ML19309B143

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Proposed Changes to Tech Spec Figures,6.2-1,6.2-2 & Tech Specs 6.5.1.2,6.5.1.8,6.5.2.2 & 6.5.3.1 Re Organization & Responsibilities & Figure 3.2-3 & Bases 2.1.1 Re Change in Rod Bow Penalty Calculation
ML19309B143
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 03/28/1980
From:
ALABAMA POWER CO.
To:
Shared Package
ML19309B141 List:
References
NUDOCS 8004030194
Download: ML19309B143 (10)
v • d • e


Text

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SAFETY EVALUATION FOR TECH. SPEC. CHANGE BASIS:

The changes in the off-site organization are being made to consolidate the Company nuclear program under one executive officer.

The changes in the Facility Organization are being made to enhance the daily and long term operation of the plant.

(No

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positions are being deleted by this change.)

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i ENECUTIVE VICE PRESIDENT 5x SENIOR E

VICE PRESIDENT NORB y

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VICE PRESIDENT NUCLEAR GENERATION

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MANAGER MANAGER MANAGER OPERATIONS NUCLEAR ENGINEERINC NUCLEAR GENERATION QUALITY ASSURANCE

& TECHNICAL SUPPOR1 i

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PLANT MANAGER STAFF STAFF g pp FARLEY

  • Corporate respor sibility for PLANT STAFF fire protection program Figure 6.2-1 Offsite Organization for Facility Management and Technical Support I

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SL - Senior Operator's License

- Re:ctor operstors wm have operator's Licenic Figure 6.2-2 Facility Organization - Joseph M. Farley Unit No.1

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' - Onsite Responsibi'ity fo Fire Frctection Prr. gram t-Will Be Impic=ented Prior to Unit 2 Fuel Load u

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AD:4IlllSTRATIVE C0:ITROLS Or V'

6_. 3 FACILITY STAF~ 03AllFICAT!T;S 6.3.1 Each rember of the facility staff shall r.eet or cxceed the minimum

  • qualifications of A::SI :;15.1-1971 for comparable positions, except for the Chemistry and Health Physics Supervisor who shall meet ~or exceed the qualifications of Regulatory Guide 1.8, September 1975.*

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6.4 TRAII:I:lG 6.4.1 A retraining and replace-ent training program for the facility staff shall be maintained under the direction of the Training Supervisor and shall neet or exceed the requirements and recommendations of Section 5.5 of A:iSI fil8.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A training progran for the Fire Brigade shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements of Section 27 of the i;FPA Code-1976.

6.5 REVIEW A:19 AUDIT 6.5.1 PLA::T OPERATIO :S REVIEU COMMITTEE (PORC)

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6.5.1.1 The PORC shall function to advise the Plant.11anager on all matters related to nuclear safety.

COMP 0SITIO::

6.5.1.2 The PORC shall be composed of the:

Chairman:

Plant lianager Vice Chairman:

Assistant Plant lianager 14 ember:

Technical Superintendent lienber:

Operations Suerintendent flember: (flon-Voting)

Plant Quality Assurance Engineer llenber:

flaintenance Superintendent Me4en Perf % cc ~4 A no;3 sqWed eh Al.TERi!ATES 6.5.1.3 All alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than one alter-nate shall participate as voting members iri PORC activities at any one tirae.

  • The itinimum qualifications requirement for the Chemistry and Health Physics Supervisor shall.become effective when the initial incumbent in this position is replaced.

Amendmentflo.f.)[

FARLEY - UtilT 1 6-5 i

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admit 11STP.ATIVE CONTROLS j.

The plant Security Plan.

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The Emergency Flan.

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Facility operations to detect potential nuclear safety hazards.

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Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Nuclear Operations Review Board.

AUTHORITY 6.5.1.7 The PORC shall:

a.

Recommend to the Plant Manager written approval or disapproval of items considered under 6.5.1.6(a) through (e) and(j)and(k)above.

b.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a), (c) and (d) above

' constitutes an unreviewed safety question.

c.

Make recommendations to the Plant Manager in writing that actions reviewed under 6.5.1.6(b) above did not constitute an unreviewed safety question.

RECORDS 6.5.1.8 The PORC shall maintain written minutes of each meeting and k

copies shall be provided to the Vice President-Nud.e.or and Chairman of the Nuclear Operations Review Board.

gyy,t;,n 6.5.2 NUCLEAR OPERATIONS REVIEW BOARD NORB FUNCTION 6.5.2.1 The fl0RB shall function to provide independent review and audit of designated activities in the areas of:

a.

Nuclear power plant operations b.

Nuclear engineering c.

Chemistry and radiochemistry

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FARLEY - UNIT 1 6-7 r-l 1

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R ADMIllISTRATIVE C0ilTROLS 4

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fletallurgy

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Instrumentation and control c.

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Radiological safety

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Mechnical and electrical engineering (k

h.

Quality assurance practices COMPOSITION 6,5.2.2 The tiORB shall be composed of at least five persons including; 1

Chairman:

Senior Vice President Vice Chairman:

Vice President-Pra 'ucticr. Lim C,edco.

Altern:tc Vice Chair--

Vice President P:,; r Supply Scryices y

Secretary:

llanager-0perations Quality Assurance 11 ember:

Manager-!1uclear Generation MeAw:

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and other appointed personnel having' an academic degree in an engineering or physical sciencefield and a minimum of' five years technical experience, of which a minimum of three years shall be in one or more of the areas given in 6.5.2.1.,

ALTERNATES

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6.5.2.3 All alternate members shall be appointed in writing by the

.gg tiORB Chairman to serve on a temporary basis; however, no more than

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two alternates shall participate as voting members in NORB activities at any one time.

C0tlSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NORB Chairman to provide expert advice to the NORB.

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[1EETIt!G FREQUENCY 2

6.5.2.5 The TIROS shall meet at least once per calendar quarter during

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the initial year of facility operation following fuel loading and at least once per six months thereafter.

<.r 6fii MWt FARLEY

, UNIT 1 6-8 Amendment flo. 7 p'c'1 i

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.AD:11tilSTRATIVE CONTROLS 7'

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a.

Minutes of each !!ORG meeting shall be pre;)arett, ' approved and forwarded to the Senior Vice President uithin 14 days followinc,each meeting.

b.

Reports of reviews encorrpassed by Section 6.5.2.7. above, shall be prepared, approved and forwarded to the Senior Vice President within 14 days following completion of the review.

Audit reports encompassed by Section' 6.5.2.8 above, shall be c.

forwarded 'to the Senior Vice President and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.5.3 TECHfilCAL REVIEW APID CONTROL ACTIVITIES -

c 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:

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a.

Procedures required by Technical Specification 6.8 and other procedures which affect plant nuclear safety, and changes (other than editorial or typographical changes) thereto, shall

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be prepared, reviewed and approved.

Each such procedure or N...

procedure change shall be reviewed by an individual / group other c

than the individual / group which prepared the procedure or pro-cedure change, but who may be from the same organization as the individual / group which prepared the procedure or procedure change.

Procedures other than Administrative Procedures will be approved by either the Technical Superintendent, the Opera-* Nsed tions Superintendent, the Maintenance Superintendent-c. th:

Assistant Plant Manager as applicable." The Plant Manager will approve administrative procedures, security -implementing procedures and emergency plan implementing procedures, Tempo-rary changes to procedures which clearly do not change the intent of the approved procedures uill be approved by two members of the plant staff, at least one of whom holds a Senior Reactor Oper W 's License.

For changas to procedures which may involve a change in intent of the ap roved procedures, the person authorized above to anprove the proi

'ure shall ap-prove the change.

b.

Proposed changes er modifications to plant nuclear safety -

related structures, systems and components shall be reviewed as designated by the Plant Manager.

Each such modification shall be reviewed by an individual / group other than the individual / group uhich designed the modification, but who may be from the same organization as the individual / group which Nh designed the modifications.

Proposed modifications to plant

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nuclear safety-related structures, systems and components shall be approved prior to implementation by the Plant Manager.

FARLEY - UNIT 1 6-11 Amendment !!o. p, k jNc. hevhmxce, 3,d h an,s;,,hpak,.A d d Sihted S

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Safety Evaluation for Technical Specification Changes Associated with Reduced Rod Bow Penalty

Background:

The present rod bow penalty on the enthalpy hot channel factor (F H) in 3

the Farley Plant Technical Specifications is based on a linear relationship assumption between DNBR penalty and fractional rod gap closure.

The NRC has approved a new reduced DNBR penalty as a function of gap closure based en partial bow test data. A reduction in rod bow penalty improves plant operational flexibility.

References:

(1) Technical Specification Paragraphs 2.1.1 and B 3/4.2.5 and Figure 3.2-3.

(2)

NS-CE-1580 letter from C. E. Eicheldinger (Westinghouse) to D. F. Ross, Jr.

(NRC) dated October 24, 1977.

(3) NRC letter J. F. Stolz (NRC) to T. M. Anderson (Westinghouse), dated April 5,1979.

(4)

NS-TMA-1760, " Fuel Rod Bowing", T. M. Anderson (Westinghouse) to J. F. Stolz (NRC), dated April 19, 1978.

Bases:

The present DNBR penalty due to gap closure was assumed linear which resulted in the current rod bow penalty to F H, Reference (1). The new curve combines 6

the amount of rod bow versus burnup for Westinghouse 17x17 plants in Reference (2), with the rod bow penalty versus amount of rod bow given by the NRC in 4

Reference (3).

The curve in Reference (3) is converted to the enclosed Figure by the following methods: 1.8" change in DNBR equals to 1.0% change in F H.

The conversion method 3

j from gap closure to region average burnup is documented in Refer 1nce (4).

The change only incorporates recent approval on partial bow data and does not i

reduce the margin of safety as defined in the basis for this speci'ication or as defined in the FSAR.

==

Conclusion:==

The reduction in rod bow penalty based on partial bow test data does not involve an unreviewed safety question as defined by 10CFR50.59, 1

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g d8B Figure 3.2-3 Rod Bow Penalty (RBP)

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Region Average Burnup FARLEY - Unit 1 3/4 2-10a i

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1 SAFETY LIMITS

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and a reference cosine with a peak of 1.551 r~ axial power shah., of 1.55 -

The curves are based on an enthalpy hot channel factor, F An N

allowance is included for an increase in F at reduced power based on AH the expression:

N zc5co y [ gg & 33,owd LH < l.55 [1 + 0.2 (1-P)] [ g-RBP(BU)]

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__ o., oo for-khere: RBP(BU) =.0' ;' i.i56/ + 0.0553; GUTim DU - 400 g andR3P(BU)=0forbli M [ 2.6.500 $

1 These limiting heat flux conditions are higher than ihose calculated for the range of all control rods fully withdrawn to the Caximum allowable' control rod insertion assuming the axial power imbalance h within the limits of the f, (AI) function of the Overtemperature trip: When t%

axial power imb61ance is not within the tolerance, the axial popr

  • imbalance eff.ect on the Overtemperature AT trips will r duck tht-setpoints f..

e to provide protection consistent with core safety limit $.

2.1.2" REACTOR COOLANT SYSTEM PRESSURE The restriction of this Safety Limit protects the integrity of the Reactor Coolant System from overpressurization and thereby prevents the release of radionuclides contained in the reactor coolant from reaching the containment atmosphere.

The reactor pressure vessel pressurizer and the reactor coolant system piping and fittings are designed to Section III of the ASME Code for Nuclear Power Plant which permits a Tr.aximum transient pressure of 110% (2735 psig) of design pressure.

The Safety Limit of 2735 psig is therefore consistent with the design criteria and associated code requircaents.

The entire Reactor Coolant System is hydrotested at 3107 psig,125%

of design pressure, to demonstrate integrity prior to initial operation.

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FARLEY - UNIT 1 B 2-2 faendment No. '8 I

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