AECM-86-0243, Application for Amend to License NPF-29,modifying License Condition 2.C(33)(b) Requiring Util to Conduct Simulated Loss of Onsite & Offsite Alternating Current Power Test

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Application for Amend to License NPF-29,modifying License Condition 2.C(33)(b) Requiring Util to Conduct Simulated Loss of Onsite & Offsite Alternating Current Power Test
ML20205F654
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 08/11/1986
From: Kingsley O
MISSISSIPPI POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
AECM-86-0243, AECM-86-243, TAC-61196, NUDOCS 8608190278
Download: ML20205F654 (7)


Text

..

MISSISSIPPI POWER & LIGHT COMPANY

] Helping Build Mississippi P. O. B O X 1640, J A C K S O N, MIS SIS SIP PI 39215-1640 August 11, 1986 O. D. KINGSLEY, J R.

VICE PRESIDENT NUCLEAR OPERATIONS U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Mr. Harold R. Denton, Director

Dear Mr. Denton:

SUBJECT:

Grand Gulf Nuclear Station Unit 1 i Docket No. 50-416 License No. NPF-29 File: 0260/0840/L-860.0 Proposed Amendment to the Operating License (PCOL-86/18)

Supplement AECM-86/0243 Mississippi Power & Light (MP&L) made a submittal, AECM-86/0198, dated July 25, 1986, requesting an amendment to Facility Operating License No. NPF-29 for Grand Gulf Nuclear Station (GGNS) Unit 1. The proposed amendment modifies License Condition 2.C.(33)(b) requiring that MP&L conduct a simulated loss of onsite and offsite alternating current power test.

Based on conversations with the staff, MP&L wishes to supplement AECM-86/0198 to revise the New License Condition as follows:

Prior to restart following the first refueling outage, MP&L shall complete the additional training and testing related to TMI Action Plan I.G.I as described in Section 2.3 of the MP&L submittal dated April 3, 1986.

This change provides a more specific requirement than originally proposed but has no affect on the technical content of the earlier submittal.

For the convenience of the staff the entire submittal is enclosed with the above change incorporated. The remainder of the submittal is unchanged.

In accordance with the provisions of 10 CFR 50.30, three (3) signed originals and forty (40) copies of the requested amendment are enclosed. The attachment provides the complete technical justification and discussion to support the requested amendment. The technical content and safety concerns associated with this proposed amendment were reviewed and accepted by the Plant Safety Review Committee (PSRC) and the Safety Review Committee (SRC) at the time of the original submittal.

8008190278 860725 DR ADOCKOSOOg6 J12AECM86073102 - 1 i i Member Middle South Utilities System l

AECM-86/0243 Pags 2 Based on the guidelines presented in 10 CFR 50.92, it is the opinion of MP8L that this proposed amendment involves no significant hazards considerations.

Yours ly, ODK:rg '\'

Attachments: GGNS PCOL-86/18 cc: Mr. T. H. Cloninger (w/a)

Mr. R. B. McGehee (w/a)

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o)

Mr. R. C. Butcher (w/a)

Mr. James M. Taylor, Director (w/a)

Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Dr. J. Nelson Grace, Regional Administrator (w/a)

U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W., Suite 2900 Atlanta, Georgia 30323 Dr. Alton B. Cobb (w/a)

State Health Officer State Board of Health Box 1700 Jackson, Mississippi 39205 J12AECM86073102 - 2

BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-29 i

DOCKET NO. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY and MIDDLE SOUTH ENERGY, INC.

and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION AFFIRMATION I, O. D. Kingsley, Jr., being duly sworn, stated that I am Vice President, Nuclear Operations of Mississippi Power & Light Company; that on behalf of Mississippi Power & Light Company, Middle South Energy, Inc., and South Mississippi Electric Power Association I am authorized by Mississippi Power & Light Company to sign and file with the Nuclear Regulatory Commission, this application for amendment of the Operating License of the Grand Gulf Nuclear Station; that I signed this application as Vice President, Nuclear l,

Operations of Mississippi Power & Light Company; and that the statements madc and the matters set forth therein are true and correct to th best of my knowledge, information and belief.

.t

'T). M Kings 1 .

STATE OF MISSISSIPPI COUNTY OF HINDS SUBSCRIBED AND SWORN T0 befog me, a Not y Public, in and for the County and State above named, this //Nday of _

, , 1986.

I (SEAL) i

.AlaNotary.Public a0 W My commission expires:

hg Commissi:n Dphes Se? II 1937 J12AECM86073102 - 4

, , - . , , ----....---.m -- ,_ ,

1) OLCR NLS-86/02

SUBJECT:

Facility ConditionOperating (License No. NPF-29, page 11 License 2.C.(33)b)

DISCUSSION: Mississippi Power & Light Company (MP&L) wishes to amend the Grand Gulf Nuclear Station (GGNS) Operating License replacing License Condition 2.C.(33)(b):

MP&L shall conduct a special test, Simulated Loss of Onsite and Offsite Alternating-Current Power Test, as described in the MP&L letter dated August 18, 1981. At least 4 weeks prior to per-forming the Special Test, MP&L shall provide a safety analysis for this test and its procedures to NRC for review and approval.

with the following:

Prior to restart following the first refueling outage, MP&L shall complete the additional training and testing related to TMI Action Plan'I.G.1 as described in Section 2.3 of the MP&L~ submittal dated April 3, 1986.

JUSTIFICATION: The requirement for performing an SB0 test originated from TMI Action Plan Item I.G.1, " Training During Low Power Testing." This Action Plan item, as presented in NUREG 0694, requested that applicants, "... define 'and commit to a special low-power testing program approved by NRC to be conducted at power levels no greater than 5 percent for the purposes of providing meaningful technical information beyond that obtained in the normal startup test program and to provide supplemental training."

In a January 27, 1981 letter from the NRC, Mississippi Power & Light was requested to commit to performing an SB0 test as part of TMI Item I.G.I.

MP&L committed to perform a Low-Power Test Training Program to be developed using the guidelines provided in the report "BWR Owners' Group Program for Compliance with NUREG 0737, Item I.G.1 Training During Low Power Testing" and also -

committed to perform a Station Blackout test.

The Grand Gulf Facility Operating License, NPF-29, consequently contained licensing condition 2.C.(33)(b) which required MP&L to conduct a simulated SB0 test.

J13ATTC86062701 - 1

b In NRC Generic' Letter 83-24, the NRC modified their  !

position on SB0 testing by stating "..if it can be demonstrated that temperature and/or other SB0 test ,

, conditions would adversely impact and pose a hazard to  !

plant equipment, the BWR Uwners' Group recommendations by

, themselves would constitute compliance with Item '

I.G.1...." MP&L submittec' a Station Blackout report, transmitted by letter AECM-86/0042 dated April 3, 1986.

Section 2.0 of this report provides justification for not performing the SB0 test. This report shows that GGNS can

, withstand an SB0 for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> given no additional failures and points out the detrimental effect to plant components if SB0 testing were allowed to progress to the point where temperature (xceeds normal limits.

SIGNIFICANT HAZARDS CONSIDERATION: ,

1. MP&L has determined that no significant increase in probability or consequences of an accident previously evaluated exists due to this change. This
change-will not result in changes to hardware or operating
procedures at GGNS. The object of "providing

. meaningful technical information beyond that obtained

in the normal startup test program and to provide  !

supplemental training" is fulfilled by alternate 4 training and testing without the possible detrimental effects of the originally proposed test.- The above .

conclusions are supported by the Station Blackout Report submitted to the NRC by MP&L April 3, 1986.

2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated since it will not result in hardware or operating procedure changes. ,

! 3. There is no significant reduction in margin of safety

since the intent of performing alternate testing '

' is to avoid degradation of plant equipment. As shown in the above referenced Station Blackout report the

, training goals are being met through alternate testing.

The Station Blackout Report itself provided additional analytical information on plant performance under SB0 conditions.

l Therefore, deleting the requirement to conduct a special simulated loss of onsite alternating-current power test and instead demonstrating the adverse impact of such a test and i implementing the BWR Owners' recommendations for compliance i with I.G.1 does not involve a significant hazards L consideration.  :

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i i

(a) Control Room Design Review (I.D.I. SER; Appendia E. SSER #2 55ER #4, 55ER f5)

Prior to startup following the first refueling outage, MP&L l shall demonstrate the ability to maintain an effective temperature" condition of 85'F or less in the remote shut-down panel (RSP) room for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with an ambient outdoor temperature of at least 95'F.

(b) TrainingDuringLow-PowerTestino(I.G.I.SER) nret-4ati conauct a speciai test, stamistea Loss e

and OffsflPA atin -Current Power Te escribed in INSERT ' the MP&L letter date . 1 . At least 4 weeks prior to performin a P&L shall provide a safety an r this test and its pro o NRC for nd accroval.
(c) Post Accident Samp1tne (11.B.3 SER $$ER fl. SSER #4
55ER f5) ,

Prior to startup following the first refueling outage. MP&L shall incorporate the additional requirements into the procedure for relating radionuclide caseous and ionic l species to estimate core damage as d'scussed in Section 11.8.3.1 of SSER F4.

(d) _ Hydrogen Control (Section 11.8.7. SER SSER #2 SSER f3 55ER#4,55ERF5)

(1) During the first cycle of operation, MP&L shall maintain a suitable program of analysis and testing of the installed hydrogen ignition system. MP&L shall submit to the NRC quarterly reports on the status of their research programs.

(a) MP&L shall amend its research program on hydrogen control measures to include, but not be limited to, the following items:

1) Perform containment sensitivity analysis to determine the adequacy of the hydrogen control system for a spectrum of degraded core accidents including the determination of accident sequences for which equipment .

survivability is assured

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Insert to Operating License Condition 2.C(33)(b)

Prior to restart following the first refueling outage, MPAL shall coitplete the additional training and testing related to TMI Action Plan I.G.1 as described in Section 2.3 of the MP&L submittal dated April 3, 1986.

J13ATTC86062701 - 3