ML20154A443

Proposed Tech Spec Table 3.6-1,adding 16 Containment Isolation Valves,Including 8 post-accident Sampling Sys Valves Installed During 1983 Refueling Outage

ML20154A443
Person / Time
Site:	Rancho Seco
Issue date:	02/28/1986
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20154A430	List: ML20154A427 ML20154A443
References
NUDOCS 8603040043
Download: ML20154A443 (24)

Text

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. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.6-1 111>< CONTAINMENT ISOLATION VALVES VALVE NUMBER DESCRIPTION MAXIMUM CLOSURE TIME (SEC) 111> SFV 53612 RB Atm. Purge Sampl e, AB Si de. . . . . . . . . . . . . . . . . . . . . . . 25 SFV 53613 RB Atm. Rad Sample, AB Side......................... 25

,, SFV 60003 RC Sy s. D rai n I sol , AB Si de. . . . . . . . . . . . . . . . . . . . . . . . . . . 25 SFV 66308 RB Normal Sump Drain, AB Side......................... 25 SFV 92520 Przr. Ni trogen I sol . , AB Side. . . . . . . . . . . . . . . . . . . . . . . . . 25 SFY 53610 RB Press. Equalizer, AB Side.......................... 25 SFV 60002 RC Sys tem Vent I sol . , AB Si de. . . . . . . . . . . . . . . . . . . . . . . . . 25 SFV 60004 RC Sys tem D rai n I sol . , AB Si de. . . . . . . . . . . . . . . . . . . . . . . . 25 SFV 66309 RB No rmal Sump D rai n , AB Si de . . . . . . . . . . . . . . . . . . . . . . . . . 25 SFV 70002 Pzrz. Liquid Sample Isol., AB Side.................... 26 SFV 72502 Pzrz. Gas Sampl e I sol . , AB Si de. . . . . . . . . . . . . . . . . . . . . . . 25

• • HV 20611 OTSG 's Bl owdown I sol . , AB Side. . . . . . . . . . . . . . . . . . . . . . . . 22

• • HV 20593 OTSG- A Sampl e I sol . , AB Si de . . . . . . . . . . . . . . . . . . . . . . . . . . 12

• • HV 20594 OTSG-B Sample Isol., AB Side.......................... 5 SFV 53603 RB Press. Equalizer, RB Side. . . . . . . . . . . . . . . . . . . . . . . . . . 25 SFY 60001 RC Sys . Vent I sol , RB Si de . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 SFV 70001 Pzrz. Liquid Sample I sol . , RB Side. . . . . . . . . . . . . . . . . . . . 25 SFY 70003 Przr. Vapor Sampl e Isol . , RB Side. . . . . . . . . . . . . . . . . . . . . 25

< SFV 72501 Prz r. Gas Sampl e I sol . , RB Si de. . . . . . . . . . . . . . . . . . . . . . . 25

• SFV 46014 RB CCW Supply, AB Side......,......................... 14

• SFV 46203 RB CCW Return, RB Side.......... ..................... 14

• SFY 46204 RB CCW Return, AB Side................................ 18

• SFV 46906 CRD Cooling Water Supply, AB Side..................... 13

• SFY 46907 CRD Cooling Water Return, RB Side. . . . . . . . . . . . . . . . . . . . . 14

• SFV 46908 CRD Cool ing Water Return, AB Side. . . . . . . . . . . . . . . . . . . . . 11 111> ** HV 20609 OTSG-A Bl owdown I sol . , RB Si de. . . . . . . . . . . . . . . . . . . . . . . . 15

• • HV 20610 OTSG-B Bl owdown I sol . , RB C i de. . . . . . . . . . . . . . . . . . . . . . . . 14 SFV 22023 RC Sys. Letdown, RB Side.............................. 25

< SFY 22009 RC Sys. Letdown, AB Side.............................. 25 SFV 24004 RC Pump Seal Return, RB Side.......................... 71 SFV 24013 RC Pump Seal Return, AB Side.......................... 12

• Manual initiation signal (no auto. initiation).

111><** Administrative controls are established to allow opening of these valves during power operation.

Proposed Amendment No. 111 3-40 I

B603040043 ADOCK gh2 PDR PDR P

F RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 111> Table 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES VALVE NUMBER DESCRIPTION MAXIMUM CLOSURE TIME (SEC)

SFV-53615 Reac tor Buil ding Hydrogen Pu rge. . . . . . . . . . . . . . . . . . . . . . . 25 SFV-53616 Reactor Buil ding Hydrogen P urge. . . . . . . . . . . . . . . . . . . . . . . 25 HV -53617 Reactor Buil ding Hydrogen Pu rge. . . . . . . . . . . . . . . . . . . . . . . 25 HV -53618 Reactor Building Hydrogen Purge. . . . . . . . . . . . . . . . . . . . . . . 25

, HV -53620 Hy d roge n Rec ombi n e r s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 5 HV -53621 Hyd rogen Recombi ne rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 HV -53622 Hy d rog e n Rec omb i ne rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 5 HV -53623 Hyd rogen Recombi ne rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25

• • HV -70040 Hydrogen Monitor Containment Outlet Isolation.. .. .... . 25

• • HV -70041 Hydrogen Monitor Containment Inlet Isolation. . . . . . . . . . 25

• • HV -70042 Hydrogen Monitor Containment Inlet Isolation. . . . . . . . . . 25

• • HV -70043 Hydrogen Monitor Containment Outlet Isolation.... . .. .. 25

• • HV -70044 Hydrogen Monitor Containment Outlet Isolation..... . .. . 25

• • HV -70045 Hydrogen Monitor Containment Inlet Isolation. .. . . . . ... 25

• • HV -70046 Hydrogen Monitor Containment Inlet Isolation.. . . . . . .. . 25

• • HV -70047 Hydrogen Monitor Containment Outlet Isolation......... 25

• • Administrative controls are established to allow opening of these valves

< during power operation.

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Proposed Amendment No. 111

F RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.6.7 The Reactor Building Purge Valves, SFV 53503, SFV 53504, SFV 53604, and SFV 53605, shall be closed with their respective breakers de-energized, except during cold shutdown or refueling Valves SFV 53503 and SFV 53604 shall be verified to be in the above condition at least monthly. The breakers / disconnects on valves SFV 53504 and SFY 53605 shall be verified to be de-energized at least monthly.

3.6.8 The Reactor Building Purge Valves shall isolate on high containment radiation level. See Table 3.5.1-1 for operability requirements.

Bases The reactor coolant system conditions of cold shutdown assure that no steam will be formed and hence no pressure buildup in the containment if the reactor coolant system ruptures.

The selected shutdown conditions are based on the type of activities that are being carried out and will preclude criticality in any occurrence.

The Reactor Building is designed for an internal pressure of 59 psig and an external pressure 2.0 psi greater than the internal pressure. The design external pressure corresponds to the differential pressure that could be developed if the building is sealed with an internal temperature of 120 F with a barometric pressure of 29.0 inches of Hg and the building is subsequently cooled to an internal temperature of 80 F with a concurrent rise in barometric pressure to 31.0 inches of Hg.

When containment integrity is established, the limits of 10 CFR 100 will not be exceeded should the maximum hypothetical accident occur.

The OPERABILITY of the containment isolation ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atrosphere by pres-surization of the containment. Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for LOCA.

Specifications 3.6.7 and 3.6.8 are in response to NUREG 0737 item II.E.4.2.

(1) FSAR, section 5 ,

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l Proposed Amendment No. 111 111>< 3-40b

L ATTACliMNT I SAFETY ANALYSIS.

Proposed Amendment No. 111 comprises four general changes being made to Table 3.6-1 of the Rancho Seco Technical Specifications. These changes and considerations of their effects on plant safety are discussed below:

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a. The four reactor building inlet and outlet purge valves: SFV-53503, SFV-53504 and SFV-53604, SFV-53605, respectively, are being deleted from Table 3.6-1. These four valves are administratively closed for all plant conditions above cold shutdown, and thus are judged as not requiring maximum closure times to be shown on Table 3.6-1. The dele-tion of these purge valves from Table 3.6-1 is judged to have no involve-ment with plant safety. The reasons are:

1) The Bur reactor building purge valves are administratively locked closed for all plant conditions above cold shutdown (Operating Procedure A.14, Enclosure 8.10), and their position is verified monthly (Surveillance Procedure SP 205.07). Operability, closure on failure, and acceptable closure time per ASME Subsection IWV of Section XI are tested at cold shutdown (Surveillance Procedure 214.01), and seat leakage checked at each refueling outage.

The above cited administrative controls assure isolability of the reactor building purge valves for all conditions of plant operation, and their deletion from Table 3.6-1 is judged as:

(a) Not involving a significant increase in the probability or con-sequence of an accident previously evaluated. The locked closed condition of these valves during all plant operating modes above cold shutdown and their periodic operability tests assures their isolability as designed.

(b) Not creating the possibility of a new or different kind of accident from any accident previously evaluated. The deletion of the purge valves from Table 3.6-1 in no way introduces a new or different accident condition as administrative controls assure their safe (closed) position.

(c) Not involving a significant reduction in a margin of safety.

Deletion of the four reactor building purge valves from Table 3.6-1 in no way affects the operation of valves which, by administrative controls, ensures that safety margins are not affected,

b. Bechtel Calculations 962-3-0 (Attachment IV) determined that selected con-tainment isolation valves can have maximum closure times of 25 seconds with-out exceeding the release limits established by 10 CFR 100.11. For conservative reasons, the selected valves were those which offer direct flow paths from the containment atmosphere to the environment. It was determined that at a maximum closura time of 25 seconds, these select con-tainment isolation valves would not allow a radiation release to the Exclusion Area Boundary (EAB) or Low Population Zone (LPZ) during the worst accident condition (LOCA) that would exceed the allowance of 10 CFR 100.11. In fact, a very significant margin existed between the cal-culated valves'and those of 10 CFR 100.11.

Based on the calculations of Attachment IV, the maximum closure time of the containment isolation valves, which offer. direct flow paths from the containment atmosphere to the environment,-are being changed to 25 seconds in Table 3.6-1 from the previous values established by in-situ testing. For the= reasons given below, the increase of maximum closure time for these select containment isolation valves are judged to have no adverse effect on plant safety.

1) The change does not involve a significant increase in the probability-or consequence of an accident previously evaluated. The radiation releases to the EAB and LPZ under the worst accident conditions remain well below a fraction of the radiation exposure allowed by 10 CFR 100.11.

-Acceptable performance of the containment isolation valves is assured at all times by the periodic testing of all such valves to the accep-tance requirements of ASME Section XI, Subsection IWV.

2) .The change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The increase of maximum closure times of the select containment isolation valves does not introduce a design or operational change which could result in a new or different accident potential worse than the LOCA considered.

3) The change does not involve a significant reduction in a margin of safety. Although increasing the maximum closure times of the contain-ment isolation valves from the presently specified range of 3 to 21 seconds to 25 seconds is an increase, the Bechtel calculations of Attachment IV confirm that there remains an adequate margin to the safety limits established in 10 CFR 100.11. This change provides greater flexibility in the replacement of parts which are no longer commercially available.

c. Certain control valves in Table 3.6-1 have been identified with a double asterisks to designate them as being under administrative control (occa-sionally open) during plant operation. These valves, and the operating conditions during which they are open are discussed below:

1) HV-20609, 10 and 11 are open above cold shutdown to 15% power for OTSG blowdown (Operating Procedures A.6 and B.2).

2) HV-20593 and 94 are similarly opened below 15% power for 0TSG sampling.

The same operating procedures as for Item 1 above, apply.

3) The hydrogen monitoring valves of the Post Accident Sampling System HV-70040 through 47 are occasionally opened during operation per-Operating Procedure A.ll. These valves are opened, as necessary, for sampling Pressurizer liquid, RCS and the Decay Heat System.

The safety consequences of opening these valves during certain periods of power operation have been previously established in the preparation and issuance of the operating procedures referenced above. The designation of these valves in Table 3.6-1 as being under administrative control is judged an administrative change that has no involvement with plant safety.

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d. The title of Table 3.6-1 is being changed from " Safety Features Ccntain--

ment Isolation Valves" to " Containment Isolation Valves" since the listed valves are not exclusively safety features actuated.. This title change is considered purely administrative, and _is judged to have:no involvement' with plant safety.

7 ATTAC K NT II "N0 SIGNIFICANT HAZARDS" EVALUATION Proposed Amendment No. 111 consists of four general changes to Table 3.6-1 of the Rancho Seco Technical Specifications. For the reasons given below with respect to each general change, and in consideration of the examples given in 48 FR 14870 for evaluating significant hazards, the changes are judged as not involving a "significant hazards consideration:"

1. The four reactor building purge valves are being deleted from Table 3.6-1.

These valves, through administrative contro s, are locked closed during power operation and tnus need not have their maximum closure time specified in the technical specifications.

This change is considered purely administrative and has no involvement with plant safety. Procedural controls exist which maintain these valves in the safe (locked closed) condition during plant operation. Therefore, this administrative change is considered not likely to involve significant hazards considerations.

2. Bechtel calculations (Attachment IV) have determined that the containment isolation valves in Table 3.6-1 which are in direct flow paths from the containment atmosphere to the environment can have maximum closure times much higher than those presently specified without exceeding a significant

~ fraction of the allowable radiation releases established by 10 CFR 100.11.

The existing values of maximum closure times for the selected containment isolation valves range from 3 to 21 seconds, based on in-situ tests. FSAR calculations established that the resulting radioactive releases would not exceed the releases allowed by 10 CFR 100.11 in the worst accident condition (LOCA).

Increasing the maximum closure time of these select containment isolation valves to 25 seconds is considered not likely to involve significant hazards considerations under guidance of example (vi) of 48 FR 14870 which states:

"A change which either may result in some increase to the probability or consequences of a previously-analyzed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria with respect to the system or component specified in the Standard Review Plan: for example, a change resulting from the appli-cation of a small refinement of a previously used calculational model or design method."

The increase in maximum closure time of the selected containment isolation valves are clearly shown in Attachment IV to be well within the acceptable criteria.of 10 CFR 100.11, and thus are judged not likely to involve signi-ficant hazards considerations.

3. Certain control valves in Table 3.6-1 which are occasionally opened during operation are being designated by double asterisks as being administratively controlled. The proposed designation of these control valves as being under existing administrative control is judged not likely to involve sig-nificant hazards considerations since the change is purely administrative as described in Example (i) of 48 FR 14870.

-2 .

24. The title of Table 3.6-l'is being- changed from " Safety Features Contain '

ment-Isolation Valves" to " Containment-Isolation. Valves" since the listed

. valves are not exclusively safety features actuated. This. change is

' purely administrative which,.through guidance given in 48.FR 14870, Example (i) is judged not likely to. involve significant hazards consid-

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erations.

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ATTACHMENT III DESCRIPTION OF PROPOSED CHANGES

1. Table 3.6-1, page 3-40: Deleted Reactor Building Purge Valves HV-53503, HV-53504, HV-53604 and HV-53605.

2. Table 3.6-1, page 3-40: Increased maximum closure time to 25 seconds for valves SFV-53612, SFV-53613, SFV-60003, SFV-66308, SFV-92520, SFV-53610, SFV-60002, SFV-60004, SFV-66309, SFV-70002, SFV-72502, SFV-53603, SFV-60001, SFV-70001, SFV-70003, SFV-72501, SFV-22023 and SFV-22009.

3. Table 3.6-1, page 3-40: Added double asterisk designations to valves HV-20611, HV-20593, HV-20594, HV-20609 ar.J H"-20610.

4 Table 3.6-1, page 3-40: Added following footnote:

• • Administrative controls are established to allow opening of these valves during power operation.

5. Table 3.6-1, page 3-40: Changed title ' rom " Safety Features Containment Isolation Valves" to " Containment Isolation Valves."

6. Table 3.6-1 (continued) page 3-40a: Added new page of containment isolatior valves which were installed in 1983, and assigned double asterisks with footnote to valves HV-70040 through HV-70047.

7. Changed existing page 3-40a to 3-40b.

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