/4 7-3 6-9 (plus insert) 6-15 6-16 6-19 6-23