L-87-145, Application for Amend to License NPF-16,updating Tech Specs to Make Minor Text Changes & to Correct Typos.Fee Paid

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Application for Amend to License NPF-16,updating Tech Specs to Make Minor Text Changes & to Correct Typos.Fee Paid
ML17219A492
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 03/31/1987
From: Woody C
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17219A493 List:
References
L-87-145, NUDOCS 8704070019
Download: ML17219A492 (28)
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Text

DOCKET 05000389 DISTRIBUTION CODE-A001D COPIES RECE'I YED: LTR

'NCL SIZE:

TITLE',:

OR Submittal; General Distr ibution NOTES!"

REGULATORY INFORMATION DISTRIBU1 N 'SYSTEM (RIDS)

A'GCFSS ION NBR ~ 8704070019" DOC ~ DATE q 87/03/31 NOTARIZED

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YES FACIL::50, 389 St', Lucia Plant~

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Fl or ida Power L Light Co ~

AUTH'NAME AUTHOR AFFILIATION NOODYgC,OS Florida Power L Light Co,

'RECIP ~ NAME~

RECIPIENT" AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT Applicat-ion for amend to License NPF-16'gupdating Tech Specs'.

to make minor text>> changes 8 to cor.rect'ypos,Fee-

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U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 L-87-I45 Gentlemen:

Re:

St. Lucie Unit 2 Docket No. 50-389 Proposed License Amendment Administative U date In accordance with IO CFR 50.90, Florida Power & Light Company (FPL) submits herewith a request to amend Appendix A of Facility Operating License NPF-I6.

This amendment is submitted to make administrative changes to the St. Lucie Unit 2 Technical Specifications to remove outdated material, make minor text

changes, and correct typographical errors.

Certain items identified in the staff s letter dated August 28, l986 (E. G. Tourigny to C. O. Woody) are 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.

A "Determination of No Significant Hazards Consideration" is provided as Attachment 3.

ln accordance with I 0 CFR 50.9 l(b)(l), a copy of the proposed amendment is being forwarded to the State Designee for the State of Florida.

In accordance with IO CFR l70, FPL Check No. 4537 is attached as remittance for the license amendment application fee.

The proposed amendment has been reviewed by the St. Lucie Facility Review Group and the Florida Power &Light Company Nuclear Review Board.

Please contact us if you have questions about this submittal.

V truly yours,

. O. Woody oup Vice President ea<<n<<gy

'704070019 S7033i-PDR ADOCK 05000389 COW/EJ'W/gp P,

PDR Attachment 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 EJW4/0 I2/ I an FPL Group company

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STATE OF FLORIDA

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COUNTY OF PALM BEACH )

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That he is Vice President of Nuclear 0 erations of Florida Power & Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made 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.

J. W. Di ey Subscribed and sworn to before me this 3g day of

'NOTAR,'(- PUBLlC, in and for the County of Palrsj Beach, State of Florida ROTARY PUBLIC STATE OF FLORIOA HY COHHISSIOH EXP SEPT 18,1989 BOHOEO THRU GEHERAL IHS.

OH'y Commission expires:

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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 2,

(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 REMARKS 3/4 1-1 3/4 1-2 3/4 1-3 3/4 1-5 3/4 1-8 3/4 1-10 3/4 1-12 3/4 1-14 3/4 3-25 3/4 3-26 3/4 3-34 3/4 3-39 3/4 3-53 3/4 3-57 3/4 4-27 3/4 4-38 Change 0 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 4 Delta-k/k to pcm Change

% Delta-k/k to pcm Change 4 Delta-k/k to pcm Remove outdated footnote*

Remove outdated footnote*

Correct surveillance periodicities Correct typographical error Correct typographical error Correct typographical errors Correct typographical errors*

Remove outdated footnote*

4

3/4 5-6 3/4 6-5 3/4 6-15 3/4 6-21 3/4 6-23 Correct typographical errors Remove outdated footnotes Correct typographical error Adds valve resulting from plant modification Remove outdated footnotes and correct valve number to reflect plant modification 3/4 7-4 3/4 7-3 9 3/4 8-,1 3/4 8-2 3/4 9-5 3/4 11-6 3/4 11-10 B 3/4 0-3 B 3/4 1-1 B 3/4 1-2 B 3/4 1-4 B 3/4 2-1 B 3/4 3-4 6-10 6-15 6-16 6-17 Remove outdated footnote*

Remove outdated footnote*

Correct typographical error Correct typographical error Remove outdated footnote*

Correct typographical errors Correct typographical error Correct typographical error Change 4 Delta-k/k to pcm Change 4 Delta-k/k to pcm Correct typographical error Correct typographical error Correct typographical error Update CNRB composition Remove outdated footnote*

Revise report addressee to change (10 CFR 50.4)

Revise report addressee to change (10 CFR 50.4) reflect rule reflect rule

6-20 6-23 Revise report addressees to reflect rule change (10 CFR 50.4)

Remove outdated Specifications 6.13.1 and 6.14.1*

G. Tourigny (NRC) to C.'.

Woody (FPL).

II I

ATTACHMENT 1 (Con't)

(2)

Descri tion of Pro osed Chan es SPECIFICATION PAGE DESCRIPTION 3.1.1.1 3/4 1-1 5.0% delta-k/k is changed to the equivalent 5000 pcm in two places.

4.1.1.1.1 3/4 1-1 5.0% delta-k/k is changed to the equivalent 5000 pcm in one place.

4.1.1.1.2 3/4 1-2 1.0% delta-k/k is changed to the equivalent 1000 pcm in one place.

3.1.1.2 3/4 1-3 3.0% delta-k/k is changed to the equivalent 3000 pcm in two places.

4.1.1.2 3/4 1-3 3.04 delta-k/k is changed to the equivalent 3000 pcm in one place.

3.1.1.4.a 3/4 1-5

+0.5 x

10 4

delta-k/k/degree-F is changed to the equivalent

+5 pcm/degree-F.

3. 1. l. 4.b 3/4 1-5

+0. 3 x

10 4

delta-k/k/degree-F is changed to the equivalent

+3 pcm/degree-F.

3.1.1.4.c 3/4 1-5

-2. 7 x

10 4

delta-k/k/degree-F is changed to the equivalent

-27 pcm/degree-F.

3 '.2.2 3/4 1-8 3.0< delta-k/k is changed to the equivalent 3000 pcm in one place.

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3. 1.2.4 3/4 1-10 3.04 delta-k/k is changed to the equivalent 3000 pcm in one place.-

3.1.2.6 3/4 1-12 3.04 delta-k/k is changed to the equivalent 3000 pcm in

.one place.

3.1.2.8 3/4 1-14 3.04 delta-k/k is changed to the equivalent 3000 pcm in one place.

Table 3.3-6 3/4 3-25 The fourth footnote at the bottom of this

page, which applies to the Containment Area (HI Range)

Radiation Monitoring Instrumentation, states that "monitors shall be completely installed and OPERABLE prior to exceeding 5%

of RATED THERMAL POWER."

As documented in FPL letter L-83-348, dated June 6,

1983, the monitors were installed and OPERABLE prior to exceeding 5w RATED THERMAL POWER; therefore, the footnote can -be deleted.

Table 3.3-6 3/4 3-26 The third footnote at the bottom of this

page, which applies to the Radiation Monitoring Instru-mentation Noble Gas Effluent Monitors for the Atmospheric Steam Dump Valve Discharge and the Reactor Auxiliary Building Exhaust System (Plant Vent High Range Monitor),

states that "monitors shall be completely installed and OPERABLE prior to exceeding 54 of RATED THERMAL POWER."

As documented in NRC Inspection Reports 50-389/83-25, dated April 6,

1983 and 50-389/83-59, dated September 27,

1983, the monitors were installed and OPERABLE prior to exceeding 5<

RATED THERMAL

POWER, therefore, the footnote can be deleted.

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Table 4.3-4 3/4 3-34 Peak shock recorders SMR-42-9 and SMR-42-10, located in St.

Lucie Unit 1, cannot be channel checked or have a

channel functional test performed.

As a result these surveillance periodicities are changed to NA.

This is consistent with the surveillance requirements for these identical instruments identified in the St. Lucie Unit 1 Technical Specification Table 4.3-4 and identified in the St.

Lucie Unit 2

Technical Specification Table 4.3-4 as

"(Instrumentation located in St.

Lucie Unit 1)".

Table 3.3-9 3/4 3-39 There is only one channel for the steam generator pressure instruments on the hot shutdown panel (PI-8113 and PI-8123).

Therefore, the "Required Number of Channels" column is corrected accordingly.

4.3.3.11 3/4 3-53 This Surveillance Requirement, corresponding to Limiting Condi-tion for Operation 3.3.3.10, is numbered incorrectly, It should be renumbered 4.3.3.10.

Table 4.3-9 3/4 3-57 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 4.3-9.

Table 4.4-4 3/4 4-27 Within Table 4.4-4, under Item 4.a in the "Sample and Analysis Frequency"

column, the notation for microcurie/gram is incor-ect.

In the fourth and sixth

lines, "mCi/gram" should be corrected to "micro-Ci/gram."

3.4.10 3/4 4-38 The footnote at the bottom of the page requires that "the Reactor Coolant System vents shall be completely installed and OPERABLE prior to exceeding 5% of RATED THERMAL POWER."

As documented in FPL letter L 348, dated June 6,

1983, the reactor coolant system vents were installed and OPERABLE prior to exceeding 5%

RATED THERMAL

POWER, therefore, the footnote can be deleted.

4.5.2.h.2 3/4 5-6 The prefix "HVC" for items "a" through "d" in the "HPSI System Valve Number" column should be corrected to "HCV."

Table 3.6-1 3/4 6-5 The footnotes at the bottom of.

this page no longer apply.

The modification described in FPL letter

'-84-266, dated September 28,

1984, has been completed as reported in FPL letter L-87-112, dated March 13, 1987.

Valve tag number/type is corrected accordingly.

4.6.2.1.c.2 3/4 6-15 A

typographical error is corrected.

The word "on" is changed to "an."

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Table 3.6-2 3/4 6-2 1 Containment isolation valve I-HCV-18-2 is added to "Section A) Containment Isolation".

The modification described in FPL letter L-84-266, dated September 28,

1984, and reflected in the footnotes on page 3/4 6-23, has been completed as reported in FPL letter L-87-112, dated March 13/

1987.

Table 3.6-2 3/4 6-23 The footnotes at the bottom of-this page no longer apply.

The modification described in FPL letter L-84-266, dated September 28,

1984, has been completed as reported in FPL letter L-87-112, dated March 13, 1987.

3.7. l. 2 3/4 7-4 The footnote at the bottom of this page states that "the Auxiliary Feedwater System automatic initiation system shall be completely installed and OPERABLE prior to initial criticality."

As documented in NRC Inspection Report 50-389/83-47, dated July 28,

1983, the subject system was installed and OPERABLE as required; therefore, the footnote can be deleted.

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3.7.12 The footnote at the bottom of this page states that "all fire rated assemblies shall be completely installed and OPER-ABLE prior to exceeding 54 of RATED THERMAL

POWER, with the exception of the permanent flame impingement shields in contain-ment which shall be completely installed and OPERABLE prior to STARTUP following the first refueling outage."

As docu-mented in FPL letter L-84-333, dated November 20,

1984, the fire rated assemblies and flame impingement shields were installed and OPERABLE as required; therefore, the footnote can be deleted.

3.8.1. 1 A

typographical error is corrected.

The word "a"

in Action c.2. is changed to "in."

3.8.1.1 A

typographical error is corrected.

A comma is inserted in the second sentence of Action cd 2

'.9.5 The footnote at the bottom of this page states that "the sound powered telephone system shall be completely installed and OPERABLE prior to exceeding 5%

of RATED THERMAL POWER."

As documented in NRC Inspection Report 50-389/83-47, dated July 28, 1983, the subject system was installed and OPERABLE as required; therefore, the footnote can be deleted.

9

3.11.1.3 3/4 11-6 Three typographical errors are corrected.

These three typos were made during NRC's retype of this ACTION Statement to delete the Tech Spec 6.9.1 reporting requirements.

Table 4.11-2 3/4 11-10 A

typographical error is corrected.

In Table Notation c, the word "or" is changed to Il of II B4.0.5 B 3/4 0-3 A

typographical error in the word "throughout" is corrected.

B3/4.1.1.1 B3/4. 1. 1. 2 B 3/4 1-1 54 delta-k/k is change to the equivalent 5000 pcm in two places in the BASES section on SHUTDOWN MARGIN.

B3/4.1.2 B 3/4 1-2 3% delta-k/k is changed to the equivalent 3000 pcm in two places in the BASES section on BORATION SYSTEMS.

B3/4.1.3 B 3/4 1-4 A

typographical error is corrected; the word "to" is changed to "for."

B3/4. 2. 2, B3/4.2.3 3/4.2.4 B 3/4 2-1 A

typographical error

. in the word "AZIMUTHAL"is corrected.

B3/4.3.3.10 B 3/4 3-4 A

typographical error in the word "GASEOUS" is corrected.

6.5.2.2 6-10 The CNRB composition is expanded from eight to ten

members, and the list of'titles.is revised to reflect the current organiza-tion.

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6.8.4.e The footnote at the bottom of this page states that "the post-accident sampling system (PASS) shall be completely installed and OPERABLE prior to initial criticality."

As documented in FPL L-84-333, dated November 20, 1984, the Post Accident Sampling System was installed and OPERABLE, as required; therefore, the footnote can be deleted.

6.9.1 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 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. 1.9 6-20 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. 10 6-20 The text is revised to reflect a recent change to 10 CFR 50.4 on procedures for communicating with the NRC Staff (51FR40303).

6.9.2 6-20 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 Specification 6.13.1 be deleted and the subsequent sections be renumbered 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 28, 1983 by letter from G.

W.

Knighton (NRC) to R.

E.

Uhrig (FPL).

Therefore, it is pro-posed that Specification 6.14.1 be deleted and the subsequent sections be renumbered accord-ingly.

ATTACHMENT I (con't)

(3) Marked-U Technical S ecifications Pa es 3/4 I-I 3/4 I-2 3/4 l-3 3/4 I-5 3/4 I-8 3/4 I-IO 3/4 I-I2 3/4 l-l4 3/4 3-25 3/4 3-26 3/4 3-34 3/4 3-39 3/4 3-53 3/4 3-57 3/4 4-27 3/4 4-38 3/4 5-6 3/4 6-5 3/4 6-I5 3/4 6-2I 3/4 6-23 3/4 7-4 3/4 7-39 3/4 8-I 3/4 8-2 3/4 9-5 3/4 I I-6 3/4 I I-IO B 3/4 0-3 B 3/4 I-I B 3/4 I-2 B 3/4 I-4 B 3/4 2-I B 3/4 3-4 6-I 0 6-I 0 (proposed insert) 6-I 5 6-I 6 6-I7 6-20 6-23

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